Sample records for determination site characterization

  1. Double tracks test site characterization report

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy`s (DOE) Streamlined Approach for Environmental Restoration (SAFER).

  2. Characterizing Commercial Sites Selected for

    E-Print Network [OSTI]

    selected for energy efficiency monitoring Prepared by Hawai`i Natural Energy Institute School of Ocean such as solar thermal absorption chillers, building energy management systems, and advanced lighting. The twoCharacterizing Commercial Sites Selected for Energy Efficiency Monitoring This report presents data

  3. Instrumentation for CTA site characterization

    E-Print Network [OSTI]

    Fruck, Christian; Ernenwein, Jean-Pierre; Mandát, Dušan; Schweizer, Thomas; Häfner, Dennis; Bulik, Tomasz; Cieslar, Marek; Costantini, Heide; Dominik, Michal; Ebr, Jan; Garczarczyk, Markus; Lorentz, Eckart; Pareschi, Giovanni; Pech, Miroslav; Puerto-Giménez, Irene; Teshima, Masahiro

    2015-01-01T23:59:59.000Z

    Many atmospheric and climatic criteria have to be taken into account for the selection of a suitable site for the next generation of imaging air-shower Cherenkov telescopes, the "Cherenkov Telescope Array" CTA. Such data are not available with sufficient precision or the comparability to allow for a comprehensive characterization of the proposed sites to be made. Identical cross-calibrated instruments have been developed which allow for precise comparison between sites, the cross-validation of existing data, and the ground-validation of satellite data. The site characterization work package of the CTA consortium opted to construct and deploy 9 copies of an autonomous multi-purpose weather sensor, incorporating an infrared cloud sensor a newly developed sensor for measuring the light of the night sky, and an All-Sky-Camera, the whole referred to as Autonomous Tool for Measuring Observatory Site COnditions PrEcisely (ATMOSCOPE). We present here the hardware that was combined into the ATMOSCOPE and characterize ...

  4. Preliminary Site Characterization Report, Rulsion Site, Colorado

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    This report is a summary of environmental information gathered during a review of the documents pertaining to Project Rulison and interviews with personnel who worked on the project. Project Rulison was part of Operation Plowshare (a program designed to explore peaceful uses for nuclear devices). The project consisted of detonating a 43-kiloton nuclear device on September 10, 1969, in western Colorado to stimulate natural gas production. Following the detonation, a reentry well was drilled and several gas production tests were conducted. The reentry well was shut-in after the last gas production test and was held in standby condition until the general cleanup was undertaken in 1972. A final cleanup was conducted after the emplacement and testing wells were plugged in 1976. However, some surface radiologic contamination resulted from decontamination of the drilling equipment and fallout from the gas flaring during drilling operations. With the exception of the drilling effluent pond, all surface contamination at the Rulison Site was removed during the cleanup operations. All mudpits and other excavations were backfilled, and both upper and lower drilling pads were leveled and dressed. This report provides information regarding known or suspected areas of contamination, previous cleanup activities, analytical results, a review of the regulatory status, the site`s physical environment, and future recommendations for Project Ruhson. Based on this research, several potential areas of contamination have been identified. These include the drilling effluent pond and mudpits used during drilling operations. In addition, contamination could migrate in the gas horizon.

  5. Natural phenomena hazards site characterization criteria

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    The criteria and recommendations in this standard shall apply to site characterization for the purpose of mitigating Natural Phenomena Hazards (wind, floods, landslide, earthquake, volcano, etc.) in all DOE facilities covered by DOE Order 5480.28. Criteria for site characterization not related to NPH are not included unless necessary for clarification. General and detailed site characterization requirements are provided in areas of meteorology, hydrology, geology, seismology, and geotechnical studies.

  6. Second ILAW Site Borehole Characterization Plan

    SciTech Connect (OSTI)

    SP Reidel

    2000-08-10T23:59:59.000Z

    The US Department of Energy's Hanford Site has the most diverse and largest amounts of radioactive tank waste in the US. High-level radioactive waste has been stored at Hanford since 1944. Approximately 209,000 m{sup 3} (54 Mgal) of waste are currently stored in 177 tanks. Vitrification and onsite disposal of low-activity tank waste (LAW) are embodied in the strategy described in the Tri-Party Agreement. The tank waste is to be retrieved, separated into low- and high-level fractions, and then immobilized. The low-activity vitrified waste will be disposed of in the 200 East Area of the Hanford Site. This report is a plan to drill and characterize the second borehole for the Performance Assessment. The first characterization borehole was drilled in 1998. The plan describes data collection activities for determining physical and chemical properties of the vadose zone and saturated zone on the northeast side of the proposed disposal site. These data will then be used in the 2005 Performance Assessment.

  7. NRC staff site characterization analysis of the Department of Energy`s Site Characterization Plan, Yucca Mountain Site, Nevada

    SciTech Connect (OSTI)

    NONE

    1989-08-01T23:59:59.000Z

    This Site Characterization Analysis (SCA) documents the NRC staff`s concerns resulting from its review of the US Department of Energy`s (DOE`s) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation`s first geologic repository for high-level radioactive waste. DOE`s SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC`s specific objections related to the SCP, and major comments and recommendations on the various parts of DOE`s program, are presented in SCA Section 2, Director`s Comments and Recommendations. Section 3 contains summaries of the NRC staff`s concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE`s program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC`s responsibilities with respect to DOE`s SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs.

  8. Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

    1992-01-01T23:59:59.000Z

    This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

  9. International Symposium on Site Characterization for CO2Geological Storage

    SciTech Connect (OSTI)

    Tsang, Chin-Fu

    2006-02-23T23:59:59.000Z

    Several technological options have been proposed to stabilize atmospheric concentrations of CO{sub 2}. One proposed remedy is to separate and capture CO{sub 2} from fossil-fuel power plants and other stationary industrial sources and to inject the CO{sub 2} into deep subsurface formations for long-term storage and sequestration. Characterization of geologic formations for sequestration of large quantities of CO{sub 2} needs to be carefully considered to ensure that sites are suitable for long-term storage and that there will be no adverse impacts to human health or the environment. The Intergovernmental Panel on Climate Change (IPCC) Special Report on Carbon Dioxide Capture and Storage (Final Draft, October 2005) states that ''Site characterization, selection and performance prediction are crucial for successful geological storage. Before selecting a site, the geological setting must be characterized to determine if the overlying cap rock will provide an effective seal, if there is a sufficiently voluminous and permeable storage formation, and whether any abandoned or active wells will compromise the integrity of the seal. Moreover, the availability of good site characterization data is critical for the reliability of models''. This International Symposium on Site Characterization for CO{sub 2} Geological Storage (CO2SC) addresses the particular issue of site characterization and site selection related to the geologic storage of carbon dioxide. Presentations and discussions cover the various aspects associated with characterization and selection of potential CO{sub 2} storage sites, with emphasis on advances in process understanding, development of measurement methods, identification of key site features and parameters, site characterization strategies, and case studies.

  10. Characterization of Commercial Sites Selected for

    E-Print Network [OSTI]

    Energy Institute School of Ocean and Earth Science and Technology University of Hawai`i January 2014 #12Characterization of Commercial Sites Selected for Energy Efficiency Monitoring Prepared for the U.S. Department of Energy Office of Electricity Delivery and Energy Reliability Under Cooperative Agreement No. DE

  11. Expedited site characterization. Innovative technology summary report

    SciTech Connect (OSTI)

    NONE

    1998-12-01T23:59:59.000Z

    Expedited Site Characterization (ESC) has been developed, demonstrated, and deployed as a new time-saving, cost-effective approach for hazardous waste site investigations. ESC is an alternative approach that effectively shortens the length of the assessment period and may significantly reduce costs at many sites. It is not a specific technology or system but is a methodology for most effectively conducting a site characterization. The principal elements of ESC are: a field investigation conducted by an integrated team of experienced professionals working in the field at the same time, analysis, integration and initial validation of the characterization data as they are obtained in the field, and a dynamic work plan that enables the team to take advantage of new insights from recent data to adjust the work plan in the field. This report covers demonstrations that took place between 1989 and 1996. This paper gives a description of the technology and discusses its performance, applications, cost, regulatory and policy issues, and lessons learned.

  12. Characterizing Surface Acidic Sites in Mesoporous-Silica-Supported...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Surface Acidic Sites in Mesoporous-Silica-Supported Tungsten Oxide Catalysts Using Solid State NMR and Quantum Characterizing Surface Acidic Sites in Mesoporous-Silica-Supported...

  13. Expedited Site Characterization: A rapid, cost-effective process for preremedial site characterization

    SciTech Connect (OSTI)

    Burton, J.C.; Walker, J.L.; Jennings, T.V.; Aggarwal, P.K.; Hastings, B.; Meyer, W.T.; Rose, C.M.; Rosignolo, C.L.

    1993-11-01T23:59:59.000Z

    Argonne National Laboratory has developed a unique, cost- and time-effective, technically innovative process for preremedial site characterization, referred to as Expedited Site Characterization (ESC). The cost of the ESC field sampling process ranges from 1/10 to 1/5 of the cost of traditional site characterization. The time required for this ESC field activity is approximately 1/30 of that for current methods. Argonne`s preremedial site investigations based on this approach have been accepted by the appropriate regulatory agencies. The ESC process is flexible and neither site nor contaminant dependent. The process has been successfully tested and applied in site investigations of multiple contaminated landfills in New Mexico (for the US Department of the Interior`s Bureau of Land Management [BLM]) and at former grain storage facilities in Nebraska and Kansas, contaminated with carbon tetrachloride (for the Department of Agriculture`s Commodity Credit Corporation [CCC/USDA]). A working demonstration of this process was sponsored by the US Department of Energy (DOE) Office of Technology Development as a model of the methodology needed to accelerate site characterizations at DOE facilities. This report describes the application of the process in New Mexico, Nebraska and Kansas.

  14. Site Characterization Work Plan for Gasbuggy, New Mexico

    SciTech Connect (OSTI)

    DOE/NV

    2000-12-14T23:59:59.000Z

    Project Gasbuggy was the first of three joint government-industry experiments conducted to test the effectiveness of nuclear explosives to fracture deeply buried, low-permeability natural gas reservoirs to stimulate production. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the Project Gasbuggy Site. Its goal is the collection of data in sufficient quantity and quality to determine current site conditions, support a risk assessment for the site surfaces, and evaluate if further remedial action is required to achieve permanent closure of the site that is both protective of human health and the environment. The Gasbuggy Site is located approximately 55 air miles east of Farmington, New Mexico, in Rio Arriba County within the Carson National Forest in the northeast portion of the San Juan Basin. Historically, Project Gasbuggy consisted of the joint government-industry detonation of a nuclear device on December 10, 1967, followed by reentry drilling and gas production testing and project evaluation activities in post-detonation operations from 1967 to 1976. Based on historical documentation, no chemical release sites other than the mud pits were identified; additionally, there was no material buried at the Gasbuggy Site other than drilling fluids and construction debris. Although previous characterization and restoration activities including sensitive species surveys, cultural resources surveys, surface geophysical surveys, and limited soil sampling and analysis were performed in 1978 and again in 2000, no formal closure of the site was achieved. Also, these efforts did not adequately address the site's potential for chemical contamination at the surface/shallow subsurface ground levels or the subsurface hazards for potential migration outside of the current site subsurface intrusion restrictions. Additional investigation activities will focus on the surface/shallow subsurface sampling and modeling. Suspected potential contaminants of concern for investigative analysis at the Gasbuggy Site include total petroleum hydrocarbons (diesel- and gasoline-range), volatile organic compounds, semivolatile organic compounds, total Resource Conservation and Recovery Act metals, and radionuclides. The results of this characterization and risk assessment will be used to evaluate corrective action alternatives to include no further action, the implementation of institutional controls, capping on site, or off-site disposal of contaminated waste which will be presented in a subsequent corrective action decision document.

  15. Coupled Site Characterization and Foundation Analysis Research Project

    E-Print Network [OSTI]

    Horvath, John S.

    Engineering Department Bronx, New York, U.S.A. March 2000 #12;Coupled Site Characterization and Foundation Engineering Department Bronx, NY 10471-4098 U.S.A. e-mail: #12;iii Coupled SiteCoupled Site Characterization and Foundation Analysis Research Project: Rational Selection

  16. Preliminary siting characterization Salt Disposition Facility - Site B

    SciTech Connect (OSTI)

    Wyatt, D.

    2000-01-04T23:59:59.000Z

    A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

  17. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-09-09T23:59:59.000Z

    The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP.

  18. Bioremediation demonstration on Kwajalein Island: Site characterization and on-site biotreatability studies

    SciTech Connect (OSTI)

    Siegrist, R.L.; Korte, N.E.; Pickering, D.A. (Oak Ridge National Lab., TN (United States)); Phelps, T.J. (Tennessee Univ., Knoxville, TN (United States))

    1991-09-01T23:59:59.000Z

    An environmental study was conducted during February 1991 on Kwajalein Island, a US Army Kwajalein Atoll (USAKA) Base in the Republic of the Marshall Islands (RMI). This study was undertaken for the US Department of Energy (DOE) Hazardous Waste Remedial Actions Program (HAZWRAP) acting in behalf of USAKA. The purpose of the study was to determine if selected locations for new construction on Kwajalein Island were contaminated by petroleum hydrocarbons as suspected and, if so, whether bioremediation appeared to be a feasible technology for environmental restoration. Two different sites were evaluated: (1) the site planned freshwater production facility and (2) a site adjacent to an aboveground diesel fuel storage tank. Within the proposed construction zone for the freshwater production facility (a.k.a desalination plant), total petroleum hydrocarbons (TPH) where either absent or at low levels. Characterization data for another potential construction site adjacent to an aboveground diesel fuel storage tank southeast of the old diesel power plant revealed high concentrations of diesel fuel in the soil and groundwater beneath the site. Results of this investigation indicate that there are petroleum-contaminated soils on Kwajalein Island and bioremediation appears to be a viable environmental restoration technique. Further experimentation and field demonstration are required to determine the design and operating conditions that provide for optimum biodegradation and restoration of the petroleum-contaminated soils. 17 refs., 7 figs., 26 figs.

  19. TWRS phase I privatization site environmental baseline and characterization plan

    SciTech Connect (OSTI)

    Shade, J.W.

    1997-09-01T23:59:59.000Z

    This document provides a plan to characterize and develop an environmental baseline for the TWRS Phase I Privatization Site before construction begins. A site evaluation study selected the former Grout Disposal Area of the Grout Treatment Facility in the 200 East Area as the TWRS Phase I Demonstration Site. The site is generally clean and has not been used for previous activities other than the GTF. A DQO process was used to develop a Sampling and Analysis Plan that would allow comparison of site conditions during operations and after Phase I ends to the presently existing conditions and provide data for the development of a preoperational monitoring plan.

  20. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-12-14T23:59:59.000Z

    The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP).

  1. Expedited Site Characterization | The Ames Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicy and Assistance100 tonusingdeposition.EnergyExpedited Site

  2. Ames expedited site characterization demonstration at the former manufactured gas plant site, Marshalltown, Iowa

    SciTech Connect (OSTI)

    Bevolo, A.J.; Kjartanson, B.H.; Wonder, J.D.

    1996-03-01T23:59:59.000Z

    The goal of the Ames Expedited Site Characterization (ESC) project is to evaluate and promote both innovative technologies (IT) and state-of-the-practice technologies (SOPT) for site characterization and monitoring. In April and May 1994, the ESC project conducted site characterization, technology comparison, and stakeholder demonstration activities at a former manufactured gas plant (FMGP) owned by Iowa Electric Services (IES) Utilities, Inc., in Marshalltown, Iowa. Three areas of technology were fielded at the Marshalltown FMGP site: geophysical, analytical and data integration. The geophysical technologies are designed to assess the subsurface geological conditions so that the location, fate and transport of the target contaminants may be assessed and forecasted. The analytical technologies/methods are designed to detect and quantify the target contaminants. The data integration technology area consists of hardware and software systems designed to integrate all the site information compiled and collected into a conceptual site model on a daily basis at the site; this conceptual model then becomes the decision-support tool. Simultaneous fielding of different methods within each of the three areas of technology provided data for direct comparison of the technologies fielded, both SOPT and IT. This document reports the results of the site characterization, technology comparison, and ESC demonstration activities associated with the Marshalltown FMGP site. 124 figs., 27 tabs.

  3. Determination of ecologically vital groundwaters at selected sites in the Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    Vinikour, W.S.; Yin, S.C.L.

    1989-08-01T23:59:59.000Z

    The US Department of Energy is classifying groundwaters at sites in its Formerly Utilized Sites Remedial Action Program (FUSRAP). Of particular concern is the potential presence of groundwaters that are highly vulnerable to contamination and that are either (1) irreplaceable sources of drinking water or (2) ecologically vital. Conditions at nine FUSRAP sites were evaluated to determine if ecologically vital groundwaters are present. The sites evaluated were Wayne Interim Storage Site, Maywood Interim Storage Site, and Middlesex Sampling Plant in New Jersey; Ashland 2 Site, Seaway Industrial Park, Colonie Interim storage Site, and Niagara Falls Storage Site in New York; and the St. Louis Airport Site and Hazelwood Interim Storage Site in Missouri. The analyses indicated that groundwaters are vulnerable to contamination at all but two of the sites -- the Ashland 2 and Seaway Industrial Park sites in New York. Groundwater discharge points were identified within a 2-mile radius (i.e., the classification review area) of all of the sites. No ecologically vital groundwater areas exist in the vicinities of any of the nine FUSRAP sites evaluated. 35 refs., 17 figs.

  4. Subsurface characterization of the San Jacinto River Research site

    E-Print Network [OSTI]

    Leik, Jason Allan

    1998-01-01T23:59:59.000Z

    In order to develop an effective petroleum repudiation ics. strategy, the interaction between surface and shallow subsurface water was determined for the San Jacinto River Oi1 Spill Remediation Research site. The ten-acre wetland is located...

  5. Hanford Site National Environmental Policy Act (NEPA) Characterization

    SciTech Connect (OSTI)

    Cushing, C.E. (ed.)

    1992-12-01T23:59:59.000Z

    This fifth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Information is presented on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels, prepared by Pacific Northwest Laboratory (PNL) staff. Models are described that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Federal and state regulations, DOE orders and permits, and environmental standards directly applicable for the NEPA documents at the Hanford Site, are provided.

  6. Hanford Site National Environmental Policy Act (NEPA) Characterization. Revision 5

    SciTech Connect (OSTI)

    Cushing, C.E. [ed.] [ed.

    1992-12-01T23:59:59.000Z

    This fifth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Information is presented on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels, prepared by Pacific Northwest Laboratory (PNL) staff. Models are described that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Federal and state regulations, DOE orders and permits, and environmental standards directly applicable for the NEPA documents at the Hanford Site, are provided.

  7. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 9, Index

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules.

  8. Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 7

    SciTech Connect (OSTI)

    Cushing, C.E. [ed.] ed.; Baker, D.A.; Chamness, M.A. [and others] and others

    1995-09-01T23:59:59.000Z

    This seventh revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Chapter 4.0 summarizes up-to-date information on climate and meteorology, geology, hydrology, environmental monitoring, ecology, history and archaeology, socioeconomics, land use, and noise levels prepared by Pacific Northwest Laboratory (PNL) staff. More detailed data are available from reference sources cited or from the authors. Chapter 5.0 was not updated from the sixth revision (1994). It describes models, including their principal underlying assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. The updated Chapter 6.0 provides the preparer with the federal and state regulations, DOE Orders and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site, following the structure of Chapter 4.0. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be used directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the Hanford Site and its past activities by which to evaluate projected activities and their impacts.

  9. Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 6

    SciTech Connect (OSTI)

    Cushing, C.E. [ed.; Baker, D.A.; Chamness, M.A. [and others

    1994-08-01T23:59:59.000Z

    This sixth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. Chapter 4.0 summarizes up-to-date information on climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels prepared by Pacific Northwest Laboratory (PNL) staff. More detailed data are available from reference sources cited or from the authors; Chapter 5.0 has been significantly updated from the fifth revision. It describes models, including their principal underlying assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclide transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions; The updated Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site, following the structure of Chapter 4.0. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be utilized directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the Hanford Site and its past activities by which to evaluate projected activities and their impacts.

  10. Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 9

    SciTech Connect (OSTI)

    Neitzel, D.A. [ed.] [ed.; Bjornstad, B.N.; Fosmire, C.J. [and others] [and others

    1997-08-01T23:59:59.000Z

    This ninth revision of the Hanford Site National Environmental Policy Act (NEPA) Characterization presents current environmental data regarding the hanford Site and its immediate environs. This information is intended for use in preparing Chapters 4 and 6 in Hanford Site-related NEPA documents. Chapter 4.0 (Affected Environment) includes information on climate and meteorology, geology, hydrology, ecology, cultural, archaeological and historical resources, socioeconomics, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) provides the preparer with the federal and state regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site. Not all of the sections have been updated for this revision. The following lists the updated sections: climate and meteorology; ecology (threatened and endangered species section only); culture, archaeological, and historical resources; socioeconomics; all of Chapter 6.

  11. Strategic Petroleum Reserve (SPR) geological site characterization report, Big Hill Salt Dome

    SciTech Connect (OSTI)

    Hart, R.J.; Ortiz, T.S.; Magorian, T.R.

    1981-09-01T23:59:59.000Z

    Geological and geophysical analyses of the Big Hill Salt Dome were performed to determine the suitability of this site for use in the Strategic Petroleum Reserve (SPR). Development of 140 million barrels (MMB) of storage capacity in the Big Hill Salt Dome is planned as part of the SPR expansion to achieve 750 MMB of storage capacity. Objectives of the study were to: (1) Acquire, evaluate, and interpret existing data pertinent to geological characterization of the Big Hill Dome; (2) Characterize the surface and near-surface geology and hydrology; (3) Characterize the geology and hydrology of the overlying cap rock; (4) Define the geometry and geology of the dome; (5) Determine the feasibility of locating and constructing 14 10-MMB storage caverns in the south portion of the dome; and (6) Assess the effects of natural hazards on the SPR site. Recommendations are included. (DMC)

  12. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06T23:59:59.000Z

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility.

  13. Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 8

    SciTech Connect (OSTI)

    Neitzel, D.A. [ed.] [ed.; Bjornstad, B.N.; Fosmire, C.J.; Fowler, R.A. [and others] [and others

    1996-08-01T23:59:59.000Z

    This eighth revision of the Hanford Site National Environmental Policy Act (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Chapters 4 and 6 in Hanford Site-related NEPA documents. Chapter 4 (Affected Environment) includes information on climate and meteorology, geology, hydrology, ecology, historical, archaeological and cultural resources, socioeconomics, and noise. Chapter 6 (Statutory and Regulatory Requirements) provides the preparer with the federal and state regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site. The following sections were updated in this revision: climate and meteorology; ecology (threatened and endangered species section only); historical; archaeological and cultural resources; and all of chapter 6. No conclusions or recommendations are given in this report. Rather, it is a compilation of information on the Hanford Site environment that can be used directly by Site contractors. This information can also be used by any interested individual seeking baseline data on the hanford Site and its past activities by which to evaluate projected activities and their impacts.

  14. Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement

    SciTech Connect (OSTI)

    NONE

    1994-03-31T23:59:59.000Z

    The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.

  15. Yucca Mountain Site Characterization Project technical data catalog quarterly supplement

    SciTech Connect (OSTI)

    NONE

    1995-03-31T23:59:59.000Z

    The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with t requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to@ previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.

  16. Site Characterization Work Plan for the Gnome-Coach Site, New Mexico (Rev. 1, January 2002)

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV)

    2002-01-14T23:59:59.000Z

    Project Gnome was the first nuclear experiment conducted under the U.S. Atomic Energy Commission (AEC), predecessor to the U.S. Department of Energy (DOE), Plowshare Program. The Plowshare Program focused on developing nuclear devices exclusively for peaceful purposes. The intent of the Gnome experiment was to evaluate the effects of a nuclear detonation in a salt medium. Historically, Project Gnome consisted of a single detonation of a nuclear device on December 10, 1961 with the Salado Formation. Since the Gnome detonation, the AEC/DOE has conducted surface restoration, site reconnaissance, and decontamination and decommissioning activities at the site. In addition, annual groundwater sampling is performed under a long-term hydrological monitoring program begun in 1972. Coach, an experiment to be located near the Gnome project, was initially scheduled for 1963. Although construction and rehabilitation were completed for Coach, the experiment was canceled and never executed. Known collectively as Project Gnome-Coach, the site is located approximately 25 miles east of Carlsbad, New Mexico, in Eddy County, and is comprised of nearly 680 acres, of which approximately 60 acres are disturbed from the combined AEC/DOE operations. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the project. The subsurface at the Gnome-Coach site has two contaminant sources that are fundamentally different in terms of both their stratigraphic location and release mechanism. The goal of this characterization is to collect data of sufficient quantity and quality to establish current site conditions and to use the data to identify and evaluate if further action is required to protect human health and the environment and achieve permanent closure of the site. The results of these activities will be presented in a subsequent corrective action decision document.

  17. Site Characterization Work Plan for Gnome-Coach Site, New Mexico

    SciTech Connect (OSTI)

    DOE/NV

    2001-02-13T23:59:59.000Z

    Project Gnome was the first nuclear experiment conducted under the U.S. Atomic Energy Commission (AEC), predecessor to the U.S. Department of Energy (DOE), Plowshare Program. Gnome was part of a joint government-industry experiment focused on developing nuclear devices exclusively for peaceful purposes. The intent of the Gnome experiment was to evaluate the effects of a nuclear detonation in a salt medium. Historically, Project Gnome consisted of a single detonation of a nuclear device on December 10, 1961. Since the Gnome detonation, the AEC/DOE has conducted surface restoration, site reconnaissance, and decontamination and decommissioning activities at the site. In addition, annual groundwater sampling is performed under a long-term hydrological monitoring program begun in 1980. Coach, an experiment to be located near the Gnome project, was initially scheduled for 1963. Although construction and rehabilitation were completed for Coach, the experiment was canceled and never executed. Known collectively as Project Gnome-Coach, the site is situated within the Salado Formation approximately 25 miles east of Carlsbad, New Mexico, in Eddy County, and is comprised of nearly 680 acres, of which 60 acres are disturbed from the combined AEC/DOE operations. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the project. The subsurface at the Gnome-Coach site has two contaminant sources that are fundamentally different in terms of both their stratigraphic location and release mechanism. The goal of this characterization is to collect data of sufficient quantity and quality to establish current site conditions and to use the data to identify and evaluate if further action is required to protect human health and the environment and achieve permanent closure of the site. The results of these activities will be presented in a subsequent corrective action decision document.

  18. Hanford Site National Evnironmental Policy Act (NEPA) characterization

    SciTech Connect (OSTI)

    Cushing, C.E. (ed.)

    1991-12-01T23:59:59.000Z

    This fourth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. In Chapter 4.0 are presented summations of up-to-date information about climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels. Chapter 5.0 describes models, including their principal assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclides transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable for environmental impact statements for the Hanford Site, following the structure Chapter 4.0. NO conclusions or recommendations are given in this report.

  19. Hanford Site National Evnironmental Policy Act (NEPA) characterization. Revision 4

    SciTech Connect (OSTI)

    Cushing, C.E. [ed.

    1991-12-01T23:59:59.000Z

    This fourth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. In Chapter 4.0 are presented summations of up-to-date information about climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels. Chapter 5.0 describes models, including their principal assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclides transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable for environmental impact statements for the Hanford Site, following the structure Chapter 4.0. NO conclusions or recommendations are given in this report.

  20. CHARACTERIZATION OF GLOVEBOX GLOVES FOR THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Korinko, P.

    2013-01-24T23:59:59.000Z

    A task was undertaken to characterize glovebox gloves that are currently used in the facilities at Savannah River Site (SRS) as well as some experimental and advanced compound gloves that have been proposed for use. Gloves from four manufacturers were tested for permeation in hydrogen and air, thermal stability, tensile properties, puncture resistance and dynamic mechanical response. The gloves were compared to each other within the type and also to the butyl rubber glove that is widely used at the SRS. The permeation testing demonstrated that the butyl compounds from three of the vendors behaved similarly and exhibited hydrogen permeabilities of .52‐.84 x10{sup ‐7} cc H{sub 2}*cm / (cm{sup 2}*atm). The Viton? glove performed at the lower edge of this bound, while the more advanced composite gloves exhibited permeabilities greater than a factor of two compared to butyl. Thermogravimetric analysis was used to determine the amount of material lost under slightly aggressive conditions. Glove losses are important since they can affect the life of glovebox stripper systems. During testing at 90, 120, and 150?C, the samples lost most of the mass in the initial 60 minutes of thermal exposure and as expected increasing the temperature increased the mass loss and shortened the time to achieve a steady state loss. The ranking from worst to best was Jung butyl‐Hypalon? with 12.9 %, Piercan Hypalon? with 11.4 %, and Jung butyl‐Viton? with 5.2% mass loss all at approximately 140?C. The smallest mass losses were experienced by the Jung Viton? and the Piercan polyurethane. Tensile properties were measured using a standard dog bone style test. The butyl rubber exhibited tensile strengths of 11‐15 MPa and elongations or 660‐843%. Gloves made from other compounds exhibited lower tensile strengths (5 MPa Viton) to much higher tensile strengths (49 MPa Urethane) with a comparable range of elongation. The puncture resistance of the gloves was measured in agreement with an ASTM standard. The Butyl gloves exhibited puncture resistance from 183 ? 296 lbs/in for samples of 0.020 ? 0.038? thick. Finally, the glass transition temperature and the elastic and viscoelastic properties as a function of temperature up to maximum use temperature were determined for each glove material using Dynamic Mechanical Analysis. The glass transition temperatures of the gloves were ‐60?C for butyl, ‐30?C for polyurethane, ‐ 16?C Hypalon?, ‐16?C for Viton?, and ‐24?C for polyurethane‐Hypalon?. The glass transition was too complex for the butyl‐Hypalon? and butyl‐Viton? composite gloves to be characterized by a single glass transition temperature. All of the glass transition temperatures exceed the vendor projected use temperatures.

  1. Site Characterization Work Plan for Gasbuggy, New Mexico (Rev.1, Jan. 2002)

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV)

    2002-01-25T23:59:59.000Z

    Project Gasbuggy was the first of three joint government-industry experiments conducted to test the effectiveness of nuclear explosives to fracture deeply buried, low-permeability natural gas reservoirs to stimulate production. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the Project Gasbuggy Site. Its goal is the collection of data in sufficient quantity and quality to determine current site conditions, support a risk assessment for the site surfaces, and evaluate if further remedial action is required to achieve permanent closure of the site that is both protective of human health and the environment. The Gasbuggy Site is located approximately 55 air miles east of Farmington, New Mexico, in Rio Arriba County within the Carson National Forest in the northeast portion of the San Juan Basin. Historically, Project Gasbuggy consisted of the joint government-industry detonation of a nuclear device on December 10, 1967, followed by reentry drilling and gas production testing and project evaluation activities in post-detonation operations from 1967 to 1976. Based on historical documentation, no chemical release sites other than the mud pits were identified; additionally, there was no material buried at the Gasbuggy Site other than drilling fluids and construction debris. Although previous characterization and restoration activities including sensitive species surveys, cultural resources surveys, surface geophysical surveys, and limited soil sampling and analysis were performed in 1978 and again in 2000, no formal closure of the site was achieved. Also, these efforts did not adequately address the site's potential for chemical contamination at the surface/shallow subsurface ground levels or the subsurface hazards for potential migration outside of the current site subsurface intrusion restrictions. Additional investigation activities will focus on the surface/shallow subsurface sampling and deep subsurface modeling. Suspected potential contaminants of concern for investigative analysis at the Gasbuggy Site include total petroleum hydrocarbons (diesel- and gasoline-range), volatile organic compounds, semivolatile organic compounds, total Resource Conservation and Recovery Act metals, and radionuclides. The results of this characterization and risk assessment will be used to evaluate corrective action alternatives to include no further action, the implementation of institutional controls, capping on site, or off-site disposal of contaminated waste which will be presented in a subsequent corrective action decision document.

  2. Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    NONE

    1992-01-01T23:59:59.000Z

    The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.

  3. Strategic petroleum reserve (SPR) geological site characterization report, Bayou Choctaw Salt Dome. Sections I and II

    SciTech Connect (OSTI)

    Hogan, R.G. (ed.)

    1981-03-01T23:59:59.000Z

    This report comprises two sections: Bayou Choctaw cavern stability issues, and geological site characterization of Bayou Choctaw. (DLC)

  4. Noninvasive Contaminant Site Characterization Using Geophysical Induced Polarization

    SciTech Connect (OSTI)

    Morgan, F.D.; Sogade, J.; Lesmes, D.; Coles, D.; Vichabian, Y.; Scira-Scappuzzo, F.; Shi, W.; Vandiver, A.; Rodi, W.

    2003-03-27T23:59:59.000Z

    Results of aspects of a broad foundational study of time domain IP (TDIP) and spectral IP (SIP) for contaminant site characterization are presented. This ongoing study encompassed laboratory studies of coupled effects of rock/soil microgeometry and contaminant chemistry on induced polarization (IP), an investigation of electromagnetic coupling (EMC) noise and development of 3D modeling and inversion codes. SIP requires extensions to higher frequencies (above the typical 100Hz threshold) and EMC becomes the major limitation for field implementation, because conventional correction methods are inadequate at required higher frequencies. A proposed methodology is outlined, based on a model of all EMC components, that addresses the EMC problem by coupling IP and electromagnetic induction in modeling and inversion. Examples of application of IP and SIP to contaminant mapping and detection for TDIP and SIP will be presented for FS-12 plume at Massachusetts Military Reservation and a suspected DNAPL plume at Savannah River Site.

  5. Uranium characterization at the St. Louis Airport Site

    SciTech Connect (OSTI)

    Schilk, A.J.; Hubbard, C.W.; Bowyer, T.W. [Pacific Northwest Lab., Richland, WA (United States); Reiman, R.T. [Technical Measurement Co., Boulder, CO (United States)

    1995-05-01T23:59:59.000Z

    In support of the Department of Energy/Office of Technology Development`s Expedited Site Characterization (ESC) project (coordinated by Ames Laboratory), the Pacific Northwest Laboratory demonstrated two complementary technologies at the St. Louis Airport (SLAP) site that have been designed and optimized for the rapid, in situ quantification of radionuclide contamination in surface soils. The sensors are optimized for the detection of high-energy beta particles or gamma rays emitted from the decay of specific radionuclides of interest. These technologies were demonstrated by measuring the beta and gamma fluxes at several locations within the SLAP site. Measurements were converted to average contamination levels, using detector calibrations performed with spiked samples (beta) or sealed sources (gamma). Additionally, subsurface activity levels were derived from discrete soil samples (provided by the ESC field crew) via gamma-ray spectrometry in a controlled laboratory setting. Since the beta and gamma sensor technologies are intrinsically sensitive to different types of radiation and activity distributions (i.e., surface and shallow subsurface, respectively), the data obtained from the two detectors provide complementary information about the distribution of the contamination. The results reported here suggest that a number of locations within the SLAP site have elevated levels of {sup 211}U, and the differences between the beta and gamma activities indicate that the contamination is largely located near the surface of the soil.

  6. A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository- A Decision Aiding Methodology

    Broader source: Energy.gov [DOE]

    In December 1984, the Department of Energy (DOE) published draft environmental assessments (EAs) to support the proposed nomination of five sites and the recommendation of three sites for characterization for the first radioactive-waste repository. A chapter common to all the draft EAs (Chapter 7) presented rankings of the five sites against the postclosure and the preclosure technical siting guidelines. To determine which three sites appeared most favorable for recommendation for characterization, three simple quantitative methods were used to aggregate the rankings assigned to each site for the various technical guidelines. In response to numerous comments on the methods, the DOE has undertaken a formal application of one of them (hereafter referred to as the decision-aiding methodology) for the purpose of obtaining a more rigorous evaluation of the nominated sites.

  7. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    SciTech Connect (OSTI)

    NONE

    1988-01-01T23:59:59.000Z

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.

  8. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 1

    SciTech Connect (OSTI)

    NONE

    1988-01-01T23:59:59.000Z

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs.

  9. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    SciTech Connect (OSTI)

    NONE

    1988-01-01T23:59:59.000Z

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  10. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    SciTech Connect (OSTI)

    NONE

    1988-01-01T23:59:59.000Z

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  11. Gulf of Mexico Miocene CO2 Site Characterization Mega Transect

    SciTech Connect (OSTI)

    Meckel, Timothy; Trevino, Ramon

    2014-09-30T23:59:59.000Z

    This project characterized the Miocene-age sub-seafloor stratigraphy in the near-offshore portion of the Gulf of Mexico adjacent to the Texas coast. The large number of industrial sources of carbon dioxide (CO2) in coastal counties and the high density of onshore urbanization and environmentally sensitive areas make this offshore region extremely attractive for long-term storage of carbon dioxide emissions from industrial sources (CCS). The study leverages dense existing geologic data from decades of hydrocarbon exploration in and around the study area to characterize the regional geology for suitability and storage capacity. Primary products of the study include: regional static storage capacity estimates, sequestration “leads” and prospects with associated dynamic capacity estimates, experimental studies of CO2-brine-rock interaction, best practices for site characterization, a large-format ‘Atlas’ of sequestration for the study area, and characterization of potential fluid migration pathways for reducing storage risks utilizing novel high-resolution 3D (HR3D) seismic surveys. In addition, three subcontracted studies address source-to-sink matching optimization, offshore well bore management and environmental aspects. The various geologic data and interpretations are integrated and summarized in a series of cross-sections and maps, which represent a primary resource for any near-term commercial deployment of CCS in the area. The regional study characterized and mapped important geologic features (e.g., Clemente-Tomas fault zone, the regionally extensive Marginulina A and Amphistegina B confining systems, etc.) that provided an important context for regional static capacity estimates and specific sequestration prospects of the study. A static capacity estimate of the majority of the Study area (14,467 mi2) was estimated at 86 metric Gigatonnes. While local capacity estimates are likely to be lower due to reservoir-scale characteristics, the offshore Miocene interval is a storage resource of National interest for providing CO2 storage as an atmospheric emissions abatement strategy. The natural petroleum system was used as an analog to infer seal quality and predict possible migration pathways of fluids in an engineered system of anthropogenic CO2 injection and storage. The regional structural features (e.g., Clemente-Tomas fault zone) that exert primary control on the trapping and distribution of Miocene hydrocarbons are expected to perform similarly for CCS. Industrial?scale CCS will require storage capacity utilizing well?documented Miocene hydrocarbon (dominantly depleted gas) fields and their larger structural closures, as well as barren (unproductive, brine?filled) closures. No assessment was made of potential for CO2 utilization for enhanced oil and gas recovery. The use of 3D numerical fluid flow simulations have been used in the study to greatly assist in characterizing the potential storage capacity of a specific reservoir. Due to the complexity of geologic systems (stratigraphic heterogeneity) and inherent limitations on producing a 3D geologic model, these simulations are typically simplified scenarios that explore the influence of model property variability (sensitivity study). A specific site offshore San Luis Pass (southern Galveston Island) was undertaken successfully, indicating stacked storage potential. Downscaling regional capacity estimates to the local scale (and the inverse) has proven challenging, and remains an outstanding gap in capacity assessments. In order to characterize regional seal performance and identify potential brine and CO2 leakage pathways, results from three high-resolution 3D (HR3D) seismic datasets acquired by the study using novel HR3D (P-Cable) acquisition system showed steady and significant improvements in data quality because of improved acquisition and processing technique. Finely detailed faults and stratigraphy in the shallowest 1000 milliseconds (~800 m) of data allowed for the identification and mapping of unconformable surfaces including what is probably

  12. An overview of treatment and characterization technologies for environmental remediation at the Savannah River Site

    SciTech Connect (OSTI)

    Holt, D.L.; Butcher, B.T.

    1992-05-01T23:59:59.000Z

    The Environmental Restoration Department (ERD) at the Savannah River Site (SRS) has the responsibility to remediate waste sites and groundwater to standards as determined by Federal and State Authorities. This mission requires that certain programmatic interfaces within the ERD, Savannah River Technology Center (SRTC, formerly Savannah River Laboratory (SRL)), the Department of Energy Headquarters (DOE-HQ) Office of Technology Development (OTD), and outside commercial contractors be utilized to ensure cost-effective remediation technologies are utilized. This paper provides a synopsis of a select cross-section of the treatment and characterization technologies currently being pursued by ERD. Environmental Restoration Technology (ERT) Department's future role in providing the necessary technologies for waste sites and groundwater remediation is also discussed.

  13. An overview of treatment and characterization technologies for environmental remediation at the Savannah River Site

    SciTech Connect (OSTI)

    Holt, D.L.; Butcher, B.T.

    1992-05-01T23:59:59.000Z

    The Environmental Restoration Department (ERD) at the Savannah River Site (SRS) has the responsibility to remediate waste sites and groundwater to standards as determined by Federal and State Authorities. This mission requires that certain programmatic interfaces within the ERD, Savannah River Technology Center (SRTC, formerly Savannah River Laboratory (SRL)), the Department of Energy Headquarters (DOE-HQ) Office of Technology Development (OTD), and outside commercial contractors be utilized to ensure cost-effective remediation technologies are utilized. This paper provides a synopsis of a select cross-section of the treatment and characterization technologies currently being pursued by ERD. Environmental Restoration Technology (ERT) Department`s future role in providing the necessary technologies for waste sites and groundwater remediation is also discussed.

  14. Characterization Report for the David Witherspoon Screen Art Site

    SciTech Connect (OSTI)

    Phyllis C. Weaver

    2011-01-31T23:59:59.000Z

    The U.S. Department of Energy (DOE) Oak Ridge Office (ORO) of Environmental Management (EM) requested the technical assistance of Oak Ridge Institute for Science and Education (ORISE) to characterize a tract of land associated with the David Witherspoon, Incorporated (DWI) Volunteer Equipment and Supply Company (VESC). This tract of land (hereinafter referred to as Screen Arts) is located in the Vestal Community in the 2000-block of Maryville Pike in south Knoxville, Tennessee, as shown in Figure A-1. This tract of land has been used primarily to store salvaged equipment and materials for resale, recycle, or for disposal in the former landfill once operated by DWI. The DWI Site industrial landfill and metal recycling business had been permitted by the Tennessee Division of Radiological Health to accept low-level radiologically contaminated metals. DWI received materials and equipment associated with operations from DOE sites, including those in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. It is likely that items stored at Screen Arts may have contained some residual radiological materials.

  15. Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

    SciTech Connect (OSTI)

    Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

    1989-07-01T23:59:59.000Z

    Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs.

  16. Site characterization progress report: Yucca Mountain, Nevada. Number 15, April 1--September 30, 1996

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    During the second half of fiscal year 1996, activities at the Yucca Mountain Site Characterization Project (Project) supported the objectives of the revised Program Plan released this period by the Office of Civilian Radioactive Waste Management of the US Department of Energy (Department). Outlined in the revised plan is a focused, integrated program of site characterization, design, engineering, environmental, and performance assessment activities that will achieve key Program and statutory objectives. The plan will result in the development of a license application for repository construction at Yucca Mountain, if the site is found suitable. Activities this period focused on two of the three near-term objectives of the revised plan: updating in 1997 the regulatory framework for determining the suitability of the site for the proposed repository concept and providing information for a 1998 viability assessment of continuing toward the licensing of a repository. The Project has also developed a new design approach that uses the advanced conceptual design published during the last reporting period as a base for developing a design that will support the viability assessment. The initial construction phase of the Thermal Testing Facility was completed and the first phase of the in situ heater tests began on schedule. In addition, phase-one construction was completed for the first of two alcoves that will provide access to the Ghost Dance fault.

  17. Sorting and Characterizing Oversized Boxes of Transuranic Waste at the Nevada Test Site

    ScienceCinema (OSTI)

    None

    2014-10-28T23:59:59.000Z

    Characterization activities conducted inside the Visual Examination and Repackaging Building at the Area 5 Radioactive Waste Management Complex on the Nevada Test Site.

  18. Aquifer characterization and groundwater modeling in support of remedial actions at the Weldon Spring Site

    SciTech Connect (OSTI)

    Durham, L.A. [Argonne National Lab., IL (United States); Carman, J.D. [Jacobs Engineering Group, Inc., St. Charles, MO (United States)

    1993-10-01T23:59:59.000Z

    Aquifer characterization studies were performed to develop a hydrogeologic understanding of an unconfined shallow aquifer at the Weldon Spring site west of St. Louis, Missouri. The 88-ha site became contaminated because of uranium and thorium processing and disposal activities that took place from the 1940s through the 1960s. Slug and pumping tests provided valuable information on the lateral distribution of hydraulic conductivities, and packer tests and lithologic information were used to determine zones of contrasting hydrologic properties within the aquifer. A three-dimensional, finite- element groundwater flow model was developed and used to simulate the shallow groundwater flow system at the site. The results of this study show that groundwater flow through the system is predominantly controlled by a zone of fracturing and weathering in the upper portion of the limestone aquifer. The groundwater flow model, developed and calibrated from field investigations, improved the understanding of the hydrogeology and supported decisions regarding remedial actions at the site. The results of this study illustrate the value, in support of remedial actions, of combining field investigations with numerical modeling to develop an improved understanding of the hydrogeology at the site.

  19. Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2006-06-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

  20. Hanford Site National Environmental Policy Act (NEPA) characterization. Revision 10

    SciTech Connect (OSTI)

    Neitzel, D.A. [ed.; Fosmire, C.J.; Fowler, R.A. [and others

    1998-09-01T23:59:59.000Z

    This document describes the US Department of Energy`s (DOE) Hanford Site environment and is numbered to correspond to the chapters where such information is presented in Hanford Site NEPA related documents. The document is intended to provide a consistent description of the Hanford Site environment for the many NEPA documents that are being prepared by contractors. The two chapters in this document (Chapters 4 and 6) are numbered this way to correspond to the chapters where such information is presented in environmental impact statements (EISs) and other Site-related NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes the Hanford Site environment, and includes information on climate and meteorology, geology, hydrology, ecology, cultural, archaeological and historical resources, socioeconomics, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes applicable federal and state laws and regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site.

  1. Data Summary Report for Hanford Site Coal Ash Characterization

    SciTech Connect (OSTI)

    Sulloway, H. M.

    2012-03-06T23:59:59.000Z

    The purpose of this report is to present data and findings from sampling and analysis of five distinct areas of coal ash within the Hanford Site River Corridor

  2. Environmental assessment for the Groundwater Characterization Project, Nevada Test Site, Nye County, Nevada; Revision 1

    SciTech Connect (OSTI)

    NONE

    1992-08-01T23:59:59.000Z

    The US Department of Energy (DOE) proposes to conduct a program to characterize groundwater at the Nevada Test Site (NTS), Nye County, Nevada, in accordance with a 1987 DOE memorandum stating that all past, present, and future nuclear test sites would be treated as Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites (Memorandum from Bruce Green, Weapons Design and Testing Division, June 6, 1987). DOE has prepared an environmental assessment (DOE/EA-0532) to evaluate the environmental consequences associated with the proposed action, referred to as the Groundwater Characterization Project (GCP). This proposed action includes constructing access roads and drill pads, drilling and testing wells, and monitoring these wells for the purpose of characterizing groundwater at the NTS. Long-term monitoring and possible use of these wells in support of CERCLA, as amended by the Superfund Amendments and Reauthorization Act, is also proposed. The GCP includes measures to mitigate potential impacts on sensitive biological, cultural and historical resources, and to protect workers and the environment from exposure to any radioactive or mixed waste materials that may be encountered. DOE considers those mitigation measures related to sensitive biological, cultural and historic resources as essential to render the impacts of the proposed action not significant, and DOE has prepared a Mitigation Action Plan (MAP) that explains how such mitigations will be planned and implemented. Based on the analyses presented in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement is not required and the Department is issuing this FONSI.

  3. Site Characterization Plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 218 figs., 50 tabs.

  4. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 1, Part A: Chapters 1 and 2

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 750 refs., 123 figs., 42 tabs.

  5. Physicochemical and mineralogical characterization of soil/saprolite cores from a field research site, Tennessee

    SciTech Connect (OSTI)

    Moon, Ji Won [ORNL; Phelps, Tommy Joe [ORNL; Phillips, Debra H [Queen's University, Belfast; Watson, David B [ORNL; Kim, Young Jin [ORNL; Brooks, Scott C [ORNL

    2006-08-01T23:59:59.000Z

    Site characterization is an essential initial step in determining the feasibility of remedial alternatives at hazardous waste sites. Physico-chemical and mineralogical characterization of U-contaminated soils in deeply weathered saprolite at Area 2 of the DOE Field Research Center (FRC) site, Oak Ridge, TN, was accomplished to examine the feasibility of bioremediation. Concentrations of U in soil-saprolite (up to 291 mg kg^-1 in oxalate-extractable Uo) were closely related to low pH (ca. 4-5), high effective cation exchange capacity without Ca (64.7-83.2 cmolc kg_1), amorphous Mn content (up to 9910 mg kg_1), and the decreased presence of relative clay mineral contents in the bulk samples (i.e., illite 2.5-12 wt. %, average 32 wt. %). The pH of the fill material ranged from 7.0 to 10.5, whereas the pH of the saprolite ranged from 4.5 to 8. Uranium concentration was highest (about 300 mg kg^-1) at around 6 m below land surface near the saprolite-fill interface. The pH of ground water at Area 2 tended to be between 6 and 7 with U concentrations of about 0.9 to 1.7 mg L^-1. These site specific characteristics of Area 2, which has lower U and nitrate con-tamination levels and more neutral ground water pH compared with FRC Areas 1 and 3 (ca. 5.5 and _4, respectively), indicate that with appropriate addition of electron donors and nutrients bioremediation of U by metal reducing microorganisms may be possible.

  6. A radiological characterization of remediated tank battery sites

    SciTech Connect (OSTI)

    Hebert, M.B. [NORMCO, Amelia, LA (United States); Scott, L.M. [Louisiana State Univ., Baton Rouge, LA (United States); Zrake, S.J. [Ashland Exploration, Inc., Houston, TX (United States)

    1995-03-01T23:59:59.000Z

    Tank battery sites have historically been used for the initial processing of crude oil which separates water and sediment from the produced oil. Typically, one or more producing wells is connected to a tank battery site consisting of storage and separation tanks. Historical operating practices also included a production holding pit for increaesd separation of oil, water, and sediment.

  7. Characterize and explore potential sites and prepare research and development plan (site investigation study). Final draft. Task 2. Milestone report

    SciTech Connect (OSTI)

    None

    1980-12-01T23:59:59.000Z

    Phase II of a 5-phase overall compressed air energy storage (CAES) development program was performed to characterize and explore potential CAES sites and to prepare a research and development plan. This volume for Phase II activities contains an evaluation of the suitability of seven selected sites to undergo field drilling and air injection testing; a bibliography; results of a literature search on the effects of air injection of aquifer-caprock well systems; reservoir data for the sites; cost estimates; and predicted potential risks from a CAES plant. (LCL)

  8. Site characterization report for the basalt waste isolation project. Volume II

    SciTech Connect (OSTI)

    None

    1982-11-01T23:59:59.000Z

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment.

  9. Site characterization for LIL radioactive waste disposal in Romania

    SciTech Connect (OSTI)

    Diaconu, D. R. (Daniela R.); Birdsell, K. H. (Kay H.); Witkowski, M. S. (Marc S.)

    2001-01-01T23:59:59.000Z

    Recent studies in radioactive waste management in Romania have focussed mainly on the disposal of low and intermediate level waste from the operation of the new nuclear power plant at Cernavoda. Following extensive geological, hydrological, seismological, physical and chemical investigations, a disposal site at Saligny has been selected. This paper presents description of the site at Saligny as well as the most important results of the site characterisation. These are reflected in the three-dimensional, stratigraphical representation of the loess and clay layers and in representative parameter values for the main layers. Based on these data, the simulation of the background, unsaturated-zone water flow at the Saligny site, calculated by the FEHM code, is in a good agreement with the measured moisture profile.

  10. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    FEASIBILITY: TEAPOT DOME EOR PILOT L. Chiaramonte, M.TO IDENTIFY OPTIMAL CO 2 EOR STORAGE SITES V. Núñez Lopez,from a carbon dioxide EOR/sequestration project. Energy

  11. The Nevada Test Site Legacy TRU Waste - The WIPP Central Characterization Project

    SciTech Connect (OSTI)

    Norton, J. F.; Lahoud, R. G.; Foster, B. D.; VanMeighem, J.

    2003-02-25T23:59:59.000Z

    This paper discusses the Central Characterization Project (CCP) designed by the Waste Isolation Pilot Plant (WIPP) to aid sites, especially those sites with small quantities of transuranic (TRU) waste streams, in disposing of legacy waste at their facility. Because of the high cost of contracting vendors with the characterization capabilities necessary to meet the WIPP Waste Acceptance Criteria, utilizing the CCP is meant to simplify the process for small quantity sites. The paper will describe the process of mobilization of the vendors through CCP, the current production milestones that have been met, and the on-site lessons learned.

  12. Hanford Site National Environmental Policy Act (NEPA) characterization

    SciTech Connect (OSTI)

    Cushing, C.E. (ed.)

    1988-09-01T23:59:59.000Z

    This document describes the Hanford Site environment (Chapter 4) and contains data in Chapter 5 and 6 which will guide users in the preparation of National Environmental Policy Act (NEPA)-related documents. Many NEPA compliance documents have been prepared and are being prepared by site contractors for the US Department of Energy, and examination of these documents reveals inconsistencies in the amount of detail presented and the method of presentation. Thus, it seemed necessary to prepare a consistent description of the Hanford environment to be used in preparing Chapter 4 of environmental impact statements and other site-related NEPA documentation. The material in Chapter 5 is a guide to the models used, including critical assumptions incorporated in these models, in previous Hanford NEPA documents. The users will have to select those models appropriate for the proposed action. Chapter 6 is essentially a definitive NEPA Chapter 6, which describes the applicable laws, regulations, and DOE and state orders. In this document, a complete description of the environment is presented in Chapter 4 without excessive tabular data. For these data, sources are provided. Most subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information where it is available on the 100, 200, 300, and other Areas. This division will allow a person requiring information to go immediately to those sections of particular interest. However, site-specific information on each of these separate areas is not always complete or available. In this case, the general Hanford Site description should be used. 131 refs., 19 figs., 32 tabs.

  13. Hanford Site National Environmental Policy Act (NEPA) Characterization

    SciTech Connect (OSTI)

    Rohay, A.C.; Fosmire, C.J.; Neitzel, D.A.; Hoitink, D.J.; Harvey, D.W.; Antonio, E.J.; Wright, M.K.; Thorne, P.D.; Hendrickson, P.L.; Fowler, R.A.; Goodwin, S.M.; Poston, T.M.

    1999-09-28T23:59:59.000Z

    This document describes the US Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many NEPA documents being prepared by DOE contractors. No conclusions or recommendations are provided. This year's report is the eleventh revision of the original document published in 1988 and is (until replaced by the 12th revision) the only version that is relevant for use in the preparation of Hanford NEPA; SEPA and CERCLA documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is presented in environmental impact statements (EISs) and other Site-related NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological and historical resources, socioeconomic; occupational safety, and noise. Sources for extensive tabular data related to these topics are provided in the chapter. Most subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information, where available, of the 100,200,300, and other Areas. This division allows the reader to go directly to those sections of particular interest. When specific information on each of these separate areas is not complete or available, the general Hanford Site description should be used. Chapter 6.0 (Statutory and Regulatory Requirements) is essentially a definitive NEPA Chapter 6.0, which describes applicable federal and state laws and regulations, DOE directives and permits, and environmental standards directly applicable to the NEPA documents on the Hanford Site. People preparing environmental assessments and EISs should also be cognizant of the document entitled ''Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements'' published by the DOE Office of NEPA Oversight. Pacific Northwest National Laboratory (PNNL) staff prepared individual sections of this document, with input from other Site contractors. More detailed data are available from reference sources cited or from the authors. The following sections of the document were reviewed by the authors and updated with the best available information through June 1999: Climate and Meteorology; Ecology; Cultural, Archaeological, and Historical Resources; Socioeconomics; and All of Chapter 6.

  14. Hanford Site National Environmental Policy Act (NEPA) Characterization

    SciTech Connect (OSTI)

    Neitzel, Duane A.; Bunn, Amoret L.; Duncan, Joanne P.; Eschbach, Tara O.; Fowler, Richard A.; Fritz, Brad G.; Goodwin, Shannon M.; Harvey, David W.; Hendrickson, Paul L.; Hoitink, Dana J.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Rohay, Alan C.; Scott, Michael J.; Thorne, Paul D.

    2002-09-01T23:59:59.000Z

    This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No statements of significance or environmental consequences are provided. This year's report is the thirteenth revision of the original document published in 1988 and is (until replaced by the fourteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (Weiss) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomics, occupational safety, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities.

  15. Hanford Site National Environmental Policy Act (NEPA) Characterization Report

    SciTech Connect (OSTI)

    Neitzel, Duane A.; Bunn, Amoret L.; Cannon, Sandra D.; Duncan, Joanne P.; Fowler, Richard A.; Fritz, Brad G.; Harvey, David W.; Hendrickson, Paul L.; Hoitink, Dana J.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Reidel, Steve P.; Rohay, Alan C.; Scott, Michael J.; Thorne, Paul D.

    2004-09-22T23:59:59.000Z

    This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No statements of significance or environmental consequences are provided. This year's report is the sixteenth revision of the original document published in 1988 and is (until replaced by the seventeenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (Weiss) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomics, occupational safety and health, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities.

  16. Hanford Site National Environmental Policy Act (NEPA) Characterization, Revision 15

    SciTech Connect (OSTI)

    Neitzel, Duane A.; Bunn, Amoret L.; Burk, Kenneth W.; Cannon, Sandra D.; Duncan, Joanne P.; Fowler, Richard A.; Fritz, Brad G.; Harvey, David W.; Hendrickson, Paul L.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Reidel, Steve P.; Scott, Michael J.; Thorne, Paul D.; Woody, Dave M.

    2003-09-01T23:59:59.000Z

    This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No statements of significance or environmental consequences are provided. This year's report is the thirteenth revision of the original document published in 1988 and is (until replaced by the fourteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (Weiss) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomics, occupational safety, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities.

  17. Hanford Site National Environmental Policy Act (NEPA) Characterization

    SciTech Connect (OSTI)

    Neitzel, Duane A.; Antonio, Ernest J.; Eschbach, Tara O.; Fowler, Richard A.; Goodwin, Shannon M.; Harvey, David W.; Hendrickson, Paul L.; Hoitink, Dana J.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast, Ellen L.; Rohay, Alan C.; Thorne, Paul D.

    2001-09-01T23:59:59.000Z

    This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No statements of significance or environmental consequences are provided. This year's report is the thirteenth revision of the original document published in 1988 and is (until replaced by the fourteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (Weiss) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomics, occupational safety, and noise. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities.

  18. Hanford Site Assessment & Characterization/Verification of Buildings Procedure

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2M HILL Secretary MonizSite Public Tours Hanford Site2

  19. Categorical Exclusion Determinations: Y-12 Site Office | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovemberWashingtonAdministration-SierraEnergy Y-12 Site

  20. CX-004198: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-004198: Categorical Exclusion Determination Lurance Canyon Burn Site Soil and Groundwater Site Characterization CX(s) Applied: B3.1 Date: 06142010 Location(s):...

  1. Computers and nautical archaeology: characterization of the C.S.S. Georgia wreck site

    E-Print Network [OSTI]

    Baker, James Graham

    1982-01-01T23:59:59.000Z

    COMPUTERS AND NAUTICAL ARCHAEOLOGY: CHARACTERIZATION OF THE C. S. S. GEORGIA NRECK SITE A Thesis by JAMES GRAHAM BAKER Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirements for the degree... of MASTER OF ARTS December 19HZ Major Subject: Anthropology COMPUTERS IN NAUTICAL ARCHAEOLOGY: CHARACTERIZATION OF THE C. S. S, GEORGIA WRECK SITE A Thesis by JAMES GRAHAM BAKER Approved as to style and content by: Frederick H. van Doorninck, Jr...

  2. Resource Conservation and Recovery Act industrial site environmental restoration site characterization report - area 6 steam cleaning effluent ponds

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    The Area 6 North and South Steam Cleaning Effluent Ponds (SCEPs) are historic disposal units located at the Nevada Test Site (NTS) in Nye County, Nevada. The NTS is operated by the U.S. Department of Energy, Nevada Operations Office (DOE/NV) which has been required by the Nevada Division of Environmental Protection (NDEP) to characterize the site under the requirements of the Resource Conservation and Recovery Act (RCRA) Part B Permit for the NTS and Title 40 Code of Federal Regulations, Part 265.

  3. Characterizing Surface Acidic Sites in Mesoporous-Silica-Supported Tungsten

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation SitesStandingtheir AtmosphericAnalysisVents Using Osmotically

  4. ARRA Site Characterization Projects | netl.doe.gov

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)Productssondeadjustsondeadjust DocumentationARMStreamsUS DepartmentARM'sARPES Provides 2 *AcARRA Site

  5. Soil Characterization at the Linde FUSRAP Site and the Impact on Soil Volume Estimates

    SciTech Connect (OSTI)

    Boyle, J.; Kenna, T.; Pilon, R.

    2002-02-27T23:59:59.000Z

    The former Linde site in Tonawanda, New York is currently undergoing active remediation of Manhattan Engineering District's radiological contamination. This remediation is authorized under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The focus of this paper will be to describe the impact of soil characterization efforts as they relate to soil volume estimates and project cost estimates. An additional objective is to stimulate discussion about other characterization and modeling technologies, and to provide a ''Lessons Learned'' scenario to assist in future volume estimating at other FUSRAP sites. Initial soil characterization efforts at the Linde FUSRAP site in areas known to be contaminated or suspected to be contaminated were presented in the Remedial Investigation Report for the Tonawanda Site, dated February 1993. Results of those initial characterization efforts were the basis for soil volume estimates that were used to estimate and negotiate the current remediation contract. During the course of remediation, previously unidentified areas of contamination were discovered, and additional characterization was initiated. Additional test pit and geoprobe samples were obtained at over 500 locations, bringing the total to over 800 sample locations at the 135-acre site. New data continues to be collected on a routine basis during ongoing remedial actions.

  6. Site characterization progress report: Yucca Mountain, Nevada, April 1, 1993--September 30, 1993, No. 9

    SciTech Connect (OSTI)

    NONE

    1994-02-01T23:59:59.000Z

    In accordance with requirements of Section 113(b)(3) of the Nuclear Waste Policy Act of 1982, as amended, and 10 CFR 60.18(g), the U.S. Department of Energy has prepared this report on the progress of site characterization activities at Yucca Mountain, Nevada, for the period April 1, 1993, through September 30, 1993. This report is the ninth in a series issued at intervals of approximately six months during site characterization of Yucca Mountain as a possible site for a geologic repository for the permanent disposal of high-level radioactive waste. Also included in this report are activities such as public outreach and international programs that are not formally part of the site characterization process. Information on these activities is provided to report on all aspects of the Yucca Mountain studies.

  7. Probable maximum flood control; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    DeGabriele, C.E.; Wu, C.L. [Bechtel National, Inc., San Francisco, CA (United States)

    1991-11-01T23:59:59.000Z

    This study proposes preliminary design concepts to protect the waste-handling facilities and all shaft and ramp entries to the underground from the probable maximum flood (PMF) in the current design configuration for the proposed Nevada Nuclear Waste Storage Investigation (NNWSI) repository protection provisions were furnished by the United States Bureau of Reclamation (USSR) or developed from USSR data. Proposed flood protection provisions include site grading, drainage channels, and diversion dikes. Figures are provided to show these proposed flood protection provisions at each area investigated. These areas are the central surface facilities (including the waste-handling building and waste treatment building), tuff ramp portal, waste ramp portal, men-and-materials shaft, emplacement exhaust shaft, and exploratory shafts facility.

  8. Direct measurements of transport properties are essential for site characterization

    SciTech Connect (OSTI)

    Wright, J. [Pacific Northwest Lab., Richland, WA (United States); Conca, J.L. [Washington State Univ. Tri-Cities, Richland, WA (United States). Environmental Sciences

    1994-08-01T23:59:59.000Z

    Direct measurements of transport parameters on subsurface sediments using, the UFA method provided detailed hydrostratigraphic mapping, and subsurface flux distributions at a mixed-waste disposal site at Hanford. Seven hundred unsaturated conductivity measurements on fifty samples were obtained in only six months total of UFA run time. These data are used to provide realistic information to conceptual models, predictive models and restoration strategies. The UFA instrument consists of an ultracentrifuge with a constant, ultralow flow pump that provides fluid to the sample surface through a rotating seal assembly and microdispersal system. Effluent from the sample is collected in a transparent, volumetrically-calibrated chamber at the bottom of the sample assembly. Using a strobe light, an observer can check the chamber while the sample is being centrifuged. Materials can be run in the UFA as recomposited samples or in situ samples can be subcored directly into the sample UFA chamber.

  9. Quantifying breakage parameters of fragile archaeological components to determine the feasibility of site burial

    E-Print Network [OSTI]

    Rushmore, Forest Paul

    1988-01-01T23:59:59.000Z

    , 1968) ~ The Cahokia site, located in the broad alluvial plain, east of St. Louis, within the Mississippi River Valley known as the American Bottom, is without a doubt 35 the largest prehistoric site in North America north of central Mexico (Fowler...QUANTIFYING BREAKAGE PARAMETERS OF FRAGILE ARCHAEOLOGICAL COMPONENTS TO DETERMINE THE FEASIBILITY OF SITE BURIAL A Thesis by Forest Paul Rushmore III Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment...

  10. Threatened and endangered wildlife species of the Hanford Site related to CERCLA characterization activities

    SciTech Connect (OSTI)

    Fitzner, R.E. [Pacific Northwest Lab., Richland, WA (United States); Weiss, S.G.; Stegen, J.A. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-06-01T23:59:59.000Z

    The US Department of Energy`s (DOE) Hanford Site has been placed on the National Priorities List, which requires that it be remediated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) or Superfund. Potentially contaminated areas of the Hanford Site were grouped into operable units, and detailed characterization and investigation plans were formulated. The DOE Richland Operations Office requested Westinghouse Hanford Company (WHC) to conduct a biological assessment of the potential impact of these characterization activities on the threatened, endangered, and sensitive wildlife species of the Hanford Site. Additional direction for WHC compliances with wildlife protection can be found in the Environmental Compliance Manual. This document is intended to meet these requirements, in part, for the CERCLA characterization activities, as well as for other work comparable in scope. This report documents the biological assessment and describes the pertinent components of the Hanford Site as well as the planned characterization activities. Also provided are accounts of endangered, threatened, and federal candidate wildlife species on the Hanford Site and information as to how human disturbances can affect these species. Potential effects of the characterization activities are described with recommendations for mitigation measures.

  11. After the wind resource and project site have been determined and the community outreach effort has

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    permit application. See the Fact Sheets on resource assessment and wind resource data for more: Technology Performance Impacts & Issues Siting Resource Assessment Wind Data Permitting Case Studies 1. 2. 3After the wind resource and project site have been determined and the community outreach effort has

  12. Characterization ReportOperational Closure Covers for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada Geotechnical Sciences

    2005-06-01T23:59:59.000Z

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Area 3 RWMS is located in south-central Yucca Flat and the Area 5 RWMS is located about 15 miles south, in north-central Frenchman Flat. Though located in two separate topographically closed basins, they are similar in climate and hydrogeologic setting. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste, while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. Over the next several decades, most waste disposal units at both the Area 3 and Area 5 RWMSs are anticipated to be closed. Closure of the Area 3 and Area 5 RWMSs will proceed through three phases: operational closure, final closure, and institutional control. Many waste disposal units at the Area 5RWMS are operationally closed and final closure has been placed on one unit at the Area 3 RWMS (U-3ax/bl). Because of the similarities between the two sites (e.g., type of wastes, environmental factors, operational closure cover designs, etc.), many characterization studies and data collected at the Area 3 RWMS are relevant and applicable to the Area 5 RWMS. For this reason, data and closure strategies from the Area 3 RWMS are referred to as applicable. This document is an interim Characterization Report – Operational Closure Covers, for the Area 5 RWMS. The report briefly describes the Area 5 RWMS and the physical environment where it is located, identifies the regulatory requirements, reviews the approach and schedule for closing, summarizes the monitoring programs, summarizes characterization studies and results, and then presents conclusions and recommendations.

  13. Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Appendix D, Addenda D1--D7

    SciTech Connect (OSTI)

    Ludlam, J.R.

    1985-01-01T23:59:59.000Z

    This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation foe the US Department of Energy (DOE), Grand Junction Project Office, in response to and in accord with a Statement of Work prepared by the DOE Uranium Mill tailings Remedial Action Project (UMTRAP) Technical Assistance Contractor, Jacobs Engineering Group, Inc. the objective of this project was to determine the horizontal and vertical extent of contamination that exceeds the US Environmental Protection Agency (EPA) standards at the Mexican Hat site. The data presented in this report are required for characterization of the areas adjacent to the Mexican Hat tailings piles and for the subsequent design of cleanup activities. Some on-pile sampling was required to determine the depth of the 15-pCi/g Ra-226 interface in an area where wind and water erosion has taken place.

  14. Nevada Test Site Perspective on Characterization and Loading of Legacy Transuranic Drums Utilizing the Central Characterization Project

    SciTech Connect (OSTI)

    R.G. Lahoud; J. F. Norton; I. L. Siddoway; L. W. Griswold

    2006-01-01T23:59:59.000Z

    The Nevada Test Site (NTS) has successfully completed a multi-year effort to characterize and ship 1860 legacy transuranic (TRU) waste drums for disposal at the Waste Isolation Pilot Plant (WIPP), a permanent TRU disposal site. This has been a cooperative effort among the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), the U.S. Department of Energy, Carlsbad Field Office (DOE/CBFO), the NTS Management and Operations (M&O) contractor Bechtel Nevada (BN), and various contractors under the Central Characterization Project (CCP) umbrella. The success is due primarily to the diligence, perseverance, and hard work of each of the contractors, the DOE/CBFO, and NNSA/NSO, along with the support of the U.S. Department of Energy, Headquarters (DOE/HQ). This paper presents, from an NTS perspective, the challenges and successes of utilizing the CCP for obtaining a certified characterization program, sharing responsibilities for characterization, data validation, and loading of TRU waste with BN to achieve disposal at WIPP from a Small Quantity Site (SQS) such as the NTS. The challenges in this effort arose from two general sources. First, the arrangement of DOE/CBFO contractors under the CCP performing work and certifying waste at the NTS within a Hazard Category 2 (HazCat 2) non-reactor nuclear facility operated by BN, presented difficult challenges. The nuclear safety authorization basis, safety liability and responsibility, conduct of operations, allocation and scheduling of resources, and other issues were particularly demanding. The program-level and field coordination needed for the closely interrelated characterization tasks was extensive and required considerable effort by all parties. The second source of challenge was the legacy waste itself. None of the waste was generated at the NTS. The waste was generated at Lawrence Livermore National Laboratory (LLNL), Lawrence Berkeley Laboratory (LBL), Lynchburg, Rocky Flats Environmental Technology Site (RFETS), and a variety of other sites over 20 years ago, making the development of Acceptable Knowledge a significant and problematic effort. In addition, the characterization requirements, and data quality objectives for shipment and WIPP disposal today, were non-existent when this waste was generated, resulting in real-time adjustments to unexpected conditions.

  15. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    SciTech Connect (OSTI)

    NONE

    1988-01-01T23:59:59.000Z

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

  16. Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives

    SciTech Connect (OSTI)

    Biedscheid, J.; Stahl, S.; Devarakonda, M.; Peters, K.; Eide, J.

    2002-02-26T23:59:59.000Z

    The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste prior to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP characterization program uses primarily acceptable knowledge (AK) and visual examination (VE) during waste packaging to characterize RH-TRU waste. These methods are used to estimate physical waste parameters, including weight percentages of metals, cellulosics, plastics, and rubber in the waste, and to determine the absence of prohibited items, including free liquids. AK combined with computer modeling is used to estimate radiological waste parameters, including total activity on a waste container basis, for the majority of BCLDP RH-TRU waste. AK combined with direct analysis is used to characterize radiological parameters for the small populations of the RH-TRU waste generated by the BCLDP. All characterization based on AK is verified. Per its design for comprehensive waste data collection, the BCLDP characterization program using AK and waste packaging procedures, including VE during packaging, meets the proposed WIPP RH-TRU waste characterization objectives. The conservative program design implemented generates certification data that will be adequate to meet any additional program requirements that may be imposed by the CBFO.

  17. Drift design methodology and preliminary application for the Yucca Mountain Site Characterization Project; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Hardy, M.P. [Agapito (J.F.T.) and Associates, Inc., Grand Junction, CO (United States); Bauer, S.J. [Sandia National Labs., Albuquerque, NM (United States)

    1991-12-01T23:59:59.000Z

    Excavation stability in an underground nuclear waste repository is required during construction, emplacement, retrieval (if required), and closure phases to ensure worker health and safety, and to prevent development of potential pathways for radionuclide migration in the post-closure period. Stable excavations are developed by appropriate excavation procedures, design of the room shape, design and installation of rock support reinforcement systems, and implementation of appropriate monitoring and maintenance programs. In addition to the loads imposed by the in situ stress field, the repository drifts will be impacted by thermal loads developed after waste emplacement and, periodically, by seismic loads from naturally occurring earthquakes and underground nuclear events. A priori evaluation of stability is required for design of the ground support system, to confirm that the thermal loads are reasonable, and to support the license application process. In this report, a design methodology for assessing drift stability is presented. This is based on site conditions, together with empirical and analytical methods. Analytical numerical methods are emphasized at this time because empirical data are unavailable for excavations in welded tuff either at elevated temperatures or under seismic loads. The analytical methodology incorporates analysis of rock masses that are systematically jointed, randomly jointed, and sparsely jointed. In situ thermal and seismic loads are considered. Methods of evaluating the analytical results and estimating ground support requirements for all the full range of expected ground conditions are outlines. The results of a preliminary application of the methodology using the limited available data are presented. 26 figs., 55 tabs.

  18. Overburden characterization and post-burn study of the Hoe Creek, Wyoming underground coal gasification site and comparison with the Hanna, Wyoming site

    SciTech Connect (OSTI)

    Ethridge, F.C.; Burns, L.K.; Alexander, W.G.; Craig, G.N. II; Youngberg, A.D.

    1983-01-01T23:59:59.000Z

    In 1978 the third test (Hoe Creek III) in a series of underground coal gasification (UCG) experiments was completed at a site south of Gillette, Wyoming. The post-burn study of the geology of the overburden and interlayered rock of the two coal seams affected by the experiment is based on the study of fifteen cores. The primary purpose of the study was to characterize the geology of the overburden and interlayered rock and to determine and evaluate the mineralogical and textural changes that were imposed by the experiment. Within the burn cavity the various sedimentary units have been brecciated and thermally altered to form several pyrometamorphic rock types of paralava rock, paralava breccia, buchite, buchite breccia and hornfels. High temperature minerals of mullite, cordierite, oligo-clase-andesine, tridymite, cristobalite, clinopyroxenes, and magnetite are common in the pyrometamorphic rocks. The habit of these minerals indicates that they crystallized from a melt. These minerals and textures suggest that the rocks were formed at temperatures between 1200/sup 0/ and 1400/sup 0/C. A comparison of geologic and geological-technological factors between the Hoe Creek III site, which experienced substantial roof collapse, and the Hanna II site, which had only moderate roof collapse, indicates that overburden thickness relative to coal seam thickness, degree of induration of overburden rock, injection-production well spacing, and ultimate cavity size are important controls of roof collapse in the structural setting of the two sites.

  19. Site characterization progress report: Yucca Mountain, Nevada, October 1, 1993--March 31, 1994

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This report is the tenth in a series issued at intervals of approximately six months during site characterization of Yucca Mountain as a possible site for a geologic repository for the permanent disposal of spent nuclear fuel and high-level radioactive waste. Also included in this report are descriptions of activities such as public outreach and international programs that are not formally part of the site characterization process. Information on these activities is provided to report on all aspects of the Yucca Mountain studies. The Executive Summary is intended to provide a summary of major decisions, activities, accomplishments, and issues of interest during the reporting period. Chapter 1, Introduction, provides background information to assist the reader in understanding the current status of the program. Chapter 2 provides specific detailed discussions of activities conducted during the current reporting period and has two major divisions. Section 2.1, Preparatory Activities, provides information on select preparatory activities necessary to conduct site characterization and design activities. Sections 2.2 through 2.8 provide specific details on studies and activities conducted during the reporting period and follow the original structure of the Department`s 1988 Site Characterization Plan. Chapter 3 contains the current summary schedule, while Chapter 4 provides a description of the program outreach, including activities during the reporting period, in both the international program and public outreach. Chapter 5 presents an epilogue of significant events that occurred after the end of the reporting period.

  20. Site characterization progress report: Yucca Mountain, Nevada. October 1, 1996--March 31, 1997

    SciTech Connect (OSTI)

    NONE

    1997-10-01T23:59:59.000Z

    The report is the sixteenth in a series issued approximately every six months to report progress and results of site characterization activities being conducted to evaluate Yucca Mountain as a possible geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. This report highlights work started, in progress, and completed during the reporting period. In addition, this report documents and discusses changes to the Office of Civilian Radioactive Waste Management (OCRWM) Site Characterization Program (Program) resulting from the ongoing collection and evaluation of site information, systems analyses, development of repository and waste package designs, and results of performance assessment activities. Details on the activities summarized can be found in the numerous technical reports cited throughout the progress report. Yucca Mountain Site Characterization Project (Project) activities this period focused on implementing the near-term objectives of the revised Program Plan issued last period. Near-term objectives of the revised Program Plan include updating the US Department of Energy`s (DOE) repository siting guidelines to be consistent with a more focused performance-driven program; supporting an assessment in 1998 of the viability of continuing with actions leading to the licensing of a repository; and if the site is suitable, submittal of a Secretarial site recommendation to the President in 2001 and license application the US Nuclear Regulatory Commission (NRC) in 2002. During this reporting period, the Project developed and baselined its long-range plan in December 1996. That revision reflected the detailed fiscal year (FY) 1997 work scope and funding plan previously baselined at the end of FY 1996. Site characterization activities have been focused to answer the major open technical issues and to support the viability assessment.

  1. Argonne National Laboratory Expedited Site Characterization: First International Symposium on Integrated Technical Approaches to Site Characterization - Proceedings Volume

    SciTech Connect (OSTI)

    NONE

    1998-06-08T23:59:59.000Z

    Laboratory applications for the analysis of PCBS (polychlorinated biphenyls) in environmental matrices such as soil/sediment/sludge and oil/waste oil were evaluated for potential reduction in waste, source reduction, and alternative techniques for final determination. As a consequence, new procedures were studied for solvent substitution, miniaturization of extraction and cleanups, minimization of reagent consumption, reduction of cost per analysis, and reduction of time. These new procedures provide adequate data that meet all the performance requirements for the determination of PCBS. Use of the new procedures reduced costs for all sample preparation techniques. Time and cost were also reduced by combining the new sample preparation procedures with the power of fast gas chromatography. Separation of Aroclor 1254 was achieved in less than 6 min by using DB-1 and SPB-608 columns. With the greatly shortened run times, reproducibility can be tested quickly and consequently with low cost. With performance-based methodology, the applications presented here can be applied now, without waiting for regulatory approval.

  2. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    SciTech Connect (OSTI)

    Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1995-05-01T23:59:59.000Z

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

  3. Geochemical Characterization of Chromate Contamination in the 100 Area Vadose Zone at the Hanford Site

    SciTech Connect (OSTI)

    Dresel, P. Evan; Qafoku, Nikolla; McKinley, James P.; Fruchter, Jonathan S.; Ainsworth, Calvin C.; Liu, Chongxuan; Ilton, Eugene S.; Phillips, J. L.

    2008-07-16T23:59:59.000Z

    The major objectives of the proposed study were to: 1.) determine the leaching characteristics of hexavalent chromium [Cr(VI)] from contaminated sediments collected from 100 Area spill sites; 2.) elucidate possible Cr(VI) mineral and/or chemical associations that may be responsible for Cr(VI) retention in the Hanford Site 100 Areas through the use of i.) macroscopic leaching studies and ii.) microscale characterization of contaminated sediments; and 3.) provide information to construct a conceptual model of Cr(VI) geochemistry in the Hanford 100 Area vadose zone. In addressing these objectives, additional benefits accrued were: (1) a fuller understanding of Cr(VI) entrained in the vadose zone that will that can be utilized in modeling potential Cr(VI) source terms, and (2) accelerating the Columbia River 100 Area corridor cleanup by providing valuable information to develop remedial action based on a fundamental understanding of Cr(VI) vadose zone geochemistry. A series of macroscopic column experiments were conducted with contaminated and uncontaminated sediments to study Cr(VI) desorption patterns in aged and freshly contaminated sediments, evaluate the transport characteristics of dichromate liquid retrieved from old pipelines of the 100 Area; and estimate the effect of strongly reducing liquid on the reduction and transport of Cr(VI). Column experiments used the < 2 mm fraction of the sediment samples and simulated Hanford groundwater solution. Periodic stop-flow events were applied to evaluate the change in elemental concentration during time periods of no flow and greater fluid residence time. The results were fit using a two-site, one dimensional reactive transport model. Sediments were characterized for the spatial and mineralogical associations of the contamination using an array of microscale techniques such as XRD, SEM, EDS, XPS, XMP, and XANES. The following are important conclusions and implications. Results from column experiments indicated that most of contaminant Cr travels fast through the sediments and appears as Cr(VI) in the effluents. The significance of this for groundwater concentrations would, however, depend on the mass flux of recharge to the water table. adsorption of Cr(VI) to sediments from spiked Cr(VI) solution is low; calculated retardation coefficients are close to one. Calcium polysulfide solutions readily reduced Cr(VI) to Cr(III) in column experiments. However a significant amount of the Cr(VI) was mobilized ahead of the polysulfide solution front. This has significant implications for in-situ reductive remediation techniques. The experiments suggest that it would be difficult to design a remedial measure using infiltration of liquid phase reductants without increasing transport of Cr(VI) toward the water table. The microscopic characterization results are consistent with the column studies. Cr(VI) is found as ubiquitous coatings on sediment grain surfaces. Small, higher concentration, chromium sites are associated with secondary clay mineral inclusions, with occasional barium chromate minerals, and reduced to Cr(III) in association with iron oxides that are most likely magnetite primary minerals. Within the restricted access domains of sediment matrix, ferrous iron could also diffuse from in situ, high-surface-area minerals to cause the reductive immobilization of chromate. This process may be favored at microscale geochemical zones where ferrous iron could be supplied. Once nucleated, micrometer-scale precipitates are favored as growing locales for further accumulation, causing the formation of discrete zones of Cr(III).

  4. Natural Gas Storage in Basalt Aquifers of the Columbia Basin, Pacific Northwest USA: A Guide to Site Characterization

    SciTech Connect (OSTI)

    Reidel, Steve P.; Spane, Frank A.; Johnson, Vernon G.

    2002-08-08T23:59:59.000Z

    This report provides the technical background and a guide to characterizing a site for storing natural gas in the Columbia River Basalt

  5. AEROSOL CHEMICAL COMPOSITION CHARACTERIZATION AT THE ARM SOUTHERN GREAT PLAINS (SGP) SITE USING AN AEROSOL CHEMICAL

    E-Print Network [OSTI]

    AEROSOL CHEMICAL COMPOSITION CHARACTERIZATION AT THE ARM SOUTHERN GREAT PLAINS (SGP) SITE USING AN AEROSOL CHEMICAL SPECIATION MONITOR Yin-Nan Lee1 , Fan Mei1 , Stephanie DeJong1 , Anne Jefferson2 1 Atmospheric Sciences Division, Brookhaven National Lab, Upton, NY 2 CIRES, University of Colorado, Boulder, CO

  6. Pre-site Characterization Risk Analysis for Commercial-Scale Carbon Sequestration

    E-Print Network [OSTI]

    Lu, Zhiming

    Pre-site Characterization Risk Analysis for Commercial-Scale Carbon Sequestration Zhenxue Dai a probability framework to evaluate subsurface risks associated with commercial-scale carbon sequestration to the atmosphere.1-3 The Big Sky Carbon Sequestration Partnership (BSCSP) is one of seven partnerships tasked

  7. Characterization of Pu-contaminated soils from Nuclear Site 201 at the Nevada Test Site

    SciTech Connect (OSTI)

    Lee, S.Y.; Tamura, T.; Larsen, I.L.

    1983-01-01T23:59:59.000Z

    Distribution and characteristics of Pu-bearing radioactive particles throughout five soil profiles from Nuclear Site (NS) 201 were investigated. Concentrations of /sup 239/ /sup 240/Pu and /sup 241/Am decreased with depth and most of the contamination was contained in the top 5 cm except in profile 4 where it extended to 10 cm. The mean activity ratio of /sup 239/ /sup 240/Pu to /sup 241/Am and its standard error were 5.8 +- 0.3 (N=42). Most of the total radioactivity of the soils was contributed by 0.25 to 2 mm sand size fraction which comprised 20 to 50% by weight of the soils. The radioactive particles in the 0.25 to 2 mm size fraction occurred as spherical glass particles or as glass coatings on sand particles. The glass coatings had gas voids in the matrix but were not as porous as the radioactive particles from NS 219. After impact grinding the >0.25-mm size fractions for one hour, 85% of the initial activity in a NS 201 sample remained with the particles on the 0.25 mm sieve, whereas in the NS 219 sample only 10% remained. The results show that the radioactive particles from NS 201 were much more stable against the impact grinding force than those from NS 219. Therefore, the NS 201 soils would be expected to have a lower probability of producing respirable-size radioactive particles by saltation during wind erosion. 19 references, 3 figures, 3 tables.

  8. Determination of total cyanide in Hanford Site high-level wastes

    SciTech Connect (OSTI)

    Winters, W.I. [Westinghouse Hanford Co., Richland, WA (United States); Pool, K.H. [Pacific Northwest Lab., Richland, WA (United States)

    1994-05-01T23:59:59.000Z

    Nickel ferrocyanide compounds (Na{sub 2-x}Cs{sub x}NiFe (CN){sub 6}) were produced in a scavenging process to remove {sup 137}Cs from Hanford Site single-shell tank waste supernates. Methods for determining total cyanide in Hanford Site high-level wastes are needed for the evaluation of potential exothermic reactions between cyanide and oxidizers such as nitrate and for safe storage, processing, and management of the wastes in compliance with regulatory requirements. Hanford Site laboratory experience in determining cyanide in high-level wastes is summarized. Modifications were made to standard cyanide methods to permit improved handling of high-level waste samples and to eliminate interferences found in Hanford Site waste matrices. Interferences and associated procedure modifications caused by high nitrates/nitrite concentrations, insoluble nickel ferrocyanides, and organic complexants are described.

  9. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 1, Introduction, history, and current candidates

    SciTech Connect (OSTI)

    Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

    1995-08-01T23:59:59.000Z

    The purpose of the Yucca Mountain Site Characterization Project is to evaluate Yucca Mountain for its suitability as a potential site for the nation`s first high-level nuclear waste repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) has been occupied for a number of years with developing and evaluating the performance of waste packages for the potential repository. In recent years this work has been carried out under the guidance of and in collaboration with the Management and Operating contractor for the Civilian Radioactive Waste Management System, TRW Environmental Safety Systems, Inc., which in turn reports to the Office of Civilian Radioactive Waste Management of the US Department of Energy. This report summarizes the history of the selection and characterization of materials to be used in the engineered barrier system for the potential repository at Yucca Mountain, describes the current candidate materials, presents a compilation of their properties, and summarizes available corrosion data and modeling. The term ``engineered materials`` is intended to distinguish those materials that are used as part of the engineered barrier system from the natural, geologic materials of the site.

  10. Final Characterization Report for Corrective Action Unit 109: Area 2 U-2BU Crater, Nevada Test Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    ITLV

    1998-12-01T23:59:59.000Z

    Corrective Action Unit 109, Area 2 U-2bu Crater, is an inactive Resource Conservation and Recovery Act Part A Permit disposal unit located in Area 2 at the Nevada Test Site, Nevada. The Corrective Action Unit has been characterized under the requirements of the Nevada Test Site Resource Conservation and Recovery Act, Part A Permit (NDEP, 1995) and Title 40 Code of Federal Regulations Part 265 (CFR, 1996). The site characterization was performed under the RCRA Part A Permit Characterization Plan for the U-2bu Subsidence Crater (DOE/NV, 1998c), as approved by the Nevada Division of Environmental Protection (Liebendorfer, 1998). The primary objective of the site characterization activities was to evaluate the presence, concentration, and extent of any Resource Conservation and Recovery Act contaminants in the crater. Surface soil samples were collected on April 22, 1998, and subsurface soil samples and geotechnical samples were collected from April 27-29, 1998. Soil samples were collected using a hand auger or a piston-type drive hammer to advance a 5-centimeter (2-inch) diameter steel sampling tool into the ground. The permit for the Nevada Test Site requires that Corrective Action Unit 109 be closed under 40 Code of Federal Regulations 265 Subpart G and 40 Code of Federal Regulations Part 265.310 (CFR, 1996). Analysis of the data collected during the characterization effort indicates that lead was detected in Study Area 1 at 5.7 milligrams per liter, above the regulatory level in 40 Code of Federal Regulations 261.24 of 5.0 milligrams per liter. Except for the lead detection at a single location within the crater, the original Resource Conservation Recovery Act constituents of potential concern determined between the U.S. Department of Energy, Nevada Operations Office and the Nevada Department of Environmental Protection during the Data Quality Objectives process (DOE/NV, 1998b) were not found to be present at Corrective Action Unit 109 above regulatory levels of concern. The single lead detection that exceeded regulatory limits was discovered at a depth of 1.2 meters (4 feet) in Study Area 1. Total petroleum hydrocarbons were detected in Study Area 4 at two locations at concentrations of 130 and 190 milligrams per kilogram. These concentrations exceed the 100 milligram per kilogram action level established in Nevada Administrative Code 445A.2272 (NAC, 1996). The primary conceptual model identified during the Data Quality Objectives process appears to have been substantiated by the analytical results from site characterization; migration of contaminants of potential concern does not appear to be occurring, as none were detected in a significant percentage of the characterization samples. Based on the results of the characterization, clean closure by removal and disposal of impacted soil will be evaluated in the closure plan to address Study Area 1. An (a) through (k) analysis, as specified in Nevada Administrative Code 445A.227, should be used to evaluate total petroleum hydrocarbon contamination within Study Area 4. Study Areas 2, 3, and 5 should be clean closed without further assessment or remediation (see Figures 2-1 and 5-1 in the Characterization Report).

  11. Conversion of the Bryan Mound geological site characterization reports to a three-dimensional model.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Rautman, Christopher Arthur

    2005-04-01T23:59:59.000Z

    The Bryan Mound salt dome, located near Freeport, Texas, is home to one of four underground crude oil-storage facilities managed by the U. S. Department of Energy Strategic Petroleum Reserve (SPR) Program. Sandia National Laboratories, as the geotechnical advisor to the SPR, conducts site-characterization investigations and other longer-term geotechnical and engineering studies in support of the program. This report describes the conversion of two-dimensional geologic interpretations of the Bryan Mound site into three-dimensional geologic models. The new models include the geometry of the salt dome, the surrounding sedimentary units, mapped faults, and the 20 oil-storage caverns at the site. This work provides an internally consistent geologic model of the Bryan Mound site that can be used in support of future work.

  12. Conversion of the Big Hill geological site characterization report to a three-dimensional model.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Rautman, Christopher Arthur

    2003-02-01T23:59:59.000Z

    The Big Hill salt dome, located in southeastern Texas, is home to one of four underground oil-storage facilities managed by the U. S. Department of Energy Strategic Petroleum Reserve (SPR) Program. Sandia National Laboratories, as the geotechnical advisor to the SPR, conducts site-characterization investigations and other longer-term geotechnical and engineering studies in support of the program. This report describes the conversion of two-dimensional geologic interpretations of the Big Hill site into three-dimensional geologic models. The new models include the geometry of the salt dome, the surrounding sedimentary units, mapped faults, and the 14 oil storage caverns at the site. This work provides a realistic and internally consistent geologic model of the Big Hill site that can be used in support of future work.

  13. Conversion of the West Hackberry geological site characterization report to a three-dimensional model.

    SciTech Connect (OSTI)

    Stein, Joshua S.; Rautman, Christopher Arthur; Snider, Anna C.

    2004-08-01T23:59:59.000Z

    The West Hackberry salt dome, in southwestern Louisiana, is one of four underground oil-storage facilities managed by the U. S. Department of Energy Strategic Petroleum Reserve (SPR) Program. Sandia National Laboratories, as the geotechnical advisor to the SPR, conducts site-characterization investigations and other longer-term geotechnical and engineering studies in support of the program. This report describes the conversion of two-dimensional geologic interpretations of the West Hackberry site into three-dimensional geologic models. The new models include the geometry of the salt dome, the surrounding sedimentary layers, mapped faults, and a portion of the oil storage caverns at the site. This work provides a realistic and internally consistent geologic model of the West Hackberry site that can be used in support of future work.

  14. Applicability of petroleum horizontal drilling technology to hazardous waste site characterization and remediation

    SciTech Connect (OSTI)

    Goranson, C.

    1992-09-01T23:59:59.000Z

    Horizontal wells have the potential to become an important tool for use in characterization, remediation and monitoring operations at hazardous waste disposal, chemical manufacturing, refining and other sites where subsurface pollution may develop from operations or spills. Subsurface pollution of groundwater aquifers can occur at these sites by leakage of surface disposal ponds, surface storage tanks, underground storage tanks (UST), subsurface pipelines or leakage from surface operations. Characterization and remediation of aquifers at or near these sites requires drilling operations that are typically shallow, less than 500-feet in depth. Due to the shallow nature of polluted aquifers, waste site subsurface geologic formations frequently consist of unconsolidated materials. Fractured, jointed and/or layered high compressive strength formations or compacted caliche type formations can also be encountered. Some formations are unsaturated and have pore spaces that are only partially filled with water. Completely saturated underpressured aquifers may be encountered in areas where the static ground water levels are well below the ground surface. Each of these subsurface conditions can complicate the drilling and completion of wells needed for monitoring, characterization and remediation activities. This report describes some of the equipment that is available from petroleum drilling operations that has direct application to groundwater characterization and remediation activities. A brief discussion of petroleum directional and horizontal well drilling methodologies is given to allow the reader to gain an understanding of the equipment needed to drill and complete horizontal wells. Equipment used in river crossing drilling technology is also discussed. The final portion of this report is a description of the drilling equipment available and how it can be applied to groundwater characterization and remediation activities.

  15. Site Characterization Data from the U3ax/bl Exploratory Boreholes at the Nevada Test Site

    SciTech Connect (OSTI)

    Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-08-01T23:59:59.000Z

    This report provides qualitative analyses and preliminary interpretations of hydrogeologic data obtained from two 45-degree, slanted exploratory boreholes drilled within the Area 3 Radioactive Waste Management Site (RWMS) at the Nevada Test Site. Borehole UE-3bl-D1 was drilled beneath the U3ax/bl mixed waste disposal unit, and Borehole UE-3bl-U1 was drilled in undisturbed alluvium adjacent to the disposal unit. The U3ax/bl disposal unit is located within two conjoined subsidence craters, U3ax and U3bl, which were created by underground nuclear testing. Data from these boreholes were collected to support site characterization activities for the U3ax/bl disposal unit and the entire Area 3 RWMS. Site characterization at disposal units within the Area 3 RWMS must address the possibility that subsidence craters and associated disturbed alluvium of the chimneys beneath the craters might serve as pathways for contaminant migration. The two boreholes were drilled and sampled to compare hydrogeologic properties of alluvium below the waste disposal unit with those of adjacent undisturbed alluvium. Whether Borehole UE-3bl-D1 actually penetrated the chimney of the U3bl crater is uncertain. Analyses of core samples showed little difference in hydrogeologic properties between the two boreholes. Important findings of this study include the following: No hazardous or radioactive constituents of waste disposal concern were found in the samples obtained from either borehole. No significant differences in physical and hydrogeologic properties between boreholes is evident, and no evidence of significant trends with depth for any of these properties was observed. The values observed are typical of sandy materials. The alluvium is dry, with volumetric water content ranging from 5.6 to 16.2 percent. Both boreholes exhibit a slight increase in water content with depth, the only such trend observed. Water potential measurements on core samples from both boreholes show a large positive potential gradient (water moves upward, via evapotranspiration) for the entire vertical depth. Very little liquid flow occurs through the vadose zone. The direction of flow in the upper vadose zone (approximately the upper 35 meters) is upward, based on unsaturated hydraulic conductivity data, water potential data, and environmental tracer data.

  16. Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices

    SciTech Connect (OSTI)

    NONE

    1985-05-01T23:59:59.000Z

    Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques.

  17. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 2, Design data

    SciTech Connect (OSTI)

    Konynenburg, R.A.; McCright, R.D. [Lawrence Livermore National Lab., CA (United States); Roy, A.K. [B and W Fuel Co., Lynchburg, VA (United States); Jones, D.A. [Nevada Univ., Reno, NV (United States)

    1995-08-01T23:59:59.000Z

    This is Volume 2 of the Engineered Materials Characterization Report which presents the design data for candidate materials needed in fabricating different components for both large and medium multi-purpose canister (MPC) disposal containers, waste packages for containing uncanistered spent fuel (UCF), and defense high-level waste (HLW) glass disposal containers. The UCF waste package consists of a disposal container with a basket therein. It is assumed that the waste packages will incorporate all-metallic multibarrier disposal containers to accommodate medium and large MPCs, ULCF, and HLW glass canisters. Unless otherwise specified, the disposal container designs incorporate an outer corrosion-allowance metal barrier over an inner corrosion-resistant metal barrier. The corrosion-allowance barrier, which will be thicker than the inner corrosion-resistant barrier, is designed to undergo corrosion-induced degradation at a very low rate, thus providing the inner barrier protection from the near-field environment for a prolonged service period.

  18. A Ten Step Protocol and Plan for CCS Site Characterization, Based on an Analysis of the Rocky Mountain Region, USA

    SciTech Connect (OSTI)

    McPherson, Brian; Matthews, Vince

    2013-09-15T23:59:59.000Z

    This report expresses a Ten-Step Protocol for CO2 Storage Site Characterization, the final outcome of an extensive Site Characterization analysis of the Rocky Mountain region, USA. These ten steps include: (1) regional assessment and data gathering; (2) identification and analysis of appropriate local sites for characterization; (3) public engagement; (4) geologic and geophysical analysis of local site(s); (5) stratigraphic well drilling and coring; (6) core analysis and interpretation with other data; (7) database assembly and static model development; (8) storage capacity assessment; (9) simulation and uncertainty assessment; (10) risk assessment. While the results detailed here are primarily germane to the Rocky Mountain region, the intent of this protocol is to be portable or generally applicable for CO2 storage site characterization.

  19. Yucca Mountain Site Characterization Project Bibliography, January--June 1993. An update: Supplement 4, Addendum 1

    SciTech Connect (OSTI)

    Stephan, P.M. [ed.

    1995-01-01T23:59:59.000Z

    Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1994 through June 30, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers,and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

  20. Yucca Mountain Site Characterization Project bibliography, January--June 1995. Supplement 4, Add.3: An update

    SciTech Connect (OSTI)

    Stephan, P.M. [ed.

    1996-01-01T23:59:59.000Z

    Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1995, through June 30, 1995. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

  1. AREA COMPLETION STRATEGIES AT SAVANNAH RIVER SITE: CHARACTERIZATION FOR CLOSURE AND BEYOND

    SciTech Connect (OSTI)

    Bagwell, L; Mark Amidon, M; Sadika Baladi, S

    2007-06-11T23:59:59.000Z

    During the first four decades of its 56 year existence, the Savannah River Site (SRS) was a key supplier of nuclear material for national defense. During the 1990s, the site's primary missions became waste site closure, environmental restoration, and deactivation and decommissioning (D&D) of remnant cold war apparatus. Since 1989, with the approval of State and Federal regulatory agencies and with the participation of interested stakeholders, SRS has implemented a final remedy for a majority of the more than 500 individual waste sites at the former nuclear materials complex. These waste sites range from small, inert rubble pits to large, heavy industrial areas and radioactive waste disposal grounds. The closure and final remediation of these waste sites mark significant progress toward achieving SRS's overarching goal of reducing or eliminating future environmental damage and human health threats. However, larger challenges remain. For example, what are appropriate and achievable end-states for decommissioned nuclear facilities? What environmental and human health risks are associated with these end-states? To answer these questions within the strictures of smaller budgets and accelerated schedules, SRS is implementing an ''area completion'' strategy that: (1) unites several discrete waste units into one conceptual model, (2) integrates historically disparate environmental characterization and D&D activities, (3) reduces the number of required regulatory documents, and (4) in some cases, compresses schedules for achieving a stakeholder-approved end-state.

  2. Characterization of candidate DOE sites for fabricating MOX fuel for lead assemblies

    SciTech Connect (OSTI)

    Holdaway, R.F.; Miller, J.W.; Sease, J.D.; Moses, R.J.; O`Connor, D.G. [Oak Ridge National Lab., TN (United States); Carrell, R.D. [Technical Resources International, Inc., Richland, WA (United States); Jaeger, C.D. [Sandia National Labs., Albuquerque, NM (United States); Thompson, M.L.; Strasser, A.A. [Delta-21 Resources, Inc., Oak Ridge, TN (United States)

    1998-03-01T23:59:59.000Z

    The Office of Fissile Materials Disposition (MD) of the Department of Energy (DOE) is directing the program to disposition US surplus weapons-usable plutonium. For the reactor option for disposition of this surplus plutonium, MD is seeking to contract with a consortium, which would include a mixed-oxide (MOX) fuel fabricator and a commercial US reactor operator, to fabricate and burn MOX fuel in existing commercial nuclear reactors. This option would entail establishing a MOX fuel fabrication facility under the direction of the consortium on an existing DOE site. Because of the lead time required to establish a MOX fuel fabrication facility and the need to qualify the MOX fuel for use in a commercial reactor, MD is considering the early fabrication of lead assemblies (LAs) in existing DOE facilities under the technical direction of the consortium. The LA facility would be expected to produce a minimum of 1 metric ton heavy metal per year and must be operational by June 2003. DOE operations offices were asked to identify candidate sites and facilities to be evaluated for suitability to fabricate MOX fuel LAs. Savannah River Site, Argonne National Laboratory-West, Hanford, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory were identified as final candidates to host the LA project. A Site Evaluation Team (SET) worked with each site to develop viable plans for the LA project. SET then characterized the suitability of each of the five plans for fabricating MOX LAs using 28 attributes and documented the characterization to aid DOE and the consortium in selecting the site for the LA project. SET concluded that each option has relative advantages and disadvantages in comparison with other options; however, each could meet the requirements of the LA project as outlined by MD and SET.

  3. HABITAT AND BIODIVERSITY MAPPING, FOR THE DETERMINATION OF ALGAL BIOMASS AQUACULTURE SITES IN THE COSTAL AREAS OF PUERTO RICO

    E-Print Network [OSTI]

    Gilbes, Fernando

    HABITAT AND BIODIVERSITY MAPPING, FOR THE DETERMINATION OF ALGAL BIOMASS AQUACULTURE SITES production of algal biomass for the production of biofuels in Puerto Rico. The study evaluates

  4. Application of EPA quality assurance procedures to a soil characterization study at the DOE Nevada Test Site

    SciTech Connect (OSTI)

    Snyder, K.E.; Byers, G.E.; Van Remortel, R.D. [Lockheed-Martin Environmental Systems and Technologies Co., Las Vegas, NV (United States); Gustafson, D.L. [Raytheon Services Nevada, Las Vegas, NV (United States)

    1995-12-01T23:59:59.000Z

    The transfer, modification, and application of well formulated and tested quality assurance (QA) procedures from one project to another deserves consideration. The use of a proven QA program design could result in cost savings and the collection of data with a greater degree of confidence. To test this thesis, a QA program, originally developed for large nationwide Environmental Protection Agency (EPA) programs, was adapted and implemented in a site characterization study at the Department of Energy (DOE) Nevada Test Site to ensure that laboratory data satisfied pre-determined measurement quality objectives (MQOs). The QA Program was adapted from EPA programs such as the National Acid Precipitation Assessment Program, the Environmental Monitoring and Assessment Program, and to a lesser degree, the Comprehensive Environmental Recovery, Compensation and Liability Act (CERCLA) Program. The QA design adopted the batch or lot concept, in which samples are organized into groups of quality samples (non-blinds, blinds, and double-blinds), which were included in each batch to evaluate and control measurement uncertainty and to address sample preparation. Detectability was assessed using instrument detection limits and precision data for low-concentration samples. Precision was assessed using data from reference samples under a two-tiered system based on concentration ranges. Accuracy was investigated in terms of bias with respect to reference values. The results showed that QA concepts developed for previous nationwide EPA programs were successfully adapted for the site-specific DOE project.

  5. CX-005052: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-005052: Categorical Exclusion Determination Shoot 2-Dimensional Seismic at Characterization Site CX(s) Applied: B3.1 Date: 01192011 Location(s): Craig,...

  6. Determination and Characterization of Ice Propagation Mechanisms on Surfaces Undergoing Dropwise Condensation

    E-Print Network [OSTI]

    Dooley, Jeffrey B.

    2011-08-08T23:59:59.000Z

    The mechanisms responsible for ice propagation on surfaces undergoing dropwise condensation have been determined and characterized. Based on experimental data acquired non-invasively with high speed quantitative microscopy, the freezing process...

  7. Scenarios constructed for basaltic igneous activity at Yucca Mountain and vicinity; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Barr, G.E.; Dunn, E.; Dockery, H.; Barnard, R. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Valentine, G.; Crowe, B. [Los Alamos National Lab., NM (United States)] [Los Alamos National Lab., NM (United States)

    1993-08-01T23:59:59.000Z

    Basaltic volcanism has been identified as a possible future event initiating a release of radionuclides from a potential repository at the proposed Yucca Mountain high-level waste repository site. The performance assessment method set forth in the Site Characterization Plan (DOE, 1988) requires that a set of scenarios encompassing all significant radionuclide release paths to the accessible environment be described. This report attempts to catalogue the details of the interactions between the features and processes produced by basaltic volcanism in the presence of the presumed groundwater flow system and a repository structure, the engineered barrier system (EBS), and waste. This catalogue is developed in the form of scenarios. We define a scenario as a well-posed problem, starting from an initiating event or process and proceeding through a logically connected and physically possible combination or sequence of features, events, and processes (FEPs) to the release of contaminants.

  8. Yucca Mountain Site Characterization Project Bibliography, July--December 1994: An update

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Charactrization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Science and Technology Database from July 1, 1994 through December 31, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

  9. Initial source and site characterization studies for the U.C. Santa Barbara campus

    SciTech Connect (OSTI)

    Archuleta, R.; Nicholson, C.; Steidl, J.; Gurrola, L.; Alex, C.; Cochran, E.; Ely, G.; Tyler, T. [University of California, Santa Barbara (United States)

    1997-12-01T23:59:59.000Z

    The University of California Campus-Laboratory Collaboration (CLC) project is an integrated 3 year effort involving Lawrence Livermore National Laboratory (LLNL) and four UC campuses - Los Angeles (UCLA), Riverside (UCR), Santa Barbara (UCSB), and San Diego (UCSD) - plus additional collaborators at San Diego State University (SDSU), at Los Alamos National Laboratory and in industry. The primary purpose of the project is to estimate potential ground motions from large earthquakes and to predict site-specific ground motions for one critical structure on each campus. This project thus combines the disciplines of geology, seismology, geodesy, soil dynamics, and earthquake engineering into a fully integrated approach. Once completed, the CLC project will provide a template to evaluate other buildings at each of the four UC campuses, as well as provide a methodology for evaluating seismic hazards at other critical sites in California, including other UC locations at risk from large earthquakes. Another important objective of the CLC project is the education of students and other professional in the application of this integrated, multidisciplinary, state-of-the-art approach to the assessment of earthquake hazard. For each campus targeted by the CLC project, the seismic hazard study will consist of four phases: Phase I - Initial source and site characterization, Phase II - Drilling, logging, seismic monitoring, and laboratory dynamic soil testing, Phase III - Modeling of predicted site-specific earthquake ground motions, and Phase IV - Calculations of 3D building response. This report cover Phase I for the UCSB campus and incudes results up through March 1997.

  10. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 2, Part A: Chapters 3, 4, and 5

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1--5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 575 refs., 84 figs., 68 tabs.

  11. CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP

    SciTech Connect (OSTI)

    Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

    2003-02-27T23:59:59.000Z

    The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

  12. Satellite remote sensing characterization of fish spawning aggregation sites in Puerto Rico and the United States Virgin Islands

    E-Print Network [OSTI]

    Gilbes, Fernando

    Satellite remote sensing characterization of fish spawning aggregation sites in Puerto Rico investigates the seasonality of the satellite-derived chlorophyll signal (Chl-a) at eight (8) established fish influence this signal. These fish spawning aggregation sites are recurrent, meaning that fish (i.e., red

  13. E-Print Network 3.0 - active site determination Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of Geophysics, Center for Rock Abuse Collection: Fossil Fuels ; Geosciences 7 SITE MAINTENANCE PLAN CSMRI SITE REMEDIATION Summary: CSMRI SITE REMEDIATION 1.0 HISTORY ...

  14. Yucca Mountain Site Characterization Project bibliography, 1992--1994. Supplement 4

    SciTech Connect (OSTI)

    NONE

    1992-06-01T23:59:59.000Z

    Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1992, through December 31, 1993. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it. Earlier information on this project can be found in the first bibliography DOE/TIC-3406, which covers 1977--1985, and its three supplements DOE/OSTI-3406(Suppl.1), DOE/OSTI-3406(Suppl.2), and DOE/OSTI-3406(Suppl.3), which cover information obtained during 1986--1987, 1988--1989, and 1990--1991, respectively. All entries in the bibliographies are searchable online on the NNW database file. This file can be accessed through the Integrated Technical Information System (ITIS) of the US Department of Energy (DOE).

  15. Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Russell, E.W.; Clarke, W. [Lawrence Livermore National Lab., CA (United States)] [Lawrence Livermore National Lab., CA (United States); Domian, H.A. [Babcock and Wilcox Co., Lynchburg, VA (United States)] [Babcock and Wilcox Co., Lynchburg, VA (United States); Madson, A.A. [Kaiser Engineers California Corp., Oakland, CA (United States)] [Kaiser Engineers California Corp., Oakland, CA (United States)

    1991-08-01T23:59:59.000Z

    This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B&S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs.

  16. Fermi Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHumanJuneDocumentingFermi Site Office CX Determinations

  17. Site characterization progress report: Yucca Mountain, Nevada, April 1, 1992--September 30, 1992, Number 7

    SciTech Connect (OSTI)

    NONE

    1992-12-01T23:59:59.000Z

    In accordance with section 113(b)(3) of the Nuclear Waste Policy Act of 1982, as amended (NWPA), the Department has prepared the seventh in a series of reports on the progress of site characterization at the Yucca Mountain candidate site. The Civilian Radioactive Waste Management Program made significant progress during the reporting period at the Yucca Mountain Site Characterization Project. Several important advances were made in the surface-based testing program including: initiation of borehole drilling utilizing the new, state-of-the-art LM-300 drill rig which employs dry drilling and coring techniques; neutron access borehole drilling to evaluate infiltration processes; excavations to aid geologic mapping; and trenching in Midway Valley to study Quaternary faulting. A Floodplain Assessment and Statement of Findings was published in the Federal Register which concluded there would be no significant impact nor cumulative impacts on floodplains resulting from Exploratory Studies Facility activities. The National Academy of Sciences` National Research Council released its report entitled ``Ground Water at Yucca Mountain: How High Can It Rise?`` which concluded that none of the evidence cited as proof of groundwater upwelling in and around Yucca Mountain could be reasonably attributed to that process and that significant water table excursions to the repository design level are not shown by the geologic record. The June 29, 1992, earthquake near Yucca Mountain provided scientists with a wealth of information relevant to understanding the neotectonics of the area and the geometry of faults at depth. Early findings suggest that accelerations recorded were well within proposed design limits for the surface waste handling facilities.

  18. Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    NONE

    1992-09-01T23:59:59.000Z

    The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

  19. Site characterization plan for groundwater in Waste Area Grouping 1 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Lee, R.R.; Curtis, A.H.; Houlberg, L.M.; Purucker, S.T.; Singer, M.L.; Tardiff, M.F.; Wolf, D.A.

    1994-07-01T23:59:59.000Z

    The Waste Area Grouping (WAG) 1 Groundwater Operable Unit (OU) at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is undergoing a site characterization to identify environmental contamination that may be present. This document, Site Characterization Report for Groundwater in Waste Area Grouping I at Oak Ridge National Laboratory, Oak Ridge, Tennessee, identifies areas of concern with respect to WAG 1 groundwater and presents the rationale, justification, and objectives for conducting this continuing site characterization. This report summarizes the operations that have taken place at each of the areas of concern in WAG 1, summarizes previous characterization studies that have been performed, presents interpretations of previously collected data and information, identifies contaminants of concern, and presents an action plan for further site investigations and early actions that will lead to identification of contaminant sources, their major groundwater pathways, and reduced off-site migration of contaminated groundwater to surface water. Site characterization Activities performed to date at WAG I have indicated that groundwater contamination, principally radiological contamination, is widespread. An extensive network of underground pipelines and utilities have contributed to the dispersal of contaminants to an unknown extent. The general absence of radiological contamination in surface water at the perimeter of WAG 1 is attributed to the presence of pipelines and underground waste storage tank sumps and dry wells distributed throughout WAG 1 which remove more than about 40 million gal of contaminated groundwater per year.

  20. Information needs for characterization of high-level waste repository sites in six geologic media. Volume 1. Main report

    SciTech Connect (OSTI)

    NONE

    1985-05-01T23:59:59.000Z

    Evaluation of the geologic isolation of radioactive materials from the biosphere requires an intimate knowledge of site geologic conditions, which is gained through precharacterization and site characterization studies. This report presents the results of an intensive literature review, analysis and compilation to delineate the information needs, applicable techniques and evaluation criteria for programs to adequately characterize a site in six geologic media. These media, in order of presentation, are: granite, shale, basalt, tuff, bedded salt and dome salt. Guidelines are presented to assess the efficacy (application, effectiveness, and resolution) of currently used exploratory and testing techniques for precharacterization or characterization of a site. These guidelines include the reliability, accuracy and resolution of techniques deemed acceptable, as well as cost estimates of various field and laboratory techniques used to obtain the necessary information. Guidelines presented do not assess the relative suitability of media. 351 refs., 10 figs., 31 tabs.

  1. Characterization of the National Petroleum Reserve No. 3 (NPR-3) Site for Naturally Occurring Radioactive Material(NORM)

    SciTech Connect (OSTI)

    White, G.J; Rood, A.S.

    1999-01-21T23:59:59.000Z

    The National Petroleum Reserve No. 3 site (NPR-3) near Casper, Wyoming is being prepared for transfer to private industry. Remediation of the NPR-3 site has already begun in anticipation of this transfer. This document describes the characterization of the NPR-3 site for Naturally Occurring Radioactive Materials (NORM). Data generated on radionuclide concentrations and radon emanation may be used to determine disposal options and the need for remediation at this site. A preliminary gamma survey of the NPR-3 site was conducted to identify areas of potential NORM contamination. Based on these gamma surveys, two general areas of NORM contamination were found: the North Water Flood area and the BTP-10 produced water discharge steam. A maximum surface exposure rate of 120 {micro}R h{sup -1} was observed in the North Water Flood area, with the highest readings found along the drainage channel from the area. Exposure rates dropped to background quickly with increasing distance from the center of the drainage. The maximum observed exposure rate in the BTP-10 produced water drainage was 40 {micro}R h{sup -1}. Soil and sediment sampling were concentrated in these two areas. All samples were analyzed for concentration of {sup 226}Ra, {sup 228}Ra, and {sup 40}K. Maximum {sup 226}Ra concentrations observed in the samples collected were 46 pCi g{sup -1} for soil and 78 pCi g{sup -1} for sediment. Concentrations in most samples were considerably lower than these values. Radon emanation fraction was also measured for a randomly selected fraction of the samples. The mean Rn emanation fraction measured was 0.10, indicating that on average only 10 percent of the Rn produced is released from the medium. Based on the results of these analyses, NORM contamination at the NPR-3 site is minimal, and appears to be restricted to the two general areas sampled. Concentrations of NORM radionuclides found soils and sediments in these two locations do not justify remedial actions at present. However, continued discharge of NORM-contaminated produced waters from the BTP-10 area will likely result in the continued accumulation of NORM in sediment. It is therefore recommended that the sediments in the BTP-10 discharge stream be monitored periodically for NORM.

  2. Geochemical Characterization of Chromate Contamination in the 100 Area Vadose Zone at the Hanford Site - Part 2

    SciTech Connect (OSTI)

    Qafoku, Nikolla; Dresel, P. Evan; McKinley, James P.; Ilton, Eugene S.; Um, Wooyong; Resch, Charles T.; Kukkadapu, Ravi K.; Petersen, Scott W.

    2011-01-04T23:59:59.000Z

    At the Hanford Site, chromate was used throughout the 100 Areas (100-B, 100-C, 100-D/DR, 100-F, 100-H, and 100 K) as a corrosion inhibitor in reactor cooling water. Chromate was delivered in rail cars, tanker trucks, barrels, and local pipelines as dichromate granular solid or stock solution. In many occasions, chromate was inevitably discharged to surface or near-surface ground through spills during handling, pipeline leaks, or during disposal to cribs. The composition of the liquids that were discharged is not known and it is quite possible that Cr(VI) fate and transport in the contaminated sediments would be a function of the chemical composition of the waste fluids. The major objectives of this investigation which was limited in scope by the financial resources available, were to 1) determine the leaching characteristics of hexavalent chromium [Cr(VI)] from contaminated sediments collected from 100-D Area spill sites; 2) elucidate possible Cr(VI) mineral and/or chemical associations that may be responsible for Cr(VI) retention in the Hanford Site 100 Areas through the use of macroscopic leaching studies, and microscale characterization of contaminated sediments; and 3) provide information to construct a conceptual model of Cr(VI) geochemistry in the Hanford 100 Area vadose zone that can be used for developing options for environmental remediation. The information gathered from this research effort will help to further improve our understanding of Cr(VI) behavior in the vadose zone and will also help in accelerating the 100 Area Columbia River Corridor cleanup by providing valuable information to develop remedial action based on a fundamental understanding of Cr(VI) vadose zone geochemistry. A series of column experiments were conducted with contaminated sediments to study Cr(VI) desorption patterns. Column experiments used the field size fraction of the sediment samples and a simulated Hanford Site groundwater solution. Periodic stop flow events were applied to evaluate the change in elemental concentration during time periods of no flow and greater fluid residence time. Sediments were characterized for the spatial and mineralogical associations of the contamination using some microscale techniques such as X-ray diffraction, scanning electron microscopy, energy dispersive spectroscopy, X-ray photoelectron spectroscopy, and Mössbauer spectroscopy.

  3. Characterization of Microbial Communities in Subsurface Nuclear Blast Cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Moser, Duane; Russell, Chuck; Marshall, Matthew; Czerwinski, Ken; Daly, Michael J; Zavarin, Mavrik

    2008-02-08T23:59:59.000Z

    This exploratory research project is designed to test fundamental hypotheses concerning the possible existence and nature of indigenous microbial populations in Nevada Test Site (NTS) subsurface nuclear blast cavities. Although subsurface microbiological studies have been performed at the NTS in the past, radioactive zones have yet to be addressed. Nuclear blast zone microbiology is a completely new field and our team is well-positioned to collect and analyze samples that have never before been available to microbiologists. Relevant samples are now being obtained by incorporating microbiological collections into an ongoing annual hot well sampling program being conducted by other agencies. A combination of cultivation-based and molecular microbial detection protocols is being utilized at multiple locations to survey for uncultivable microorganisms and to develop a culture collection which will be characterized for radionuclide- and metal-reduction capabilities. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, a positive outcome from this work would have significant implications for management strategies at this and other DOE sites. A primary objective of the project has been the establishment of the regulatory and technical framework necessary to enable our acquisition of samples. Thus, much of our activity in the first phase of this work has involved the development an approved Field Area Work Plan (FAWP), Radiological Work Permit (RWP), and other documentation required for radiological work at the NTS. We have also invested significant time into ensuring that all personnel possess the required training (e.g. Radworker II and 40 hr. HAZWOPER) for access to the hot well sampling sites. Laboratory facilities, required for field processing of radioactive samples as well as DNA extraction and other manipulations, have been secured both the NTS (Mercury, NV) and UNLV. Although our year-1 field work was delayed due to non-availability of samples, an aggressive sampling campaign is now underway and our first hot well samples were collected on Feb 5th, 2008. The unique nature of this site, coupled with the combined expertise of the collaborating laboratories (DRI, LLNL, PNNL, and the Harry Reid Center) makes the likelihood of our achieving discoveries of value to DOE, the individual researchers, and society high. As the selective pressures at atomic blast sites are probably different from those of production and disposal sites, these habitats may contain novel organisms of utility for bioremediation. Such organisms will have had to develop physiological mechanisms to survive high doses of ionizing radiation over the variety of rock types and hydrologic environments present at the NTS.

  4. Unsaturated fractured rock characterization methods and data sets at the Apache Leap Tuff Site

    SciTech Connect (OSTI)

    Rasmussen, T.C.; Evans, D.D.; Sheets, P.J.; Blanford, J.H. [Arizona Univ., Tucson, AZ (USA). Dept. of Hydrology and Water Resources

    1990-08-01T23:59:59.000Z

    Performance assessment of high-level nuclear waste containment feasibility requires representative values of parameters as input, including parameter moments, distributional characteristics, and covariance structures between parameters. To meet this need, characterization methods and data sets for interstitial, hydraulic, pneumatic and thermal parameters for a slightly welded fractured tuff at the Apache Leap Tuff Site situated in central Arizona are reported in this document. The data sets include the influence of matric suction on measured parameters. Spatial variability is investigated by sampling along nine boreholes at regular distances. Laboratory parameter estimates for 105 core segments are provided, as well as field estimates centered on the intervals where the core segments were collected. Measurement uncertainty is estimated by repetitively testing control samples. 31 refs., 10 figs., 21 tabs.

  5. Status of volcanism studies for the Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Crowe, B.; Perry, F.; Murrell, M.; Poths, J.; Valentine, G.A. [Los Alamos National Lab., NM (United States); Wells, S. [Univ. of California, Riverside, CA (United States); Bowker, L.; Finnegan, K. [Univ. of Nevada, Las Vegas, NV (United States); Geissman, J.; McFadden, L.

    1995-02-01T23:59:59.000Z

    Chapter 1 introduces the volcanism issue for the Yucca Mountain site and provides the reader with an overview of the organization, content, and significant conclusions of this report. The risk of future basaltic volcanism is the primary topic of concern including both events that intersect a potential repository and events that occur near or within the waste isolation system of a repository. Chapter 2 describes the volcanic history of the Yucca Mountain region (YMR) and emphasizes the Pliocene and Quaternary volcanic record, the interval of primary concern for volcanic risk assessment. The Lathrop Wells volcanic center is described in detail because it is the youngest basalt center in the YMR. Chapter 3 describes the tectonic setting of the YMR and presents and assesses the significance of multiple alternative tectonic models. Geophysical data are described for the YMR and are used as an aid to understand the distribution of basaltic volcanic centers. Chapter 4 discusses the petrologic and geochemical features of basaltic volcanism in the YMR, the southern Great Basin and the Basin and Range province. The long time of activity and characteristic small volume of the Postcaldera basalt of the YMR result in one of the lowest eruptive rates in a volcanic field in the southwest United States. Chapter 5 summarizes current concepts of the segregation, ascent, and eruption of basalt magma. Chapter 6 summarizes the history of volcanism studies (1979 through early 1994), including work for the Yucca Mountain Site Characterization Project and overview studies by the state of Nevada and the Nuclear Regulatory Commission. Chapter 7 summarizes probabilistic volcanic hazard assessment using a three-part conditional probability model. Chapter 8 describes remaining volcanism work judged to be needed to complete characterization studies for the YMR. Chapter 9 summarizes the conclusions of this volcanism status report.

  6. Detailed Geophysical Fault Characterization in Yucca Flat, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Theodore H. Asch; Donald Sweetkind; Bethany L. Burton; Erin L. Wallin

    2009-02-10T23:59:59.000Z

    Yucca Flat is a topographic and structural basin in the northeastern part of the Nevada Test Site (NTS) in Nye County, Nevada. Between the years 1951 and 1992, 659 underground nuclear tests took place in Yucca Flat; most were conducted in large, vertical excavations that penetrated alluvium and the underlying Cenozoic volcanic rocks. Radioactive and other potential chemical contaminants at the NTS are the subject of a long-term program of investigation and remediation by the U.S. Department of Energy (DOE), National Nuclear Security Administration, Nevada Site Office, under its Environmental Restoration Program. As part of the program, the DOE seeks to assess the extent of contamination and to evaluate the potential risks to humans and the environment from byproducts of weapons testing. To accomplish this objective, the DOE Environmental Restoration Program is constructing and calibrating a ground-water flow model to predict hydrologic flow in Yucca Flat as part of an effort to quantify the subsurface hydrology of the Nevada Test Site. A necessary part of calibrating and evaluating a model of the flow system is an understanding of the location and characteristics of faults that may influence ground-water flow. In addition, knowledge of fault-zone architecture and physical properties is a fundamental component of the containment of the contamination from underground nuclear tests, should such testing ever resume at the Nevada Test Site. The goal of the present investigation is to develop a detailed understanding of the geometry and physical properties of fault zones in Yucca Flat. This study was designed to investigate faults in greater detail and to characterize fault geometry, the presence of fault splays, and the fault-zone width. Integrated geological and geophysical studies have been designed and implemented to work toward this goal. This report describes the geophysical surveys conducted near two drill holes in Yucca Flat, the data analyses performed, and the integrated interpretations developed from the suite of geophysical methodologies utilized in this investigation. Data collection for this activity started in the spring of 2005 and continued into 2006. A suite of electrical geophysical surveys were run in combination with ground magnetic surveys; these surveys resulted in high-resolution subsurface data that portray subsurface fault geometry at the two sites and have identified structures not readily apparent from surface geologic mapping, potential field geophysical data, or surface effects fracture maps.

  7. The determination of the bioavailability and the site of absorption in lambs fed different sources of magnesium

    E-Print Network [OSTI]

    Hurley, Leigh Anne

    2012-06-07T23:59:59.000Z

    THE DETERMINATION OF THE BIOAVAILABILITY AND THE SITE OF ABSORPTION IN LAMBS FED DIFFERENT SOURCES OF MAGNESIUM A Thesis I, EIGH ANNE HURLEY Submitted to the Of f ice of Graduate Studies Texas AAM UniversitY in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE December 1988 Major Subject: Animal Science THE DETERMINATION OF THE BIOAVAILABILITY AND THE SITE OF ABSORPTION IN LAMBS FED DIFFERENT SOURCES OF MAGNESIUM A Thesis by LEIGH ANNE HURLEY Approved...

  8. Strategic Petroleum Reserve (SPR) additional geologic site characterization studies, Bayou Choctaw salt dome, Louisiana

    SciTech Connect (OSTI)

    Neal, J.T. [Sandia National Labs., Albuquerque, NM (United States); Magorian, T.R. [Magorian (Thomas R.), Amherst, NY (United States); Byrne, K.O.; Denzler, S. [Acres International Corp., Amherst, NY (United States)

    1993-09-01T23:59:59.000Z

    This report revises and updates the geologic site characterization report that was published in 1980. Revised structure maps and sections show interpretative differences in the dome shape and caprock structural contours, especially a major east-west trending shear zone, not mapped in the 1980 report. Excessive gas influx in Caverns 18 and 20 may be associated with this shear zone. Subsidence values at Bayou Choctaw are among the lowest in the SPR system, averaging only about 10 mm/yr but measurement and interpretation issues persist, as observed values often approximate measurement accuracy. Periodic, temporary flooding is a continuing concern because of the low site elevation (less than 10 ft), and this may intensify as future subsidence lowers the surface even further. Cavern 4 was re-sonared in 1992 and the profiles suggest that significant change has not occurred since 1980, thereby reducing the uncertainty of possible overburden collapse -- as occurred at Cavern 7 in 1954. Other potential integrity issues persist, such as the proximity of Cavern 20 to the dome edge, and the narrow web separating Caverns 15 and 17. Injection wells have been used for the disposal of brine but have been only marginally effective thus far; recompletions into more permeable lower Pleistocene gravels may be a practical way of increasing injection capacity and brinefield efficiency. Cavern storage space is limited on this already crowded dome, but 15 MMBBL could be gained by enlarging Cavern 19 and by constructing a new cavern beneath and slightly north of abandoned Cavern 13. Environmental issues center on the low site elevation: the backswamp environment combined with the potential for periodic flooding create conditions that will require continuing surveillance.

  9. Invitation to Present, Sponsor, and Attend Geologic Carbon Sequestration Site Integrity: Characterization and

    E-Print Network [OSTI]

    Daniels, Jeffrey J.

    Invitation to Present, Sponsor, and Attend Geologic Carbon Sequestration Site Integrity and long-term sustainability of geologic carbon sequestration sites depends upon the ability on geologic carbon sequestration site monitoring. The management framework and costs will be similar

  10. Characterize and explore potential sites and prepare research and development plan (site investigation study). Final draft. Task 2. Milestone report

    SciTech Connect (OSTI)

    None

    1980-12-01T23:59:59.000Z

    A specific research and development plan to investigate the behavior and suitability of aquifers as compressed air energy storage (CAES) sites is presented. The proposed effort will evaluate present uncertainties in the performance of the underground energy storage subsystem and its impact on above ground plant design and cost. The project is planned to provide the utility industry with a quantitative basis for confidence that financial commitment to a demonstration plant and subsequent expansion is justified and poses acceptable risks. Activities in Phase II of a 5-phase overall CAES development program are reported. Information is included on the development of field testing specifications and schedules; selection of specific site for the conceptual design; development plan and schedule for the media site; development of analytical models of aquifer airflow; and well drilling requirements. As a result of these studies 14 sites in Illinois and Indiana were evaluated, 7 were ranked for suitability for CAES, and 4 were selected for possible use in the field testing program. Test procedures, the mathematical models and drilling requirments were developed. (LCL)

  11. E-Print Network 3.0 - active site characterization Sample Search...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    transuranic (TRU) waste generator sites operating... sites (Condition 2) and ... Source: Yucca Mountain Project, US EPA Collection: Environmental Sciences and Ecology 3...

  12. Establishment of a facility for intrusive characterization of transuranic waste at the Nevada Test Site

    SciTech Connect (OSTI)

    Foster, B.D.; Musick, R.G.; Pedalino, J.P.; Cowley, J.L. [Bechtel Nevada Corp., Las Vegas, NV (United States); Karney, C.C. [Dept. of Energy, Las Vegas, NV (United States); Kremer, J.L.

    1998-01-01T23:59:59.000Z

    This paper describes design and construction, project management, and testing results associated with the Waste Examination Facility (WEF) recently constructed at the Nevada Test Site (NTS). The WEF and associated systems were designed, procured, and constructed on an extremely tight budget and within a fast track schedule. Part 1 of this paper focuses on design and construction activities, Part 2 discusses project management of WEF design and construction activities, and Part 3 describes the results of the transuranic (TRU) waste examination pilot project conducted at the WEF. In Part 1, the waste examination process is described within the context of Waste Isolation Pilot Plant (WIPP) characterization requirements. Design criteria are described from operational and radiological protection considerations. The WEF engineered systems are described. These systems include isolation barriers using a glove box and secondary containment structure, high efficiency particulate air (HEPA) filtration and ventilation systems, differential pressure monitoring systems, and fire protection systems. In Part 2, the project management techniques used for ensuring that stringent cost/schedule requirements were met are described. The critical attributes of these management systems are described with an emphasis on team work. In Part 3, the results of a pilot project directed at performing intrusive characterization (i.e., examination) of TRU waste at the WEF are described. Project activities included cold and hot operations. Cold operations included operator training, facility systems walk down, and operational procedures validation. Hot operations included working with plutonium contaminated TRU waste and consisted of waste container breaching, waste examination, waste segregation, data collection, and waste repackaging.

  13. Characterization of U.S. Wave Energy Converter (WEC) Test Sites: A Catalogue of Met-Ocean Data.

    SciTech Connect (OSTI)

    Dallman, Ann Renee; Neary, Vincent Sinclair

    2014-10-01T23:59:59.000Z

    This report presents met - ocean data and wave energy characteristics at three U.S. wave energy converter (WEC) test and potential deployment sites . Its purpose is to enable the compari son of wave resource characteristics among sites as well as the select io n of test sites that are most suitable for a developer's device and that best meet their testing needs and objectives . It also provides essential inputs for the design of WEC test devices and planning WEC tests, including the planning of deployment and op eration s and maintenance. For each site, this report catalogues wave statistics recommended in the (draft) International Electrotechnical Commission Technical Specification (IEC 62600 - 101 TS) on Wave Energy Characterization, as well as the frequency of oc currence of weather windows and extreme sea states, and statistics on wind and ocean currents. It also provides useful information on test site infrastructure and services .

  14. Light-Beam-Induced-Current Characterization of CdTe Solar Cells Russell M. Geisthardt and James R. Sites

    E-Print Network [OSTI]

    Sites, James R.

    Light-Beam-Induced-Current Characterization of CdTe Solar Cells Russell M. Geisthardt and James RTe solar cells. II. EXPERIMENTAL The LBIC system at CSU has been described in [1] and [2]. The light. Sites Colorado State University, Fort Collins, CO, 80523, USA Abstract--In this work, light

  15. CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL

    SciTech Connect (OSTI)

    Farfan, E.; Coleman, R.

    2011-03-31T23:59:59.000Z

    RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

  16. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

    SciTech Connect (OSTI)

    Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1995-05-01T23:59:59.000Z

    This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

  17. A strategy to seal exploratory boreholes in unsaturated tuff; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Fernandez, J.A. [Sandia National Labs., Albuquerque, NM (United States); Case, J.B.; Givens, C.A.; Carney, B.C. [IT Corp., Albuquerque, NM (United States)

    1994-04-01T23:59:59.000Z

    This report presents a strategy for sealing exploratory boreholes associated with the Yucca Mountain Site Characterization Project. Over 500 existing and proposed boreholes have been considered in the development of this strategy, ranging from shallow (penetrating into alluvium only) to deep (penetrating into the groundwater table). Among the comprehensive list of recommendations are the following: Those boreholes within the potential repository boundary and penetrating through the potential repository horizon are the most significant boreholes from a performance standpoint and should be sealed. Shallow boreholes are comparatively insignificant and require only nominal sealing. The primary areas in which to place seals are away from high-temperature zones at a distance from the potential repository horizon in the Paintbrush nonwelded tuff and the upper portion of the Topopah Spring Member and in the tuffaceous beds of the Calico Hills Unit. Seals should be placed prior to waste emplacement. Performance goals for borehole seals both above and below the potential repository are proposed. Detailed construction information on the boreholes that could be used for future design specifications is provided along with a description of the environmental setting, i.e., the geology, hydrology, and the in situ and thermal stress states. A borehole classification scheme based on the condition of the borehole wall in different tuffaceous units is also proposed. In addition, calculations are presented to assess the significance of the boreholes acting as preferential pathways for the release of radionuclides. Design calculations are presented to answer the concerns of when, where, and how to seal. As part of the strategy development, available technologies to seal exploratory boreholes (including casing removal, borehole wall reconditioning, and seal emplacement) are reviewed.

  18. Determination of the Distribution and Inventory of Radionuclides within a Savannah River Site Waterway - 13202

    SciTech Connect (OSTI)

    Hiergesell, R.A.; Phifer, M.A. [Savannah River National Laboratory, SRNS Bldg. 773-43A, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, SRNS Bldg. 773-43A, Aiken, SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    An investigation was conducted to evaluate the radionuclide inventory within the Lower Three Runs (LTR) Integrator Operable Unit (IOU) at the U.S. Department of Energy's (DOE's) Savannah River Site (SRS). The scope of this effort included the analysis of previously existing sampling and analysis data as well as additional stream bed and flood plain sampling and analysis data acquired to delineate horizontal and vertical distributions of the radionuclide as part of the ongoing SRS environmental restoration program, and specifically for the LTR IOU program. While cesium-137 (Cs-137) is the most significant and abundant radionuclide associated with the LTR IOU it is not the only radionuclide, hence the scope included evaluating all radionuclides present and includes an evaluation of inventory uncertainty for use in sensitivity and uncertainty analyses. The scope involved evaluation of the radionuclide inventory in the P-Reactor and R-Reactor cooling water effluent canal systems, PAR Pond (including Pond C) and the flood plain and stream sediment sections of LTR between the PAR Pond Dam and the Savannah River. The approach taken was to examine all of the available Sediment and Sediment/Soil analysis data available along the P- and R-Reactor cooling water re-circulation canal system, the ponds situated along those canal reaches and along the length of LTR below Par Pond dam. By breaking the IOU into a series of sub-components and sub-sections, the mass of contaminated material was estimated and a representative central concentration of each radionuclide was computed for each compartment. The radionuclide inventory associated with each sub-compartment was then aggregated to determine the total radionuclide inventory that represented the full LTR IOU. Of special interest was the inventory of Cs-137 due to its role in contributing to the potential dose to an offsite member of the public. The overall LTR IOU inventory of Cs-137 was determined to be 2.87 E+02 GBq, which is similar to two earlier estimates. This investigation provides an independent, ground-up estimate of Cs-137 inventory in LTR IOU utilizing the most recent field data. (authors)

  19. DETERMINATION OF THE DISTRIBUTION AND INVENTORY OF RADIONUCLIDES WITHIN A SAVANNAH RIVER SITE WATERWAY

    SciTech Connect (OSTI)

    Hiergesell, R.; Phifer, M.

    2012-11-09T23:59:59.000Z

    An investigation was conducted to evaluate the radionuclide inventory within the Lower Three Runs (LTR) Integrator Operable Unit (IOU) at the U.S. Department of Energy’s (DOE’s) Savannah River Site (SRS). The scope of this effort included the analysis of previously existing sampling and analysis data as well as additional streambed and floodplain sampling and analysis data acquired to delineate horizontal and vertical distributions of the radionuclide as part of the ongoing SRS environmental restoration program, and specifically for the LTR IOU program. While cesium-137 (Cs-137) is the most significant and abundant radionuclide associated with the LTR IOU it is not the only radionuclide, hence the scope included evaluating all radionuclides present and includes an evaluation of inventory uncertainty for use in sensitivity and uncertainty analyses. The scope involved evaluation of the radionuclide inventory in the P-Reactor and RReactor cooling water effluent canal systems, PAR Pond (including Pond C) and the floodplain and stream sediment sections of LTR between the PAR Pond Dam and the Savannah River. The approach taken was to examine all of the available Sediment and Sediment/Soil analysis data available along the P- and R-Reactor cooling water re-circulation canal system, the ponds situated along those canal reaches and along the length of LTR below Par Pond dam. By breaking the IOU into a series of sub-components and sub-sections, the mass of contaminated material was estimated and a representative central concentration of each radionuclide was computed for each compartment. The radionuclide inventory associated with each sub-compartment was then aggregated to determine the total radionuclide inventory that represented the full LTR IOU. Of special interest was the inventory of Cs-137 due to its role in contributing to the potential dose to an offsite member of the public. The overall LTR IOU inventory of Cs-137 was determined to be 75.5 Ci, which is similar to two earlier estimates. This investigation provides an independent, ground-up estimate of Cs-137 inventory in LTR IOU utilizing the most recent field data.

  20. SYSTHESIS OF VOLCANISM STUDIES FOR THE YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT

    SciTech Connect (OSTI)

    FV PERRY, GA CROWE, GA VALENTINE AND LM BOWKER

    1997-09-23T23:59:59.000Z

    This report synthesizes the results of volcanism studies conducted by scientists at the Los Alamos National Laboratory and collaborating institutions on behalf of the Department of Energy's Yucca Mountain Project. Chapter 1 introduces the volcanism issue for the Yucca Mountain site and provides the reader with an overview of the organization, content, and significant conclusions of this report. The hazard of future basaltic volcanism is the primary topic of concern including both events that intersect a potential repository and events that occur near or within the waste isolation system of a repository. Future volcanic events cannot be predicted with certainty but instead are estimated using formal methods of probabilistic volcanic hazard assessment (PVHA). Chapter 2 describes the volcanic history of the Yucca Mountain region (YMR) and emphasizes the Pliocene and Quaternary volcanic record, the interval of primary concern for volcanic risk assessment. The distribution, eruptive history, and geochronology of Plio-Quaternary basalt centers are described by individual center emphasizing the younger postcaldera basalt (<5 Ma). The Lathrop Wells volcanic center is described in detail because it is the youngest basalt center in the YMR. The age of the Lathrop Wells center is now confidently determined to be about 75 thousand years old. Chapter 3 describes the tectonic setting of the YMR and presents and assesses the significance of multiple alternative tectonic models. The distribution of Pliocene and Quaternary basaltic volcanic centers is evaluated with respect to tectonic models for detachment, caldera, regional and local rifting, and the Walker Lane structural zone. Geophysical data are described for the YMR and are used as an aid to understand the distribution of past basaltic volcanic centers and possible future magmatic processes. Chapter 4 discusses the petrologic and geochemical features of basaltic volcanism in the YMR, the southern Great Basin and the Basin and Range province. Geochemical and isotopic data are presented for post-Miocene basalts of the Yucca Mountain region. Alternative petrogenetic models are assessed for the formation of the Lathrop Wells volcanic center. Based on geochemical data, basaltic ash in fault trenches near Yucca Mountain is shown to have originated from the Lathrop Wells center. Chapter 5 synthesizes eruptive and subsurface effects of basaltic volcanism on a potential repository and summarizes current concepts of the segregation, ascent, and eruption of basalt magma. Chapter 6 synthesizes current knowledge of the probability of disruption of a potential repository at Yucca Mountain. In 1996, an Expert Elicitation panel was convened by DOE that independently conducted PVHA for the Yucca Mountain site. Chapter 6 does not attempt to revise this PVHA; instead, it further examines the sensitivity of variables in PVHA. The approaches and results of PVHA by the expert judgment panel are evaluated and incorporated throughout this chapter. The disruption ratio (E2) is completely re-evaluated using simulation modeling that describes volcanic events based on the geometry of basaltic feeder dikes. New estimates of probability bounds are developed. These comparisons show that it is physically implausible for the probability of magmatic disruption of the Yucca Mountain site to be greater than 10{sup -7} events per year. Bounding probability estimates are used to assess possible implications of not drilling aeromagnetic anomalies in the Arnargosa Valley and Crater Flat. The results of simulation modeling are used to assess the sensitivity of the disruption probability for the location of northeast boundaries of volcanic zones near the Yucca Mountain site. A new section on modeling of radiological releases associated with surface and subsurface magmatic activity has been added to chapter 6. The modeling results are consistent with past total system performance assessments that show future volcanic and magmatic events are not significant components of repository performance and volcanism is not a prio

  1. Site characterization progress report: Yucca Mountain, Nevada, October 1, 1994--March 31, 1995, Number 12. Nuclear Waste Policy Act (Section 113)

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    During the first half of fiscal year 1995, most activities at the Yucca Mountain Site Characterization Project were directed at implementing the Program Plan developed by the Office of Civilian Radioactive Waste Management. The Plan is designed to enable the Office to make measurable and significant progress toward key objectives over the next five years within the financial resources that can be realistically expected. Activities this period focused on the immediate goal of determining by 1998 whether Yucca Mountain, Nevada, is technically suitable as a possible site for a geologic repository for the permanent disposal of spent nuclear fuel and high-level radioactive waste. Work on the Project advanced in several critical areas, including programmatic activities such as issuing the Program Plan, completing the first technical basis report to support the assessment of three 10 CFR 960 guidelines, developing the Notice of Intent for the Environmental Impact Statement, submitting the License Application Annotated Outline, and beginning a rebaselining effort to conform with the goals of the Program Plan. Scientific investigation and analysis of the site and design and construction activities to support the evaluation of the technical suitability of the site also advanced. Specific details relating to all Project activities and reports generated are presented in this report.

  2. Adaption of the Magnetometer Towed Array geophysical system to meet Department of Energy needs for hazardous waste site characterization

    SciTech Connect (OSTI)

    Cochran, J.R. [Sandia National Labs., Albuquerque, NM (United States); McDonald, J.R. [Naval Research Lab., Washington, DC (United States); Russell, R.J. [Geo-Centers, Inc., Newton, MA (United States); Robertson, R. [Hughes Associates, Inc., Washington, DC (United States); Hensel, E. [New Mexico State Univ., Las Cruces, NM (United States). Dept. of Mechanical Engineering

    1995-10-01T23:59:59.000Z

    This report documents US Department of Energy (DOE)-funded activities that have adapted the US Navy`s Surface Towed Ordnance Locator System (STOLS) to meet DOE needs for a ``... better, faster, safer and cheaper ...`` system for characterizing inactive hazardous waste sites. These activities were undertaken by Sandia National Laboratories (Sandia), the Naval Research Laboratory, Geo-Centers Inc., New Mexico State University and others under the title of the Magnetometer Towed Array (MTA).

  3. Characterization of solids in residual wastes from single-shell tanks at the Hanford site, Washington, USA.

    SciTech Connect (OSTI)

    Krupka, K. M.; Cantrell, K. J.; Todd Schaef, H.; Arey, B. W.; Heald, S. M.; Deutsch, W. J.; Lindberg, M. J. (X-Ray Science Division); ( PSC-USR); (PNNL)

    2010-03-01T23:59:59.000Z

    Solid phase physical and chemical characterization methods have been used in an ongoing study of residual wastes from several single-shell underground waste tanks at the U.S. Department of Energy's Hanford Site in southeastern Washington State. Because these wastes are highly-radioactive dispersible powders and are chemically-complex assemblages of crystalline and amorphous solids that contain contaminants as discrete phases and/or co-precipitated within oxide phases, their detailed characterization offers an extraordinary technical challenge. X-ray diffraction (XRD) and scanning electron microscopy/energy dispersive x-ray spectroscopy (SEM/EDS) are the two principal methods used, along with a limited series of analyses by synchrotron-based methods, to characterize solid phases and their contaminant associations in these wastes.

  4. SEISMIC DETERMINATION OF RESERVOIR HETEROGENEITY; APPLICATION TO THE CHARACTERIZATION OF HEAVY OIL RESERVOIRS

    SciTech Connect (OSTI)

    Matthias G. Imhof; James W. Castle

    2003-11-01T23:59:59.000Z

    The objective of the project is to examine how seismic and geologic data can be used to improve characterization of small-scale heterogeneity and their parameterization in reservoir models. The study is performed at West Coalinga Field in California. We continued our investigation on the nature of seismic reactions from heterogeneous reservoirs. We began testing our algorithm to infer parameters of object-based reservoir models from seismic data. We began integration of seismic and geologic data to determine the deterministic limits of conventional seismic data interpretation. Lastly, we began integration of seismic and geologic heterogeneity using stochastic models conditioned both on wireline and seismic data.

  5. Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization

    SciTech Connect (OSTI)

    Harrison, W.; Fenster, D.F.; Ditmars, J.D.; Paddock, R.A.; Rote, D.M.; Hambley, D.F.; Seitz, M.G.; Hull, A.B.

    1986-12-01T23:59:59.000Z

    At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report.

  6. Central Heating Plant site characterization report, Marine Corps Combat Development Command, Quantico, Virginia

    SciTech Connect (OSTI)

    Not Available

    1990-08-01T23:59:59.000Z

    This report presents the methodology and results of a characterization of the operation and maintenance (O M) environment at the US Marine Corps (USMC) Quantico, Virginia, Central Heating Plant (CHP). This characterization is part of a program intended to provide the O M staff with a computerized artificial intelligence (AI) decision support system that will assist the plant staff in more efficient operation of their plant. 3 refs., 12 figs.

  7. Estimations of the extent of migration of surficially applied water for various surface conditions near the potential repository perimeter; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Sobolik, S.R.; Fewell, M.E.

    1993-12-01T23:59:59.000Z

    The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level nuclear waste repository. Site characterization includes surface-based and underground testing. Analyses have been performed to support the design of site characterization activities so to have minimal impact on the ability of the site to isolate waste, and on tests performed as part of the characterization process. Two examples of site characterization activities are the construction of an Exploratory Studies Facility, which may include underground shafts, drifts, and ramps, and surface-based testing activities, which may require borehole drilling, excavation of test pits, and road watering for dust control. The information in this report pertains to two-dimensional numerical calculations modeling the movement of surficially applied water and the potential effects of that water on repository performance and underground experiments. This document contains information that has been used in preparing recommendations for two Yucca Mountain Site Characterization Project documents: Appendix I of the Exploratory Studies Facility Design Requirements document, and the Surface-Based Testing Field Requirements Document.

  8. Determination of Na submonolayer adsorption site on Cu(111) by low-energy ion blocking

    SciTech Connect (OSTI)

    Zhang, R.; Makarenko, B. [Department of Chemistry, University of Houston, Houston, Texas 77204 (United States); Bahrim, B. [Department of Chemistry and Physics, Lamar University, Beaumont, Texas 77710 (United States); Rabalais, J. W. [Department of Chemistry, University of Houston, Houston, Texas 77204 (United States); Department of Chemistry and Physics, Lamar University, Beaumont, Texas 77710 (United States)

    2007-09-15T23:59:59.000Z

    The structure of a submonolayer coverage of sodium adsorbed on a Cu(111) surface at room temperature has been investigated using time-of-flight scattering and recoiling spectrometry. The effect of the adsorbed Na atoms on the angular distribution of scattered 2 keV H{sup +} ions is analyzed by molecular dynamics and scattering and recoiling imaging code simulations. It is shown that at a coverage {theta}=0.25 monolayer, Na atoms preferentially populate the fcc threefold surface sites with a height of 2.7{+-}0.1 A above the first-layer Cu atoms. At a lower coverage of {theta}=0.10 ML, there is no adsorption site preference for the Na atoms on the Cu(111) surface.

  9. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

    SciTech Connect (OSTI)

    Not Available

    1993-03-18T23:59:59.000Z

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

  10. The determination of settling velocities for sewage sludge disposed at 106-Mile Site

    E-Print Network [OSTI]

    Hernandez, Daniel Saul

    1991-01-01T23:59:59.000Z

    THE DBTERMZNATZON OF SETTLING VELOCZTZES FOR SEWAGE SLUDGE DZSPOSED AT 106-MILE SITE A Thesis by DANIEL SAUL HERNANDEZ Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of requirements for the degree... of MASTER OF SCIENCE December 1991 Major Subject: Civil Engineering THB DETERMZNATZON OF SBTTLZNG VELOCZTZES FOR SEWAGE SLUDGE DZSPOSBD AT 106-MZLE SZTB A Thesis by DANIEL SAUL HERNANDEZ Approved as to style and content by: James S. Bonner '(Chair...

  11. The Effects of Site Characterization Activities on the Abundance of Ravens (Corvus corax) in the Yucca Mountain Area

    SciTech Connect (OSTI)

    P.E. Lederle

    1998-05-08T23:59:59.000Z

    In response to the Nuclear Waste Policy Act of 1982 and the Nuclear Waste Policy Amendments Act of 1987, the U.S. Department of Energy (DOE) developed and is implementing the Yucca Mountain Site Characterization Project. Raven abundance was measured from August 1991 through August 1995 along treatment and control routes to evaluate whether site characterization activities resulted in increased raven abundance at Yucca Mountain. This study fulfills the requirement set forth in the incidental take provisions of the Biological Opinion that DOE monitor the abundance of ravens at Yucca Mountain. Ravens were more abundant at Yucca Mountain than in the control area, and raven abundance in both areas increased over time. However, the magnitude of differences between Yucca Mountain and control surveys did not change over time, indicating that the increase in raven abundance observed during this study was not related to site characterization activities. Increases over time on both Yucca Mountain and control routes are consistent with increases in raven abundance in the Mojave Desert reported by the annual Breeding Bird Survey of the US. Fish and Wildlife Service. Evidence from the Desert Tortoise Monitoring Program at Yucca Mountain suggests that ravens are not a significant predator of small tortoises in this locale. Carcasses of small tortoises (less than 110 mm in length) collected during the study showed little evidence of raven predation, and 59 radiomarked hatchlings that were monitored on a regular basis were not preyed upon by ravens. Overall, no direct evidence of raven predation on tortoises was observed during this study. Small tortoises are probably encountered so infrequently by ravens that they are rarely exploited as a food source. This is likely due to the relatively low abundance of both desert tortoises and ravens in the Yucca Mountain area.

  12. Oak Ridge K-25 Site Technology Logic Diagram. Volume 3, Technology evaluation data sheets; Part A, Characterization, decontamination, dismantlement

    SciTech Connect (OSTI)

    Fellows, R.L. [ed.

    1993-02-26T23:59:59.000Z

    The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration and waste management problems at the Oak Ridge K-25 Site to potential technologies that can remediate these problems. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remedial action, and decontamination and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This report is part A of Volume 3 concerning characterization, decontamination, and dismantlement.

  13. Site Characterization Plan for the Old Hydrofracture Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    The aboveground structures of the Old Hydrofracture Facility (OHF) at Oak Ridge National Laboratory (ORNL) are scheduled for decontamination and decommissioning (D&D). This Site Characterization Plan presents the strategy and techniques to be used to characterize the OHF D&D structures in support of D&D planning, design, and implementation. OHF is located approximately 1 mile southwest of the main ORNL complex. From 1964 to 1979, OHF was used in the development and full-scale application of hydrofracture operations in which 969,000 gal of liquid low-level waste (LLLW) was mixed with grout and then injected under high pressure into a low-permeability shale formation approximately 1/6 mile underground.

  14. Test Area for Remedial Actions (TARA) site characterization and dynamic compaction of low-level radioactive waste trenches

    SciTech Connect (OSTI)

    Davis, E.C.; Spalding, B.P.; Lee, S.Y.; Hyder, L.K.

    1989-01-01T23:59:59.000Z

    As part of a low-level radioactive waste burial ground stabilization and closure technology demonstration project, a group of five burial trenches in Oak Ridge National Laboratory (ORNL) Solid Waste Storage Area (SWSA) 6 was selected as a demonstration site for testing trench compaction, trench grouting, and trench cap installation and performance. This report focuses on site characterization, trench compaction, and grout-trench leachate compatibility. Trench grouting and cap design and construction will be the subject of future reports. The five trenches, known as the Test Area for Remedial Actions (TARA) site, are contained within a hydrologically isolated area of SWSA 6; for that reason, any effects of stabilization activities on site performance and groundwater quality will be separable from the influence of other waste disposal units in SWSA 6. To obviate the chronic problem of burial trench subsidence and to provide support for an infiltration barrier cap, these five trenches were dynamically compacted by repeated dropping of a 4-ton weight onto each trench from heights of approximately 7 m.

  15. Diversity and characterization of sulfate-reducing bacteria in groundwater at a uranium mill tailings site

    E-Print Network [OSTI]

    Yun-juan Chang; Aaron D. Peacock; Philip E. Long; John R. Stephen; James P. Mckinley; Sarah J. Macnaughton; A. K. M. Anwar Hussain; Arnold M. Saxton; David C. White

    2001-01-01T23:59:59.000Z

    plays a role in both natural attenuation and accelerated bioremediation of uranium-contaminated sites. To realize bioremediation potential and accurately predict natural attenuation, it is important to first understand the microbial diversity of such sites. In this paper, the distribution of sulfate-reducing bacteria (SRB) in contaminated groundwater associated with a uranium mill tailings disposal site at Shiprock, N.Mex., was investigated. Two culture-independent analyses were employed: sequencing of clone libraries of PCR-amplified dissimilatory sulfite reductase (DSR) gene fragments and phospholipid fatty acid (PLFA) biomarker analysis. A remarkable diversity among the DSR sequences was revealed, including sequences from ?-Proteobacteria, gram-positive organisms, and the Nitrospira division. PLFA analysis detected at least 52 different mid-chain-branched saturate PLFA and included a high proportion of 10me16:0. Desulfotomaculum and Desulfotomaculum-like sequences were the most dominant DSR genes detected. Those belonging to SRB within ?-Proteobacteria were mainly recovered from low-uranium (1,500 ppb) sites. Logistic regression showed a significant influence of uranium concentration over the dominance of this cluster of sequences (P ? 0.0001). This strong association indicates that Desulfotomaculum has remarkable

  16. Ames Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHuman ResourcesScienceHomeAboutLightAllen J.Ames Site

  17. Argonne Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHumanJune 2008 Basic Energy Sciences (BES)Argonne Site

  18. Berkeley Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHumanJune 2008 Basic EnergyB. GrantBarryBerkeley Site

  19. Brookhaven Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHumanJune 2008 Basic EnergyB.Bette Korber,Brookhaven Site

  20. Princeton Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 IndustrialIsadore Perlman, 1960 TheOrganization ArgonnePaulEnergyPrinceton Site

  1. SLAC Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,# ,SchoolsNEUTRINOSISSLAC Site Office

  2. SLAC Site Office CX Determinations | U.S. DOE Office of Science (SC)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,# ,SchoolsNEUTRINOSISSLAC Site

  3. Hanford Site National Environmental Policy Act (NEPA) Characterization Report, Revision 17

    SciTech Connect (OSTI)

    Neitzel, Duane A.; Bunn, Amoret L.; Cannon, Sandra D.; Duncan, Joanne P.; Fowler, Richard A.; Fritz, Brad G.; Harvey, David W.; Hendrickson, Paul L.; Hoitink, Dana J.; Horton, Duane G.; Last, George V.; Poston, Ted M.; Prendergast-Kennedy, Ellen L.; Reidel, Steve P.; Rohay, Alan C.; Sackschewsky, Michael R.; Scott, Michael J.; Thorne, Paul D.

    2005-09-30T23:59:59.000Z

    This document describes the U.S. Department of Energy’s (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many environmental documents being prepared by DOE contractors concerning the National Environmental Policy Act (NEPA). No statements about significance or environmental consequences are provided. This year’s report is the seventeenth revision of the original document published in 1988 and is (until replaced by the eighteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (EISs) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology; air quality; geology; hydrology; ecology; cultural, archaeological, and historical resources; socioeconomics; noise; and occupational health and safety. Sources for extensive tabular data related to these topics are provided in the chapter. Most subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information, where available, of the 100, 200, 300, and other areas. This division allows the reader to go directly to those sections of particular interest. When specific information on each of these separate areas is not complete or available, the general Hanford Site description should be used. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities. Information in Chapter 6 of this document can be adapted and supplemented with specific information for a chapter covering statutory and regulatory requirements in an environmental assessment or environmental impact statement. When preparing environmental assessments and EISs, authors should also be cognizant of the document titled Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements published by the DOE Office of NEPA Oversight (DOE 2004). Additional guidance on preparing DOE NEPA documents can be found at http://tis.eh.doe.gov/nepa/guidance.html. Any interested individual seeking baseline data on the Hanford Site and its past activities may also use the information contained in this document to evaluate projected activities and their impacts. For this 2005 revision, the following sections of the document were reviewed by the authors and updated with the best available information through May 2005: Climate and Meteorology Air Quality Geology – Seismicity section only Hydrology – Flow charts for the Columbia and Yakima rivers only Ecology – Threatened and Endangered Species subsection only Socioeconomics Occupational Safety All of Chapter 6.

  4. Diversity and characterization of sulfate-reducing bacteria in groundwater at a uranium mill tailings site

    SciTech Connect (OSTI)

    Chang, Yun-Juan (Unknown); Peacock, A D. (Tennessee, Univ Of); Long, Philip E. (BATTELLE (PACIFIC NW LAB)); Stephen, John R. (Unknown); McKinley, James P. (BATTELLE (PACIFIC NW LAB)); Mcnaughton, Sarah J. (Unknown); Hussain, A K M A.; Saxton, A M.; White, D C. (Unknown)

    2000-12-01T23:59:59.000Z

    Microbially mediated reduction and immobilization of U(VI) to U(TV) plays a role in both natural attenuation and accelerated bioremediation of uranium contaminated sites. To realize bioremediation potential and accurately predict natural attenuation, it is important to first understand the microbial diversity of such sites. In this paper, the distribution of sulfate-reducing bacteria (SRB) in contaminated groundwater associated with a uranium mill tailings disposal site at Shiprock, N.Mex,, was investigated. Two culture-independent analyses were employed: sequencing of clone libraries of PCR-amplified dissimilatory sulfite reductase (DSR) gene fragments and phospholipid fatty acid (PLFA) biomarker analysis. A remarkable diversity among the DSR sequences was revealed, including sequences from F-Proteobacteria, gram-positive organisms, and the Nitrospira division. PLFA analysis detected at least,52 different mid-chain-branched saturate PLFA and included a high proportion of 10me16:0, Desulfotomaculum and Desulfotomaculum-like sequences were the most dominant DSR genes detected. Those belonging to SRB within F-Proteobacteria were mainly recovered from low-uranium (less than or equal to 302 ppb) samples. One Desulfotomaculum like sequence cluster overwhelmingly dominated high-U (> 1,500 ppb) sites. Logistic regression showed a significant influence of uranium concentration over the dominance of this cluster of sequences (P= 0.0001), This strong association indicates that Desulfotomaculum has remarkable tolerance and adaptation to high levels of uranium and suggests the organism's possible involvement in natural attenuation of uranium. The in situ activity level of Desulfotomaculum in uranium-contaminated environments and its comparison to the activities of other SRB and other functional groups should be an important area for future research.

  5. Characterization of microbial communities in subsurface nuclear blast cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Duane P. Moser; Ken Czerwinski; Charles E. Russell; Mavrik Zavarin

    2010-07-13T23:59:59.000Z

    This US Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this programâ??s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

  6. Characterization of Microbial Communities in Subsurface Nuclear Blast Cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Duane P. Moser, Jim Bruckner, Jen Fisher, Ken Czerwinski, Charles E. Russell, and Mavrik Zavarin

    2010-09-01T23:59:59.000Z

    This U.S. Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this program’s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

  7. GEOPHYSICS AND SITE CHARACTERIZATION AT THE HANFORD SITE THE SUCCESSFUL USE OF ELECTRICAL RESISTIVITY TO POSITION BOREHOLES TO DEFINE DEEP VADOSE ZONE CONTAMINATION - 11509

    SciTech Connect (OSTI)

    GANDER MJ; LEARY KD; LEVITT MT; MILLER CW

    2011-01-14T23:59:59.000Z

    Historic boreholes confirmed the presence of nitrate and radionuclide contaminants at various intervals throughout a more than 60 m (200 ft) thick vadose zone, and a 2010 electrical resistivity survey mapped the known contamination and indicated areas of similar contaminants, both laterally and at depth; therefore, electrical resistivity mapping can be used to more accurately locate characterization boreholes. At the Hanford Nuclear Reservation in eastern Washington, production of uranium and plutonium resulted in the planned release of large quantities of contaminated wastewater to unlined excavations (cribs). From 1952 until 1960, the 216-U-8 Crib received approximately 379,000,000 L (100,000,000 gal) of wastewater containing 25,500 kg (56,218 lb) uranium; 1,029,000 kg (1,013 tons) of nitrate; 2.7 Ci of technetium-99; and other fission products including strontium-90 and cesium-137. The 216-U-8 Crib reportedly holds the largest inventory of waste uranium of any crib on the Hanford Site. Electrical resistivity is a geophysical technique capable of identifying contrasting physical properties; specifically, electrically conductive material, relative to resistive native soil, can be mapped in the subsurface. At the 216-U-8 Crib, high nitrate concentrations (from the release of nitric acid [HNO{sub 3}] and associated uranium and other fission products) were detected in 1994 and 2004 boreholes at various depths, such as at the base of the Crib at 9 m (30 ft) below ground surface (bgs) and sporadically to depths in excess of 60 m (200 ft) bgs. These contaminant concentrations were directly correlative with the presence of observed low electrical resistivity responses delineated during the summer 2010 geophysical survey. Based on this correlation and the recently completed mapping of the electrically conductive material, additional boreholes are planned for early 2011 to identify nitrate and radionuclide contamination: (a) throughout the entire vertical length of the vadose zone (i.e., 79 m [260 ft] bgs) within the footprint of the Crib, and (b) 15 to 30 m (50 to 100 ft) east of the Crib footprint, where contaminants are inferred to have migrated through relatively permeable soils. Confirmation of the presence of contamination in historic boreholes correlates well with mapping from the 2010 survey, and serves as a basis to site future characterization boreholes that will likely intersect contamination both laterally and at depth.

  8. A New Seismic Data System for Determining Nuclear Test Yields At the Nevada Test Site

    SciTech Connect (OSTI)

    LEE, JONATHAN W.

    2001-11-01T23:59:59.000Z

    An important capability in conducting underground nuclear tests is to be able to determine the nuclear test yield accurately within hours after a test. Due to a nuclear test moratorium, the seismic method that has been used in the past has not been exercised since a non-proliferation high explosive test in 1993. Since that time, the seismic recording system and the computing environment have been replaced with modern equipment. This report describes the actions that have been taken to preserve the capability for determining seismic yield, in the event that nuclear testing should resume. Specifically, this report describes actions taken to preserve seismic data, actions taken to modernize software, and actions taken to document procedures. It concludes with a summary of the current state of the data system and makes recommendations for maintaining this system in the future.

  9. Hanford Site Assessment & Characterization/Verification of Structures & Conex Boxes Procedure

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2M HILL Secretary MonizSite Public Tours Hanford

  10. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-03-18T23:59:59.000Z

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz.

  11. Siting of low-level radioactive waste disposal facilities in Texas

    E-Print Network [OSTI]

    Isenhower, Daniel Bruce

    1982-01-01T23:59:59.000Z

    University property was evaluated for suitability for disposal of low-level radioactive waste. This site was evaluated to demonstrate, briefly, the site characterization process and to determine the ability of the statewide study to accurately predict... these boreholes. Literature review was an additional method employed to characterize the site. The results of this site characterization reveal that a more extensive investigation would be necessary to completely evaluate the site and that the state- wide...

  12. Determination of aerosol size distributions at uranium mill tailings remedial action project sites

    SciTech Connect (OSTI)

    Newton, G.J.; Reif, R.H. [CWM Federal Environmental Services, Inc., Albuquerque, NM (United States); Hoover, M.D.

    1994-11-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has an ongoing program, the Uranium Mill Tailings Remedial Action (UMTRA) Project, to stabilize piles of uranium mill tailings in order to reduce the potential radiological hazards to the public. Protection of workers and the general public against airborne radioactivity during remedial action is a top priority at the UMTRA Project. The primary occupational radionuclides of concern are {sup 230}Th, {sup 226}Ra, {sup 210}Pb, {sup 210}Po, and the short-lived decay products of {sup 222}Rn with {sup 230}Th causing the majority of the committed effective dose equivalent (CEDE) from inhaling uranium mill tailings. Prior to this study, a default particle size of 1.0 {mu}m activity median aerodynamic diameter (AMAD) was assumed for airborne radioactive tailings dust. Because of recent changes in DOE requirements, all DOE operations are now required to use the CEDE methodology, instead of the annual effective dose equivalent (AEDE) methodology, to evaluate internal radiation exposures. Under the transition from AEDE to CEDE, with a 1.0 {mu}m AMAD particle size, lower bioassay action levels would be required for the UMTRA Project. This translates into an expanded internal dosimetry program where significantly more bioassay monitoring would be required at the UMTRA Project sites. However, for situations where the particle size distribution is known to differ significantly from 1.0 {mu}m AMAD, the DOE allows for corrections to be made to both the estimated dose to workers and the derived air concentration (DAC) values. For particle sizes larger than 1.0 {mu}m AMAD, the calculated CEDE from inhaling tailings would be relatively lower.

  13. Mineralogical characterization of arsenic in gold mine tailings from three sites in Nova Scotia

    SciTech Connect (OSTI)

    M Corriveau; H Jamieson; M Parsons; G Hall

    2011-12-31T23:59:59.000Z

    Chronic exposure to high concentrations of arsenic (As) in windblown and vehicle-raised dust from tailings sites in Nova Scotia poses a potential health risk to recreational users of these areas and to nearby residents. The exposure may involve inhalation of dust, as well as oral ingestion of particles. It is important to understand the mineralogy and morphology of As-bearing dust particles in order to evaluate the risk posed by near-surface particulates in As-bearing tailings fields, as this will influence the stability and toxicity of As in the wastes. Optical mineralogy, scanning electron microscopy, electron microprobe, X-ray diffraction, synchrotron-based micro-X-ray diffraction ({mu}XRD) and micro-X-ray absorption near edge structure ({mu}XANES), and sequential leach extractions were applied to tailings samples from three sites in eastern Nova Scotia. Arsenic occurs naturally in these gold deposits mainly in arsenopyrite (FeAsS). In the near-surface material of the tailings fields, sulphide minerals have almost completely oxidized to secondary minerals such as scorodite (FeAsO{sub 4}{center_dot}2H{sub 2}O) and Ca-Fe arsenates. Iron oxyhydroxides contain variable amounts of As{sub 2}O{sub 5} from trace to 30 wt.% and CaO up to 8 wt.%. The presence of multiple As-hosting solid phases, including relatively soluble Ca-Fe arsenates and Fe oxyhydroxides with adsorbed As has important implications for human health risk assessment and remediation design.

  14. Field Investigation to Determine the Extent of Sediment Recontamination at the United Heckathorn Superfund Site, Richmond, California

    SciTech Connect (OSTI)

    Kohn, Nancy P.; Gilmore, Tyler J.

    2001-11-16T23:59:59.000Z

    This field investigation was undertaken to determine the present condition of sediment in Lauritzen Channel and Parr Canal approximately 2 years after completion of sediment remedial actions at the United Heckathorn Superfund site. The study was designed to supplement the post-remediation monitoring program by determining the extent and identifying potential sources of observed pesticide contamination in marine sediments near the site. Core samples collected from Lauritzen Channel and Parr Canal in July 1999 were described geologically, and samples were prepared from different sediment types, such as younger bay mud or older bay mud. Sediment samples were analyzed for grain size, organic carbon, and DDT compounds. Only minor changes have occurred in Parr Canal since remedial actions were taken in 1996-1997, but in Lauritzen Channel, DDT concentrations exceed the remedial goal of 590 ug/kg dry weight in nearly all the unconsolidated sediment (younger bay mud, sand, and disturbed older bay mud). The source of contaminated sediment could not be confirmed by this study; there was no clear correlation between high DDT concentrations and sediment remaining between the pilings, as was originally suspected. There also was no correlation between high DDT concentrations in sediment and the locations of outfalls, although some of the contamination retained by the creosote-treated wood appeared to be highest close to the known outfalls.

  15. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.3.5 through 8.3.5.20

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 68 figs., 102 tabs.

  16. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.4 through 8.7; Glossary and Acronyms

    SciTech Connect (OSTI)

    NONE

    1988-12-01T23:59:59.000Z

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Section 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 88 figs., 42 tabs.

  17. Analytical electron microscopy characterization of uranium-contaminated soils from the Fernald Site, FY1993 report

    SciTech Connect (OSTI)

    Buck, E.C.; Cunnane, J.C.; Brown, N.R.; Dietz, N.L.

    1994-10-01T23:59:59.000Z

    A combination of optical microscopy, scanning electron microscopy with backscattered electron detection (SEM/BSE), and analytical electron microscopy (AEM) is being used to determine the nature of uranium in soils from the Fernald Environmental Management Project. The information gained from these studies is being used to develop and test remediation technologies. Investigations using SEM have shown that uranium is contained within particles that are typically 1 to 100 {mu}m in diameter. Further analysis with AEM has shown that these uranium-rich regions are made up of discrete uranium-bearing phases. The distribution of these uranium phases was found to be inhomogeneous at the microscopic level.

  18. Transportation cask decontamination and maintenance at the potential Yucca Mountain repository; Yucca Mountain Site characterization project

    SciTech Connect (OSTI)

    Hartman, D.J.; Miller, D.D. [Bechtel National, Inc., San Francisco, CA (United States); Hill, R.R. [Sandia National Labs., Albuquerque, NM (United States)

    1992-04-01T23:59:59.000Z

    This study investigates spent fuel cask handling experience at existing nuclear facilities to determine appropriate cask decontamination and maintenance operations at the potential Yucca Mountain repository. These operations are categorized as either routine or nonroutine. Routine cask decontamination and maintenance tasks are performed in the cask preparation area at the repository. Casks are taken offline to a separate cask maintenance area for major nonroutine tasks. The study develops conceptual designs of the cask preparation area and cask maintenance area. The functions, layouts, and major features of these areas are also described.

  19. Study of soils buried under embankments to determine the potential of burial as a preservation technique for archaeological sites

    E-Print Network [OSTI]

    Gonzalez, Tania

    2012-06-07T23:59:59.000Z

    . . Thermodynamics Approach . . . . . 1 0 10 , . . . . . 1 3 . . 1 4 Ferrolysis and Other Reactions in Periodically-Saturated Soils. . . . . . . . . . . . . , . 1 7 . . . 21 Literature Review. Navajo Site Cunningham Site. Riverside Site. . Levee Site.... . . . 68 Discussion on Site Variability. Physical and Morphological Changes. Horizon Thickness. . . . . . 70 . . . . . 7 1 . . . . 7 2 Color . . . . 7 6 Texture. . . . . . 7 7 Structure. . Mottling. Calcium Carbonate Concretions. . . . . 78...

  20. Depleted uranium risk assessment for Jefferson Proving Ground using data from environmental monitoring and site characterization. Final report

    SciTech Connect (OSTI)

    Ebinger, M.H.; Hansen, W.R.

    1996-10-01T23:59:59.000Z

    This report documents the third risk assessment completed for the depleted uranium (DU) munitions testing range at Jefferson Proving Ground (JPG), Indiana, for the U.S. Army Test and Evaluation command. Jefferson Proving Ground was closed in 1995 under the Base Realignment and Closure Act and the testing mission was moved to Yuma Proving Ground. As part of the closure of JPG, assessments of potential adverse health effects to humans and the ecosystem were conducted. This report integrates recent information obtained from site characterization surveys at JPG with environmental monitoring data collected from 1983 through 1994 during DU testing. Three exposure scenarios were evaluated for potential adverse effects to human health: an occasional use scenario and two farming scenarios. Human exposure was minimal from occasional use, but significant risk were predicted from the farming scenarios when contaminated groundwater was used by site occupants. The human health risk assessments do not consider the significant risk posed by accidents with unexploded ordnance. Exposures of white-tailed deer to DU were also estimated in this study, and exposure rates result in no significant increase in either toxicological or radiological risks. The results of this study indicate that remediation of the DU impact area would not substantially reduce already low risks to humans and the ecosystem, and that managed access to JPG is a reasonable model for future land use options.

  1. Determining Long-Term Performance of Cool Storage Systems from Short-Term Tests; Literature Review and Site Selection, Nov. 1997 (Revised Feb. 1998)

    E-Print Network [OSTI]

    Haberl, J. S.; Claridge, D. E.; Reddy, T. A.; Elleson, J.

    1997-01-01T23:59:59.000Z

    This is the preliminary report contains the literature review and site selection recommendations for ASHRAE Research Project RP 1004 — "Determining Long-term Performance of Cool Storage Systems From Short-term Tests"....

  2. Strategic Petroleum Reserve (SPR) additional geologic site characterization studies, Bryan Mound Salt Dome, Texas

    SciTech Connect (OSTI)

    Neal, J.T. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Magorian, T.R.; Ahmad, S. [Acres International Corp., Amherst, NY (United States)] [Acres International Corp., Amherst, NY (United States)

    1994-11-01T23:59:59.000Z

    This report revises the original report that was published in 1980. Some of the topics covered in the earlier report were provisional and it is now practicable to reexamine them using new or revised geotechnical data and that obtained from SPR cavern operations, which involves 16 new caverns. Revised structure maps and sections show interpretative differences as compared with the 1980 report and more definition in the dome shape and caprock structural contours, especially a major southeast-northwest trending anomalous zone. The original interpretation was of westward tilt of the dome, this revision shows a tilt to the southeast, consistent with other gravity and seismic data. This interpretation refines the evaluation of additional cavern space, by adding more salt buffer and allowing several more caverns. Additional storage space is constrained on this nearly full dome because of low-lying peripheral wetlands, but 60 MMBBL or more of additional volume could be gained in six or more new caverns. Subsidence values at Bryan Mound are among the lowest in the SPR system, averaging about 11 mm/yr (0.4 in/yr), but measurement and interpretation issues persist, as observed values are about the same as survey measurement accuracy. Periodic flooding is a continuing threat because of the coastal proximity and because peripheral portions of the site are at elevations less than 15 ft. This threat may increase slightly as future subsidence lowers the surface, but the amount is apt to be small. Caprock integrity may be affected by structural features, especially the faulting associated with anomalous zones. Injection wells have not been used extensively at Bryan Mound, but could be a practicable solution to future brine disposal needs. Environmental issues center on the areas of low elevation that are below 15 feet above mean sea level: the coastal proximity and lowland environment combined with the potential for flooding create conditions that require continuing surveillance.

  3. MRS system study for the repository: Yucca Mountain Site Characterization Project; Volume 2

    SciTech Connect (OSTI)

    Sinagra, T.A. [Bechtel National, Inc., San Francisco, CA (USA); Harig, R. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA)

    1990-12-01T23:59:59.000Z

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ``MRS``) on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. This document contains A-D.

  4. Initial characterization of mudstone nanoporosity with small angle neutron scattering using caprocks from carbon sequestration sites.

    SciTech Connect (OSTI)

    McCray, John (Colorado School of Mines); Navarre-Sitchler, Alexis (Colorado School of Mines); Mouzakis, Katherine (Colorado School of Mines); Heath, Jason E.; Dewers, Thomas A.; Rother, Gernot (Oak Ridge National Laboratory)

    2010-11-01T23:59:59.000Z

    Geological carbon sequestration relies on the principle that CO{sub 2} injected deep into the subsurface is unable to leak to the atmosphere. Structural trapping by a relatively impermeable caprock (often mudstone such as a shale) is the main trapping mechanism that is currently relied on for the first hundreds of years. Many of the pores of the caprock are of micrometer to nanometer scale. However, the distribution, geometry and volume of porosity at these scales are poorly characterized. Differences in pore shape and size can cause variation in capillary properties and fluid transport resulting in fluid pathways with different capillary entry pressures in the same sample. Prediction of pore network properties for distinct geologic environments would result in significant advancement in our ability to model subsurface fluid flow. Specifically, prediction of fluid flow through caprocks of geologic CO{sub 2} sequestration reservoirs is a critical step in evaluating the risk of leakage to overlying aquifers. The micro- and nanoporosity was analyzed in four mudstones using small angle neutron scattering (SANS). These mudstones are caprocks of formations that are currently under study or being used for carbon sequestration projects and include the Marine Tuscaloosa Group, the Lower Tuscaloosa Group, the upper and lower shale members of the Kirtland Formation, and the Pennsylvanian Gothic shale. Total organic carbon varies from <0.3% to 4% by weight. Expandable clay contents range from 10% to {approx}40% in the Gothic shale and Kirtland Formation, respectively. Neutrons effectively scatter from interfaces between materials with differing scattering length density (i.e. minerals and pores). The intensity of scattered neutrons, I(Q), where Q is the scattering vector, gives information about the volume of pores and their arrangement in the sample. The slope of the scattering data when plotted as log I(Q) vs. log Q provides information about the fractality or geometry of the pore network. Results from this study, combined with high-resolution TEM imaging, provide insight into the differences in volume and geometry of porosity between these various mudstones.

  5. Site Characterization Report ORGDP Diffusion Facilities Permanent Shutdown K-700 Power House and K-27 Switch Yard/Switch House

    SciTech Connect (OSTI)

    Thomas R.J., Blanchard R.D.

    1988-06-13T23:59:59.000Z

    The K-700 Power House area, initially built to supply power to the K-25 gaseous diffusion plant was shutdown and disassembled in the 1960s. This shutdown was initiated by TVA supplying economical power to the diffusion plant complex. As a result of world wide over production of enriched, reactor grade U{sup 235}, the K-27 switch yard and switch house area was placed in standby in 1985. Subsequently, as the future production requirements decreased, the cost of production increased and the separation technologies for other processes improved, the facility was permanently shutdown in December, 1987. This Site Characterization Report is a part of the FY-88 engineering Feasibility Study for placing ORGDP Gaseous Diffusion Process facilities in 'Permanent Shutdown'. It is sponsored by the Department of Energy through Virgil Lowery of Headquarters--Enrichment and through Don Cox of ORO--Enrichment Operations. The primary purpose of these building or site characterization reports is to document, quantify, and map the following potential problems: Asbestos; PCB containing fluids; Oils, coolants, and chemicals; and External contamination. With the documented quantification of the concerns (problems) the Engineering Feasibility Study will then proceed with examining the potential solutions. For this study, permanent shutdown is defined as the securing and/or conditioning of each facility to provide 20 years of safe service with minimal expenditures and, where feasible, also serving DOE's needs for long-term warehousing or other such low-risk use. The K-700 power house series of buildings were either masonry construction or a mix of masonry and wood. The power generating equipment was removed and sold as salvage in the mid 1960s but the buildings and auxiliary equipment were left intact. The nine ancillary buildings in the power house area use early in the Manhattan Project for special research projects, were left intact minus the original special equipment. During the late 1960s and 1970s, some of the abandoned buildings were used for offices, special projects, and storage. Some of the remaining electrical transformers contain PCBs in concentrations less than 500 ppm. Many of the steam and hot water pipes in the buildings are insulated with asbestos insulation, but none of the equipment or buildings have high counts of surface radioactive contamination. The general conditions of the buildings are from fair to poor. Many should be boarded-up to prevent personnel entry and in some cases demolitions would be the safer alternative.

  6. Characterization of the geochemical and physical properties of wetland soils on the Savannah River Site: Field sampling activities. Final report

    SciTech Connect (OSTI)

    Dixon, K.L. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1992-11-01T23:59:59.000Z

    There are 36,000 acres of wetlands on the Savannah River Site (SRS) and an additional 5,000 acres of floodplain. Recent studies of wetland soils near various waste sites at SRS have shown that some wetlands have been contaminated with pollutants resulting from SRS operations. In general, releases of contaminants to wetland areas have been indirect. These releases may have originated at disposal lagoons or waste facilities located in the vicinity of the wetland areas. Transport mechanisms such as surface runoff, soil erosion, sediment transport, and groundwater seepage into downgradient wetland areas are responsible for the indirect discharges to the wetland areas. The SRS determined that a database of background geochemical and physical properties for wetland soils on the SRS was needed to facilitate future remedial investigations, human health and ecological risk assessments, treatability studies, and feasibility studies for the wetland areas. These data are needed for comparison to contaminant data collected from wetland soils that have been affected by contamination from SRS operations. This report describes the efforts associated with the collection of soil cores, preparation of a lithologic log for each core, and the processing and packaging of individual soil samples for shipment to analytical laboratory facilities.

  7. An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm

    SciTech Connect (OSTI)

    Badden, Janet W. [Washington River Protection Solutions, LLC, Richland, WA (United States); Connelly, Michael P. [Washington River Protection Solutions, LLC, Richland, WA (United States); Seeley, Paul N. [Cenibark International, Inc., Kennewick (United States); Hendrickson, Michelle L. [Washington State Univ., Richland (United States). Dept. of Ecology

    2013-01-10T23:59:59.000Z

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left "as is" and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines.

  8. Identification of structures, systems, and components important to safety at the potential repository at Yucca Mountain; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Hartman, D.J.; Miller, D.D. [Bechtel National, Inc., San Francisco, CA (United States); Klamerus, L.J. [Sandia National Labs., Albuquerque, NM (United States)

    1991-10-01T23:59:59.000Z

    This study recommends which structures, systems, and components of the potential repository at Yucca Mountain are important to safety. The assessment was completed in April 1990 and uses the reference repository configuration in the Site Characterization Plan Conceptual Design Report and follows the methodology required at that time by DOE Procedure AP6.10-Q. Failures of repository items during the preclosure period are evaluated to determine the potential offsite radiation doses and associated probabilities. Items are important to safety if, in the event they fail to perform their intended function, an accident could result which causes a dose commitment greater than 0.5 rem to the whole body or any organ of an individual in an unrestricted area. This study recommends that these repository items include the structures that house spent fuel and high-level waste, the associated filtered ventilation exhaust systems, certain waste- handling equipment, the waste containers, the waste treatment building structure, the underground waste transporters, and other items listed in this report. This work was completed April 1990. 27 refs., 7 figs., 9 tabs.

  9. Use of integrated geologic and geophysical information for characterizing the structure of fracture systems at the US/BK Site, Grimsel Laboratory, Switzerland

    SciTech Connect (OSTI)

    Martel, S.J.; Peterson, J.E. Jr. (Lawrence Berkeley Lab., CA (USA))

    1990-05-01T23:59:59.000Z

    Fracture systems form the primary fluid flow paths in a number of rock types, including some of those being considered for high level nuclear waste repositories. In some cases, flow along fractures must be modeled explicitly as part of a site characterization effort. Fractures commonly are concentrated in fracture zones, and even where fractures are seemingly ubiquitous, the hydrology of a site can be dominated by a few discrete fracture zones. We have implemented a site characterization methodology that combines information gained from geophysical and geologic investigations. The general philosophy is to identify and locate the major fracture zones, and then to characterize their systematics. Characterizing the systematics means establishing the essential and recurring patterns in which fractures are organized within the zones. We make a concerted effort to use information on the systematics of the fracture systems to link the site-specific geologic, borehole and geophysical information. This report illustrates how geologic and geophysical information on geologic heterogeneities can be integrated to guide the development of hydrologic models. The report focuses on fractures, a particularly common type of geologic heterogeneity. However, many aspects of the methodology we present can be applied to other geologic heterogeneities as well. 57 refs., 40 figs., 1 tab.

  10. Subsurface Site Characterization

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C.Green River, Utah,Tuba City,'1Dear Mr.Subsurface

  11. Sampling and analysis plan for the site characterization of the waste area Grouping 1 groundwater operable unit at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    NONE

    1994-11-01T23:59:59.000Z

    Waste Area Grouping (WAG) 1 at Oak Ridge National Laboratory (ORNL) includes all of the former ORNL radioisotope research, production, and maintenance facilities; former waste management areas; and some former administrative buildings. Site operations have contaminated groundwater, principally with radiological contamination. An extensive network of underground pipelines and utilities have contributed to the dispersal of contaminants to a known extent. In addition, karst geology, numerous spills, and pipeline leaks, together with the long and varied history of activities at specific facilities at ORNL, complicate contaminant migration-pathway analysis and source identification. To evaluate the extent of contamination, site characterization activity will include semiannual and annual groundwater sampling, as well as monthly water level measurements (both manual and continuous) at WAG 1. This sampling and analysis plan provides the methods and procedures to conduct site characterization for the Phase 1 Remedial Investigation of the WAG 1 Groundwater Operable Unit.

  12. Determination of Depleted Uranium in Environmental Bio-monitor Samples and Soil from Target sites in Western Balkan Region

    SciTech Connect (OSTI)

    Sahoo, Sarata K.; Enomoto, Hiroko; Tokonami, Shinji; Ishikawa, Tetsuo [National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage-ku, Chiba 263-8555 (Japan); Ujic, Predrag; Celikovic, Igor; Zunic, Zora S. [Institute of Nuclear Sciences, Vinca, Mike Petrovica Alasa 12-14, 11000 Belgrade (Serbia)

    2008-08-07T23:59:59.000Z

    Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper, we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses, lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP-MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2-755.43 Bq/Kg. We have determined {sup 235}U/{sup 238}U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.002097-0.002380. TIMS measurement confirms presence of DU in some samples. However, we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

  13. CX-004121: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Building 840 Asbestos Characterization and Abatement CX(s) Applied: B1.16 Date: 08022010 Location(s): New Mexico Office(s): Sandia Site...

  14. AVTA Federal Fleet PEV Readiness Data Logging and Characterization Study for the National Park Service: Fort Vancouver National Historic Site

    SciTech Connect (OSTI)

    Stephen Schey; Jim Francfort

    2014-03-01T23:59:59.000Z

    Battelle Energy Alliance, LLC, managing and operating contractor for the U.S. Department of Energy’s Idaho National Laboratory, is the lead laboratory for the U.S. Department of Energy’s Advanced Vehicle Testing. Battelle Energy Alliance, LLC contracted with Intertek Testing Services, North America (ITSNA) to collect data on federal fleet operations as part of the Advanced Vehicle Testing Activity’s Federal Fleet Vehicle Data Logging and Characterization study. The Advanced Vehicle Testing Activity study seeks to collect data to validate the use of advanced electric drive vehicle transportation. This report focuses on the Fort Vancouver National Historic Site (FVNHS) fleet to identify daily operational characteristics of select vehicles and report findings on vehicle and mission characterizations to support the successful introduction of electric vehicles (EVs) into the agencies’ fleet. Individual observations of the selected vehicles provided the basis for recommendations related to EV adoption and whether a battery electric vehicle (BEV) or plug-in hybrid electric vehicle (PHEV) (collectively plug-in electric vehicles) could fulfill the mission requirements. FVNHS identified three vehicles in its fleet for consideration. While the FVNHS vehicles conduct many different missions, only two (i.e., support and pool missions) were selected by agency management to be part of this fleet evaluation. The logged vehicles included a pickup truck and a minivan. This report will show that BEVs and PHEVs are capable of performing the required missions and providing an alternative vehicle for both mission categories, because each has sufficient range for individual trips and time available each day for charging to accommodate multiple trips per day. These charging events could occur at the vehicle’s home base, high-use work areas, or in intermediate areas along routes that the vehicles frequently travel. Replacement of vehicles in the current fleet would result in significant reductions in emission of greenhouse gases and petroleum use, while also reducing fuel costs. The Vancouver, Washington area and neighboring Portland, Oregon are leaders in adoption of PEVs in the United States1. PEV charging stations, or more appropriately identified as electric vehicle supply equipment, located on the FVNHS facility would be a benefit for both FVNHS fleets and general public use. Fleet drivers and park visitors operating privately owned plug-in electric vehicles benefit by using the charging infrastructure. ITSNA recommends location analysis of the FVNHS site to identify the optimal station placement for electric vehicle supply equipment. ITSNA recognizes the support of Idaho National Laboratory and ICF International for their efforts to initiate communication with the National Parks Service and FVNHS for participation in this study. ITSNA is pleased to provide this report and is encouraged by the high interest and support from the National Park Service and FVNHS personnel

  15. CENSUS AND STATISTICAL CHARACTERIZATION OF SOIL AND WATER QUALITY AT ABANDONED AND OTHER CENTRALIZED AND COMMERCIAL DRILLING-FLUID DISPOSAL SITES IN LOUISIANA, NEW MEXICO, OKLAHOMA, AND TEXAS

    SciTech Connect (OSTI)

    Alan R. Dutton; H. Seay Nance

    2003-06-01T23:59:59.000Z

    Commercial and centralized drilling-fluid disposal (CCDD) sites receive a portion of spent drilling fluids for disposal from oil and gas exploration and production (E&P) operations. Many older and some abandoned sites may have operated under less stringent regulations than are currently enforced. This study provides a census, compilation, and summary of information on active, inactive, and abandoned CCDD sites in Louisiana, New Mexico, Oklahoma, and Texas, intended as a basis for supporting State-funded assessment and remediation of abandoned sites. Closure of abandoned CCDD sites is within the jurisdiction of State regulatory agencies. Sources of data used in this study on abandoned CCDD sites mainly are permit files at State regulatory agencies. Active and inactive sites were included because data on abandoned sites are sparse. Onsite reserve pits at individual wells for disposal of spent drilling fluid are not part of this study. Of 287 CCDD sites in the four States for which we compiled data, 34 had been abandoned whereas 54 were active and 199 were inactive as of January 2002. Most were disposal-pit facilities; five percent were land treatment facilities. A typical disposal-pit facility has fewer than 3 disposal pits or cells, which have a median size of approximately 2 acres each. Data from well-documented sites may be used to predict some conditions at abandoned sites; older abandoned sites might have outlier concentrations for some metal and organic constituents. Groundwater at a significant number of sites had an average chloride concentration that exceeded nonactionable secondary drinking water standard of 250 mg/L, or a total dissolved solids content of >10,000 mg/L, the limiting definition for underground sources of drinking water source, or both. Background data were lacking, however, so we did not determine whether these concentrations in groundwater reflected site operations. Site remediation has not been found necessary to date for most abandoned CCDD sites; site assessments and remedial feasibility studies are ongoing in each State. Remediation alternatives addressed physical hazards and potential for groundwater transport of dissolved salt and petroleum hydrocarbons that might be leached from wastes. Remediation options included excavation of wastes and contaminated adjacent soils followed by removal to permitted disposal facilities or land farming if sufficient on-site area were available.

  16. Probing Defect Sites on TiO_2 with H_3 Re_3 (CO)_12 : Spectroscopic Characterization of the Surface Species

    SciTech Connect (OSTI)

    Suriye,K.; Lobo-Lapidus, R.; Yeagle, G.; Praserthdam, P.; Britt, R.; Gates, B.

    2008-01-01T23:59:59.000Z

    Samples of the anatase phase of titania were treated under vacuum to create Ti3+ surface-defect sites and surface O- and O2- species (indicated by electron paramagnetic resonance (EPR) spectra), accompanied by the disappearance of bridging surface OH groups and the formation of terminal Ti3+OH groups (indicated by IR spectra). EPR spectra showed that the probe molecule [Re3(CO)12H3] reacted preferentially with the Ti3+ sites, forming Ti4+ sites with OH groups as the [Re3(CO)12H3] was adsorbed. Extended X-ray absorption fine structure (EXAFS) spectra showed that these clusters were deprotonated upon adsorption, with the triangular metal frame remaining intact; EPR spectra demonstrated the simultaneous removal of surface O- and O2- species. The data determined by the three complementary techniques form the basis of a schematic representation of the surface chemistry. According to this picture, during evacuation at 773 K, defect sites are formed on hydroxylated titania as a bridging OH group is removed, forming two neighboring Ti3+ sites, or, when a Ti4+O bond is cleaved, forming a Ti3+ site and an O- species, with the Ti4+OH group being converted into a Ti3+OH group. When the probe molecule [Re3(CO)12H3] is adsorbed on a titania surface with Ti3+ defect sites, it reacts preferentially with these sites, becoming deprotonated, removing most of the oxygen radicals, and healing the defect sites.

  17. Preliminary geohydrologic site characterization and proposed water quality well locations for WAG 4, WAG 5, WAG 3, and SWSA 1

    SciTech Connect (OSTI)

    Baughn, D.C. [MCI/Consulting Engineers, Inc., Knoxville, TN (United States)

    1987-03-01T23:59:59.000Z

    The purpose of this report is to assess general site conditions and to recommend water quality well locations at Waste Area Groupings (WAGs) 4, 5 and 3 and Solid Waste Storage Area 1 (SWSA 1) within the Oak Ridge National Laboratory (ORNL) complex. The subject sites are identified on the general site location map. For reference, the relationship of the subject sites to other WAGs are shown. WAGs are regions prescribed by Martin Marietta throughout the ORNL complex that require environmental assessment which will include design and installation of ground water monitoring systems. WAGs contain solid waste management units such as SWSAs, as well as pipelines, spill sites, buildings, ponds and experimental test sites. These solid waste management units are considered to be potential sources of contamination requiring further evaluation. This report recommends locations for water quality wells which will be installed at WAG boundaries in order to gather water quality data.

  18. Summary and evaluation of existing geological and geophysical data near prospective surface facilities in Midway Valley, Yucca Mountain Project, Nye County, Nevada; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Gibson, J.D. [Sandia National Labs., Albuquerque, NM (United States); Swan, F.H.; Wesling, J.R.; Bullard, T.F.; Perman, R.C.; Angell, M.M.; DiSilvestro, L.A. [Geomatrix Consultants, Inc., San Francisco, CA (United States)

    1992-01-01T23:59:59.000Z

    Midway Valley, located at the eastern base of the Yucca Mountain in southwestern Nevada, is the preferred location of the surface facilities for the potential high-level nuclear waste repository at Yucca Mountain. One goal in siting these surface facilities is to avoid faults that could produce relative displacements in excess of 5 cm in the foundations of the waste-handling buildings. This study reviews existing geologic and geophysical data that can be used to assess the potential for surface fault rupture within Midway Valley. Dominant tectonic features in Midway Valley are north-trending, westward-dipping normal faults along the margins of the valley: the Bow Ridge fault to the west and the Paintbrush Canyon fault to the east. Published estimates of average Quaternary slip rates for these faults are very low but the age of most recent displacement and the amount of displacement per event are largely unknown. Surface mapping and interpretive cross sections, based on limited drillhole and geophysical data, suggest that additional normal faults, including the postulated Midway Valley fault, may exist beneath the Quaternary/Tertiary fill within the valley. Existing data, however, are inadequate to determine the location, recency, and geometry of this faulting. To confidently assess the potential for significant Quaternary faulting in Midway Valley, additional data are needed that define the stratigraphy and structure of the strata beneath the valley, characterize the Quaternary soils and surfaces, and establish the age of faulting. The use of new and improved geophysical techniques, combined with a drilling program, offers the greatest potential for resolving subsurface structure in the valley. Mapping of surficial geologic units and logging of soil pits and trenches within these units must be completed, using accepted state-of-the-art practices supported by multiple quantitative numerical and relative age-dating techniques.

  19. Overburden characterization and post-burn study of the Hanna IV, underground coal gasification site, Wyoming, and comparison to other Wyoming UCG sites

    SciTech Connect (OSTI)

    Marcouiller, B.A.; Burns, L.K.; Ethridge, F.G.

    1984-11-01T23:59:59.000Z

    Analysis of 21 post-burn cores taken from the Hanna IV UCG site allows 96 m (315 ft) of overburden to be subdivided into four local stratigraphic units. The 7.6 m (25 ft) thick Hanna No. 1 coal seam is overlain by a laterally discontinuous, 3.3 m (11 ft) thick shaley mudstone (Unit A') in part of the Hanna IV site. A more widespread, 30 m (90 ft) thick well-indurated sandstone (Unit A) overlies the A' unit. Unit A is the roof rock for both of the Hanna IV cavities. Overlying Unit A is a 33 m (108 ft) thick sequence of mudstone and claystone (Unit B), and the uppermost unit at the Hanna IV site (Unit C) is a coarse-grained sandstone that ranges in thickness from 40 to 67 m (131 to 220 ft). Two elliptical cavities were formed during the two phases of the Hanna IV experiment. The larger cavity, Hanna IVa, is 45 x 15 m in plan and has a maximum height of 18 m (59 ft) from the base of the coal seam to the top of the cavity; the Hanna IVb cavity is 40 x 15 m in plan and has a maximum height of 11 m (36 ft) from the base of the coal seam to the top of the cavity. Geotechnical tests indicated that the Hanna IV overburden rocks were moderately strong to strong, based on the empirical classification of Broch and Franklin (1972), and a positive, linear correlation exists between rock strength and volume percent calcite cement. There is an inverse linear correlation between rock strength and porosity for the Hanna IV overburden rocks. 28 refs., 34 figs., 13 tabs..

  20. SEISMIC DETERMINATION OF RESERVOIR HETEROGENEITY: APPLICATION TO THE CHARACTERIZATION OF HEAVY OIL RESERVOIRS

    SciTech Connect (OSTI)

    Matthias G. Imhof; James W. Castle

    2005-02-01T23:59:59.000Z

    The objective of the project was to examine how seismic and geologic data can be used to improve characterization of small-scale heterogeneity and their parameterization in reservoir models. The study focused on West Coalinga Field in California. The project initially attempted to build reservoir models based on different geologic and geophysical data independently using different tools, then to compare the results, and ultimately to integrate them all. We learned, however, that this strategy was impractical. The different data and tools need to be integrated from the beginning because they are all interrelated. This report describes a new approach to geostatistical modeling and presents an integration of geology and geophysics to explain the formation of the complex Coalinga reservoir.

  1. Method for determining formation quality factor from well log data and its application to seismic reservoir characterization

    DOE Patents [OSTI]

    Walls, Joel; Taner, M. Turhan; Dvorkin, Jack

    2006-08-08T23:59:59.000Z

    A method for seismic characterization of subsurface Earth formations includes determining at least one of compressional velocity and shear velocity, and determining reservoir parameters of subsurface Earth formations, at least including density, from data obtained from a wellbore penetrating the formations. A quality factor for the subsurface formations is calculated from the velocity, the density and the water saturation. A synthetic seismogram is calculated from the calculated quality factor and from the velocity and density. The synthetic seismogram is compared to a seismic survey made in the vicinity of the wellbore. At least one parameter is adjusted. The synthetic seismogram is recalculated using the adjusted parameter, and the adjusting, recalculating and comparing are repeated until a difference between the synthetic seismogram and the seismic survey falls below a selected threshold.

  2. Treatability Test Report: Characterization of Vadose Zone Carbon Tetrachloride Source Strength Using Tomographic Methods at the 216-Z-9 Site

    SciTech Connect (OSTI)

    Truex, Michael J.; Carroll, Kenneth C.; Rohay, Virginia J.; Mackley, Rob D.; Parker, Kyle R.

    2012-09-28T23:59:59.000Z

    A treatability test was conducted in 2011 at the 216-Z-9 Trench to evaluate methods for collecting characterization information that supports refined assessment of SVE performance goals based on impact to groundwater. The characterization information can also provide input to operational strategies for continued SVE operation and decisions regarding closure of the SVE system or transition to other remedies, if necessary.

  3. Determination of NAPL-Water Interfacial Areas in Well-Characterized Porous

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed Newcatalyst phasesData FilesShape, Density,TiO2(110). | EMSLDetermination of

  4. Biochemical Characterization and Structure Determination of a Prolyl 4-Hydroxylase-like Protein from Bacillus anthracis

    E-Print Network [OSTI]

    Culpepper, Megen

    2009-06-05T23:59:59.000Z

    Assay 64 3.2.5.2 UV-Vis Spectroscopy Coupled Assay 65 3.2.5.3 O 2 Electrode Assay 66 3.2.6 Anaerobic UV-vis Spectroscopy Monitoring Anthrax-P4H Cofactor Binding 67 3.2.7 UV-vis Spectroscopic Titration of Anthrax-P4H with !KG 68 3.2.8 Determination.../Fe(II)-Oxygenases 83 3.3.7 O 2 Electrode Assay for Anthrax-P4H Activity 85 3.3.8 pH-Dependency of Uncoupled Reaction Catalyzed by Anthrax-P4H 88 3.3.9 Anaerobic UV-Vis Spectroscopy Monitoring Anthrax-P4H Binding 89 3.3.10 Recombinant Bacillus (Collagen...

  5. SURFACE GEOPHYSICAL EXPLORATION OF SX TANK FARM AT THE HANFORD SITE RESULTS OF BACKGROUND CHARACTERIZATION WITH MAGNETICS AND ELECTROMAGNETICS

    SciTech Connect (OSTI)

    MYERS DA; RUCKER D; LEVIT M; CUBBAGE B; HENDERSON C

    2009-09-24T23:59:59.000Z

    This report presents the results of the background characterization of the cribs and trenches surrounding the SX tank farm prepared by HydroGEOPHYSICS Inc, Columbia Energy & Environmental Services Inc and Washington River Protection Solutions.

  6. Analysis of the Texas A&M impact lightning detector to determine detection efficiency and site error corrections

    E-Print Network [OSTI]

    Leahy, Frank Byron

    1999-01-01T23:59:59.000Z

    for the area 1000 km within the IMPACT detector location. A site error correction curve was used to correct for azimuthal errors in bearings to CG stroke locations. Errors were reduced to less than 4° in most cases. The IMPACT detector uses a crossed...

  7. Geochemical Characterization Using Geophysical Data and Markov Chain Monte Carolo methods: A Case Study at the South Oyster Bacterial Transport Site in Virginia

    SciTech Connect (OSTI)

    Chen, Jinsong; Hubbard, Susan; Rubin, Yoram; Murray, Chris; Roden, Eric; Majer, Ernest

    2003-11-18T23:59:59.000Z

    The spatial distribution of field-scale geochemical parameters, such as extractable Fe(II) and Fe(III), influences microbial processes and thus the efficacy of bioremediation. Because traditional characterization of those parameters is invasive and laborious, it is rarely performed sufficiently at the field-scale. Since both geochemical and geophysical parameters often correlate to some common physical properties (such as lithofacies), we investigated the utility of tomographic radar attenuation data for improving estimation of geochemical parameters using a Markov Chain Monte Carlo (MCMC) approach. The data used in this study included physical, geophysical, and geochemical measurements collected in and between several boreholes at the DOE South Oyster Bacterial Transport Site in Virginia. Results show that geophysical data, constrained by physical data, provided field-scale information about extractable Fe(II) and Fe(III) in a minimally invasive manner and with a resolution unparalleled by other geochemical characterization methods. This study presents our estimation framework for estimating Fe(II) and Fe(III), and its application to a specific site. Our hypothesis--that geochemical parameters and geophysical attributes can be linked through their mutual dependence on physical properties--should be applicable for estimating other geochemical parameters at other sites.

  8. Determination of the number of catalytic sites for ethylene-octene copolymers made with heterogeneous catalyst via interpretation of ?p13?sC NMR sequence distribution

    E-Print Network [OSTI]

    Moldovan, Daniel Gene

    1990-01-01T23:59:59.000Z

    DETERMINATION OF THE NUMBER OF CATALYTIC SITES FOR ETHYLENE-OCTENE COPOLYMERS MADE WITH HETEROGENEOUS CATALYST VIA INTERPRETATION OF C NMR SEQUENCE DISTRIBUTION A Thesis by DANIEL GENE MOLDOVAN Submitted to the Office of Graduate Studies... VIA INTERPRETATION OF C NMR SEQUENCE DISTRIBUTION A Thesis by DANIEL GENE MOLDOVAN Approved as to style and content by: C. A. J. oeve (Chair of t e committee) E. A. Meyers (Member) E. T. Ad m" (Member) J. S. Ham (Member) M. B. Hall (Head...

  9. Environmental assessment: Deaf Smith County site, Texas

    SciTech Connect (OSTI)

    Not Available

    1986-05-01T23:59:59.000Z

    In February 1983, the US Department of Energy (DOE) identified a location in Deaf Smith County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Deaf Smith County site and the eight other potentially sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. The Deaf Smith County site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. On the basis of the evaluations reported in this EA, the DOE has found that the Deaf Smith County site is not disqualified under the guidelines. On the basis of these findings, the DOE is nominating the Deaf Smith County site as one of the five sites suitable for characterization. 591 refs., 147 figs., 173 tabs.

  10. Spent nuclear fuel characterization for a bounding reference assembly for the receiving basin for off-site fuel

    SciTech Connect (OSTI)

    Kahook, S.D.; Garrett, R.L.; Canas, L.R.; Beckum, M.J. [Westinghouse Savannah River, Aiken, SC (United States)

    1995-07-01T23:59:59.000Z

    The Basis for Interim Operation (BIO) for the Receiving Basin for Off-Site Fuel (RBOF) facility at the Department of Energy (DOE) Savannah River Site (SRS) nuclear materials production complex, developed in accordance with draft DOE-STD-0019-93, required a hazard categorization for the safety analysis section as outlined in DOE-STD-1027-92. The RBOF facility was thus established as a Category-2 facility (having potential for significant on-site consequences from a radiological release) as defined in DOE 5480.23. Given the wide diversity of spent nuclear fuel stored in the RBOF facility, which made a detailed assessment of the total nuclear inventory virtually impossible, the categorization required a conservative calculation based on the concept of a hypothetical, bounding reference fuel assembly integrated over the total capacity of the facility. This scheme not only was simple but also precluded a potential delay in the completion of the BIO.

  11. Test Area for Remedial Actions (TARA) site characterization and dynamic compaction of low-level radioactive waste trenches. FY 1988 progress report

    SciTech Connect (OSTI)

    Davis, E.C.; Spalding, B.P.; Lee, S.Y.; Hyder, L.K.

    1989-01-01T23:59:59.000Z

    As part of a low-level radioactive waste burial ground stabilization and closure technology demonstration project, a group of five burial trenches in Oak Ridge National Laboratory (ORNL) Solid Waste Storage Area (SWSA) 6 was selected as a demonstration site for testing trench compaction, trench grouting, and trench cap installation and performance. This report focuses on site characterization, trench compaction, and grout-trench leachate compatibility. Trench grouting and cap design and construction will be the subject of future reports. The five trenches, known as the Test Area for Remedial Actions (TARA) site, are contained within a hydrologically isolated area of SWSA 6; for that reason, any effects of stabilization activities on site performance and groundwater quality will be separable from the influence of other waste disposal units in SWSA 6. To obviate the chronic problem of burial trench subsidence and to provide support for an infiltration barrier cap, these five trenches were dynamically compacted by repeated dropping of a 4-ton weight onto each trench from heights of approximately 7 m.

  12. Identification and Characterization of Hydrogeologic Units at the Nevada Test Site Using Geophysical Logs: Examples from the Underground Test Area Project

    SciTech Connect (OSTI)

    Lance Prothro, Sigmund Drellack, Margaret Townsend

    2009-03-25T23:59:59.000Z

    The diverse and complex geology of the Nevada Test Site region makes for a challenging environment for identifying and characterizing hydrogeologic units penetrated by wells drilled for the U.S. Department of Energy, National Nuclear Security Administration, Underground Test Area (UGTA) Environmental Restoration Sub-Project. Fortunately, UGTA geoscientists have access to large and robust sets of subsurface geologic data, as well as a large historical knowledge base of subsurface geological analyses acquired mainly during the underground nuclear weapons testing program. Of particular importance to the accurate identification and characterization of hydrogeologic units in UGTA boreholes are the data and interpretation principles associated with geophysical well logs. Although most UGTA participants and stakeholders are probably familiar with drill hole data such as drill core and cuttings, they may be less familiar with the use of geophysical logs; this document is meant to serve as a primer on the use of geophysical logs in the UGTA project. Standard geophysical logging tools used in the UGTA project to identify and characterize hydrogeologic units are described, and basic interpretation principles and techniques are explained. Numerous examples of geophysical log data from a variety of hydrogeologic units encountered in UGTA wells are presented to highlight the use and value of geophysical logs in the accurate hydrogeologic characterization of UGTA wells.

  13. U2504 Determines the Species Specificity of the A-site Cleft Antibiotics: The sStructures of Tiamulin, Homoharringtonine and Bruceantin Bound to the Ribosome

    SciTech Connect (OSTI)

    Gurel, G.; Blaha, G; Moore, P; Steitz,

    2009-01-01T23:59:59.000Z

    Structures have been obtained for the complexes that tiamulin, homoharringtonine, and bruceantin form with the large ribosomal subunit of Haloarcula marismortui at resolutions ranging from 2.65 to 3.2 {angstrom}. They show that all these inhibitors block protein synthesis by competing with the amino acid side chains of incoming aminoacyl-tRNAs for binding in the A-site cleft in the peptidyl-transferase center, which is universally conserved. In addition, these structures support the hypothesis that the species specificity exhibited by the A-site cleft inhibitors is determined by the interactions they make, or fail to make, with a single nucleotide, U2504 (Escherichia coli). In the ribosome, the position of U2504 is controlled by its interactions with neighboring nucleotides, whose identities vary among kingdoms.

  14. Determining the best source of renewable electricity to power a remote site for the National Park Service

    SciTech Connect (OSTI)

    Azerbegl, R.; Mas, C.; Walker, A.; Morris, R.; Christensen, J.

    1999-07-01T23:59:59.000Z

    Renewable energy technologies have economic and environmental advantages in many remote applications. They can provide most of the power to off-grid loads, where batteries and another power source such as a generator or a fuel cell may be required to ensure availability and feasibility. In support of the National Park Service, the Federal Energy Management Program Team at the National Renewable Energy Laboratory has evaluated several methods for providing a renewable source of electricity to a beach campsite at Kirby Cove, Marin County, California. This site requires 2 kWh per day to power a campground host in a motor home five months power year. The existing electricity line to the site is in need of replacement and the NPS is interested in evaluating more cost-effective and environmentally sensitive alternatives. Photovoltaics, tidal current, and wind power systems in combination with a back-up electric system (standard, thermoelectric, and Stirling generator and fuel cell) and an energy storage medium (battery, flywheel, and hydrogen) were analyzed. Multi-objective optimization criteria include initial cost, operating cost, emissions, maintenance requirements, and to be consistent with the NPS requirements, the system must be clean, silent, and sustainable. The best system combination was designed according to these evaluation criteria and a demonstration system is to be constructed. This paper describes the optimization procedure and design. Results indicate that a 800 Watt photovoltaic array with a hydrogen fuel cell best serves the requirements for clean, silent power. Since fuel cells are developmental, a propane generator is recommended as an alternative.

  15. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01T23:59:59.000Z

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  16. Radiological characterization survey of the former Diamond Magnesium Company Company site, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001, DMP002)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1991-12-01T23:59:59.000Z

    At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory performed an investigative radiological survey at the former Diamond Magnesium Company (DMC) site at 720 Fairport-Nursery Road, Painesville, Ohio, in September 1990. The purpose of the survey was to determine if the site is contaminated with radioactive residues as a result of federal government operation in the development of nuclear energy for defense-related projects. The survey of the site, separate parcels of which are currently owned by the Uniroyal Chemical Company (DMP001) and the Lonza Chemical Company (DMP002), included a gamma scan over the ground surface, determination of gamma exposure rates at the surface and at 1 m above the surface at grid points, collection and radionuclide analysis of soil samples, and directly measured radiation levels inside three buildings used during original DMC processing. Results of the survey revealed widespread radiological contamination outdoors on the Uniroyal property and several isolated spots of elevated radiation levels on the Lonza property. The contaminants consisted of radium, uranium, and thorium in surface and subsurface soil in concentrations exceeding DOE guidelines for the release of property for unrestricted use.

  17. Site characterization summary report for dry weather surface water sampling upper East Fork Poplar Creek characterization area Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    This report describes activities associated with conducting dry weather surface water sampling of Upper East Fork Poplar Creek (UEFPC) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. This activity is a portion of the work to be performed at UEFPC Operable Unit (OU) 1 [now known as the UEFPC Characterization Area (CA)], as described in the RCRA Facility Investigation Plan for Group 4 at the Oak- Ridge Y-12 Plant, Oak Ridge, Tennessee and in the Response to Comments and Recommendations on RCRA Facility Investigation Plan for Group 4 at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Volume 1, Operable Unit 1. Because these documents contained sensitive information, they were labeled as unclassified controlled nuclear information and as such are not readily available for public review. To address this issue the U.S. Department of Energy (DOE) published an unclassified, nonsensitive version of the initial plan, text and appendixes, of this Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) Plan in early 1994. These documents describe a program for collecting four rounds of wet weather and dry weather surface water samples and one round of sediment samples from UEFPC. They provide the strategy for the overall sample collection program including dry weather sampling, wet weather sampling, and sediment sampling. Figure 1.1 is a schematic flowchart of the overall sampling strategy and other associated activities. A Quality Assurance Project Plan (QAPJP) was prepared to specifically address four rounds of dry weather surface water sampling and one round of sediment sampling. For a variety of reasons, sediment sampling has not been conducted and has been deferred to the UEFPC CA Remedial Investigation (RI), as has wet weather sampling.

  18. CHARACTERIZATION REPORT FOR STRONTIUM TITANATE IN SWSA 7 AND ADJACENT PARCELS IN SUPPORT OF THE NATIONAL PRIORITIES LIST SITE BOUNDARY DEFINITION PROGRAM OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    David A. King

    2011-10-10T23:59:59.000Z

    The U.S. Department of Energy (DOE) Oak Ridge Office requested support from the Oak Ridge Institute for Science and Education (ORISE) contract to delineate the extent of strontium titanate (SrTiO3) contamination in and around Solid Waste Storage Area (SWSA) 7 as part of the Oak Ridge National Priorities List Site boundary definition program. The study area is presented in Fig. 1.1 relative to the Oak Ridge Reservation (ORR). The investigation was executed according to Sampling and Analysis Plan/Quality Assurance Project Plan (SAP/QAPP) (DOE 2011) to supplement previous investigations noted below and to determine what areas, if any, have been adversely impacted by site operations.

  19. Characterization of Sediments from the Soil Desiccation Pilot Test (SDPT) Site in the BC Cribs and Trenches Area

    SciTech Connect (OSTI)

    Um, Wooyong; Truex, Michael J.; Valenta, Michelle M.; Iovin, Cristian; Kutnyakov, Igor V.; Chang, Hyun-shik; Clayton, Ray E.; Serne, R. Jeffrey; Ward, Anderson L.; Brown, Christopher F.; Geiszler, Keith N.; Clayton, Eric T.; Baum, Steven R.; Smith, David M.

    2009-09-25T23:59:59.000Z

    This technical report documents the results of laboratory geochemical and hydrologic measurements of sediments collected from new borehole 299-E13-65 (C7047) and comparison of the results with those of nearby borehole 299-13E-62 (C5923) both drilled in the BC Cribs and Trenches Area. The total and water-leachable concentrations of key contaminants will be used to update contaminant-distribution conceptual models and to provide more data for improving baseline risk predictions and remedial alternative selections. Improved understanding of subsurface conditions and methods to remediate these principal contaminants can be also used to evaluate the application of specific technologies to other contaminants across the Hanford Site.

  20. Site-Selective Determination of Magnetic Helices in BaTiCoFe{sub 10}O{sub 19} by Resonant Magnetic Scattering

    SciTech Connect (OSTI)

    Okube, Maki; Kaneko, Yuhei; Ohsawa, Seiji; Sasaki, Satoshi [Materials and Structures Laboratory, Tokyo Institute of Technology, Nagatsuta 4259, Yokohama 226-8503 (Japan); Toyoda, Takeshi [Industrial Research Institute of Ishikawa, Kuratsuki 2-1, Kanazawa 920-8203 (Japan); Mori, Takeharu [Photon Factory, Institute of Materials Structure Science, KEK, Oho 1-1, Tsukuba 305-0801 (Japan)

    2010-06-23T23:59:59.000Z

    Synchrotron radiation intensity measurements were made for single crystals of ferrimagnetic BaTiCoFe{sub 10}O{sub 19} at the BL-6C(3A) beamline of the Photon Factory. The resonant x-ray magnetic scattering (RXMS) method at the Fe K edge makes it possible to determine the magnetic crystal structure, having the magnetic helices for Fe ions in tetrahedral 4f{sub 1}, bipyramidal 2b, and octahedral 2a, 4f{sub 2} and 12k sites. Based on the information on x-ray magnetic circular dichroism (XMCD) and a resonant magnetic scattering factor f''{sub m} ( = 0.23) estimated from BaFe{sub 12}O{sub 19} at E = 7128.2 eV, the magnetic structures have been determined from an asymmetrical ratio {Delta}R (Y{sup +}-Y{sup -})/(Y{sup +}+Y{sup -}), where Y{sup +} and Y{sup -} are scattering intensities for left- and right-circular polarizations, respectively. Spin orientations were estimated in the least-squares procedure to minimize a residual factor of {Sigma}({Delta}R{sub obs}-{Delta}R{sub calc}){sup 2}. The canting angles estimated in this study are 180 deg., 19 deg., 118 deg., 180 deg. and 65 deg. for the magnetic moments of Fe ions in 4f{sub 1}, 2b, 2a, 4f{sub 2} and 12k sites, respectively.

  1. Influence of woody dominated rangelands on site hydrology and herbaceous production, Edwards Plateau, Texas

    E-Print Network [OSTI]

    Hester, Justin Wayne

    1996-01-01T23:59:59.000Z

    Station at Sonora, Texas. The objective was to characterize interception by juniper canopy and litter, and to determine the redistributive effects of throughfall and stemflow on site hydrology. Based on a 10-year distribution pattern of rainfall, 66...

  2. Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

    SciTech Connect (OSTI)

    MacDougall, H R; Scully, L W; Tillerson, J R [comps.] [comps.

    1987-09-01T23:59:59.000Z

    The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

  3. CHARACTERIZATION OF DEFENSE NUCLEAR WASTE USING HAZARDOUS WASTE GUIDANCE. APPLICATIONS TO HANFORD SITE ACCELERATED HIGH-LEVEL WASTE TREATMENT AND DISPOSAL MISSION0

    SciTech Connect (OSTI)

    Hamel, William; Huffman, Lori; Lerchen, Megan; Wiemers, Karyn

    2003-02-27T23:59:59.000Z

    Federal hazardous waste regulations were developed for management of industrial waste. These same regulations are also applicable for much of the nation's defense nuclear wastes. At the U.S. Department of Energy's (DOE) Hanford Site in southeast Washington State, one of the nation's largest inventories of nuclear waste remains in storage in large underground tanks. The waste's regulatory designation and its composition and form constrain acceptable treatment and disposal options. Obtaining detailed knowledge of the tank waste composition presents a significant portion of the many challenges in meeting the regulatory-driven treatment and disposal requirements for this waste. Key in applying the hazardous waste regulations to defense nuclear wastes is defining the appropriate and achievable quality for waste feed characterization data and the supporting evidence demonstrating that applicable requirements have been met at the time of disposal. Application of a performance-based approach to demonstrating achievable quality standards will be discussed in the context of the accelerated high-level waste treatment and disposal mission at the Hanford Site.

  4. Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1995-03-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells.

  5. Conceptual, experimental and computational approaches to support performance assessment of hydrology and chemical transport at Yucca Mountain; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Narasimhan, T.N.; Wang, J.S.Y. [Lawrence Berkeley Lab., CA (United States)

    1992-07-01T23:59:59.000Z

    The authors of this report have been participating in the Sandia National Laboratory`s hydrologic performance assessment of the Yucca Mountain, Nevada, since 1983. The scope of this work is restricted to the unsaturated zone at Yucca Mountain and to technical questions about hydrology and chemical transport. The issues defined here are not to be confused with the elaborate hierarchy of issues that forms the framework of the US Department of Energy plans for characterizing the site (DOE, 1989). The overall task of hydrologic performance assessment involves issues related to hydrology, geochemistry, and energy transport in a highly heterogeneous natural geologic system which will be perturbed in a major way by the disposal activity. Therefore, a rational evaluation of the performance assessment issues must be based on an integrated appreciation of the aforesaid interacting processes. Accordingly, a hierarchical approach is taken in this report, proceeding from the statement of the broad features of the site that make it the site for intensive studies and the rationale for disposal strategy, through the statement of the fundamental questions that need to be answered, to the identification of the issues that need resolution. Having identified the questions and issues, the report then outlines the tasks to be undertaken to resolve the issues. The report consists essentially of two parts. The first part deals with the definition of issues summarized above. The second part summarizes the findings of the authors between 1983 and 1989 under the activities of the former Nevada Nuclear Waste Storage Investigations (NNWSI) and the current YMP.

  6. Total System Performance Assessment Code (TOSPAC); Volume 2, User`s guide: Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Gauthier, J.H.; Dudley, A.L; Skinner, L.H. [Spectra Research Inst., Albuquerque, NM (United States); Wilson, M.L.; Peters, R.R. [Sandia National Labs., Albuquerque, NM (United States)

    1992-07-01T23:59:59.000Z

    TOSPAC is a computer program that calculates partially saturated groundwater flow with the transport of water-soluble contaminants. TOSPAC Version 1 is restricted to calculations involving one-dimensional, vertical columns of one or more media. TOSPAC was developed to help answer questions surrounding the burial of toxic wastes in arid regions. Burial of wastes in arid regions is attractive because of generally low population densities and little groundwater flow, in the unsaturated zone, to disturb the waste. TOSPAC helps to quantify groundwater flow and the spread of contamination, offering an idea of what could happen in the distant future. Figure 1.1 illustrates the problem TOSPAC was designed to investigate. For groundwater flow, TOSPAC can provide saturations, velocities, and and travel tunes for water in the rock matrix or the fractures in the unsaturated zone. TOSPAC can determine how hydrologic conditions vary when the rate of infiltration changes. For contaminant transport, TOSPAC can compute how much of a contaminant is dissolved in the water and how it is distributed. TOSPAC can determine how fast the solute is moving and the shape of the concentration front. And TOSPAC can be used to investigate how much of the contaminant remains in the inventory of a repository, how much is adsorbed onto the soil or rock matrix, and how much reaches the water table. Effective use of TOSPAC requires knowledge in a number of diverse disciplines, including real groundwater flow and transport, the mathematical models of groundwater flow and transport, real-world data required for the models, and the numerical solution of differential equations. Equally important is a realization of the limitations intrinsic to a computer model of complex physical phenomena. This User`s Guide not only describes the mechanics of executing TOSPAC on a computer, but also examines these other topics.

  7. Determining Long-Term Performance of Cool Storage Systems from Short-Term Tests; Literature Review, Preliminary Methodology Description, and Final Site Selection (Final Revision of Nov. 1997 Report)

    E-Print Network [OSTI]

    Reddy, T. A.; Elleson, J.; Haberl, J. S.; Claridge, D. E.

    1998-01-01T23:59:59.000Z

    This preliminary report contains the literature review, a preliminary description of the methodologies that have been chosen for the project and final site selection recommendations for ASHRAE Research Project RP 1004 ~ "Determining Long...

  8. U2504 Determines the Species Specificity of the A-Site Cleft Antibiotics: The Structures of Tiamulin, Homoharringtonine, and Bruceantin Bound to the Ribosome

    SciTech Connect (OSTI)

    Gürel, Güliz; Blaha, Gregor; Moore, Peter B.; Steitz, Thomas A.; Yale

    2009-06-30T23:59:59.000Z

    Structures have been obtained for the complexes that tiamulin, homoharringtonine, and bruceantin form with the large ribosomal subunit of Haloarcula marismortui at resolutions ranging from 2.65 to 3.2 {angstrom}. They show that all these inhibitors block protein synthesis by competing with the amino acid side chains of incoming aminoacyl-tRNAs for binding in the Asite cleft in the peptidyl-transferase center, which is universally conserved. In addition, these structures support the hypothesis that the species specificity exhibited by the A-site cleft inhibitors is determined by the interactions they make, or fail to make, with a single nucleotide, U2504 (Escherichia coli). In the ribosome, the position of U2504 is controlled by its interactions with neighboring nucleotides, whose identities vary among kingdoms.

  9. Compressed air energy storage: preliminary design and site development program in an aquifer. Final draft, Task 2: Volume 2 of 3. Characterize and explore potential sites and prepare research and development plan

    SciTech Connect (OSTI)

    None

    1980-12-01T23:59:59.000Z

    The characteristics of sites in Indiana and Illinois which are being investigated as potential sites for compressed air energy storage power plants are documented. These characteristics include geological considerations, economic factors, and environmental considerations. Extensive data are presented for 14 specific sites and a relative rating on the desirability of each site is derived. (LCL)

  10. Site Characterization for CO{sub 2} Storage from Coal-fired Power Facilities in the Black Warrior Basin of Alabama

    SciTech Connect (OSTI)

    Clark, Peter; Pashin, Jack; Carlson, Eric; Goodliffe, Andrew; McIntyre-Redden, Marcella; Mann, Steven; Thompson, Mason

    2012-08-31T23:59:59.000Z

    Coal-fired power plants produce large quantities of carbon dioxide. In order to mitigate the greenhouse gas emissions from these power plants, it is necessary to separate and store the carbon dioxide. Saline formations provide a potential sink for carbon dioxide and delineating the capacity of the various known saline formations is a key part of building a storage inventory. As part of this effort, a project was undertaken to access the storage capacity of saline reservoirs in the Black Warrior Basin of Alabama. This basin has been a productive oil and gas reservoir that is well characterized to the west of the two major coal-fired power plants that are north of Birmingham. The saline zones were thought to extend as far east as the Sequatchie Anticline which is just east of the power plants. There is no oil or gas production in the area surrounding the power plants so little is known about the formations in that area. A geologic characterization well was drilled on the Gorgas Power Plant site, which is the farthest west of two power plants in the area. The well was planned to be drilled to approximately 8,000 feet, but drilling was halted at approximately 5,000 feet when a prolific freshwater zone was penetrated. During drilling, a complete set of cores through all of the potential injection zones and the seals above these zones were acquired. A complete set of openhole logs were run along with a vertical seismic profile (VSP). Before drilling started two approximately perpendicular seismic lines were run and later correlated with the VSP. While the zones that were expected were found at approximately the predicted depths, the zones that are typically saline through the reservoir were found to be saturated with a light crude oil. Unfortunately, both the porosity and permeability of these zones were small enough that no meaningful hydrocarbon production would be expected even with carbon dioxide flooding. iv While this part of the basin was found to be unsuitable for carbon dioxide injection, there is still a large storage capacity in the basin to the west of the power plants. It will, however, require pipeline construction to transport the carbon dioxide to the injection sites.

  11. An Initial Evaluation of Characterization and Closure Options for Underground Pipelines within a Hanford Site Single-Shell Tank Farm - 13210

    SciTech Connect (OSTI)

    Badden, Janet W.; Connelly, Michael P. [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States)] [Washington River Protection Services, P.O. Box 850, Richland, Washington, 99352 (United States); Seeley, Paul N. [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States)] [Cenibark International, Inc., 104318 Nicole Drive, Kennewick, Washington, 99338-7596 (United States); Hendrickson, Michelle L. [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)] [Washington State Department of Ecology, 3100 Port of Benton Blvd, Richland, Washington, 99354 (United States)

    2013-07-01T23:59:59.000Z

    The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left 'as is' and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines. (authors)

  12. Moderately to Poorly Welded Tuff, Bishop, California: Geophysical and Geological Characterization to Determine the Source of Radar

    E-Print Network [OSTI]

    Stillman, David E.

    of Earth, Material, and Planetary Sciences, Southwest Research Institute, 6220 Culebra Road, San Antonio@swri.org) , Department of Earth, Material, and Planetary Sciences, Southwest Research Institute, 6220 Culebra Road, San in the Volcanic Tableland (Bishop, California) as an analog site because some Martian volcanoes and the Stealth

  13. Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL1A, NPFPDL1B, NPFPDL1C and NPFPDL1D

    SciTech Connect (OSTI)

    WINTERHALDER, J.A.

    1999-09-29T23:59:59.000Z

    This Hazardous Waste Determination Report is intended to satisfy the terms of a Memorandum of Agreement (Agreement signed on June 16, 1999) between the U.S. Department of Energy and the New Mexico Environment Department. The Agreement pertains to the exchange of information before a final decision is made on the Waste Isolation Pilot Plant application for a permit under the ''New Mexico Hazardous Waste Act''. The Agreement will terminate upon the effective date of a final ''New Mexico Hazardous Waste Act'' permit for the Waste Isolation Pilot Plant. In keeping with the principles and terms of the Agreement, this report describes the waste stream data and information compilation process, and the physical and chemical analyses that the U.S. Department of Energy has performed on selected containers of transuranic debris waste to confirm that the waste is nonhazardous (non-mixed). This also summarizes the testing and analytical results that support the conclusion that the selected transuranic debris waste is not hazardous and thus, not subject to regulation under the ''Resource Conservation and Recovery Act'' or the ''New Mexico Hazardous Waste Act''. This report will be submitted to the New Mexico Environment Department no later than 45 days before the first shipment of waste from the Hanford Site to the Waste Isolation Pilot Plant, unless the parties mutually agree in writing to a shorter time. The 52 containers of transuranic debris waste addressed in this report were generated, packaged, and placed into storage between 1995 and 1997. Based on reviews of administrative documents, operating procedures, waste records, generator certifications, and personnel interviews, this transuranic debris waste was determined to be nonhazardous. This determination is supported by the data derived from nondestructive examination, confirmatory visual examination, and the results of container headspace gas sampling and analysis. Therefore, it is concluded that this transuranic debris waste, which consists of 52 containers from waste streams NPFPDLIA, NPFPDLIB, NPFPDLIC, and NPFPDLID, is not hazardous waste, and no hazardous waste numbers specified in Title 40 Code of Federal Regulations, Part 261, have been assigned. Accordingly, the 52 containers of transuranic debris waste addressed in this report meet the requirements for transuranic waste as defined by the Department of Energy Waste Acceptance Criteria for the Waste Isolation Pilot Plant. The 52 containers are acceptable for disposal at the Waste Isolation Pilot Plant as nonhazardous transuranic waste.

  14. Structural Analysis of Phospholipase A2 from Functional Perspective. 2. Characterization of a Molten Globule-Like State Induced by Site-Specific

    E-Print Network [OSTI]

    Tsai, Ming-Daw

    , the hydrophobic channel, the interfacial binding site, and the calcium-binding loop) are located in the remainder

  15. Geologic report for the Weldon Spring Raffinate Pits Site

    SciTech Connect (OSTI)

    none,

    1984-10-01T23:59:59.000Z

    A preliminary geologic site characterization study was conducted at the Weldon Spring Raffinate Pits Site, which is part of the Weldon Spring Site, in St. Charles County, Missouri. The Raffinate Pits Site is under the custody of the Department of Energy (DOE). Surrounding properties, including the Weldon Spring chemical plant, are under the control of the Department of the Army. The study determined the following parameters: site stratigraphy, lithology and general conditions of each stratigraphic unit, and groundwater characteristics and their relation to the geology. These parameters were used to evaluate the potential of the site to adequately store low-level radioactive wastes. The site investigation included trenching, geophysical surveying, borehole drilling and sampling, and installing observation wells and piezometers to monitor groundwater and pore pressures.

  16. Supplement Analysis for Site-Wide Environmental Impact Statement for Continued Operation of Los Alamos National Laboratory -- Modification of Management Methods for Transuranic Waste Characterization at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    N /A

    2002-08-13T23:59:59.000Z

    This Supplement Analysis (SA) has been prepared to determine if the Site-Wide Environmental Impact Statement for Continued Operations of Los Alamos National Laboratory (SWEIS) (DOE/EIS-0238) adequately addresses the environmental effects of a waste management proposal for installing and operating modular units for the characterization of transuranic (TRU) waste1 at the Los Alamos National Laboratory (LANL) Technical Area (TA)-54, Area G, or if the SWEIS needs to be supplemented. Council on Environmental Quality regulations at Title 40, Section 1502.9 (c) of the Code of Federal Regulations (40 CFR 1502.9[c]) require federal agencies to prepare a supplement to an EIS when an agency makes substantial changes in the proposed action that are relevant to environmental concerns or there are circumstances or information relevant to concerns and bearing on the proposed action or its impacts. This SA is prepared in accordance with Section 10 CFR 1021.314(c) of the Department of Energy's (DOE's) regulations for NEPA implementation stating that ''When it is unclear whether or not an EIS supplement is required, DOE shall prepare a Supplement Analysis.'' This SA specifically compares key impact assessment parameters of the waste management program evaluated in the SWEIS with those of a proposal that would change the approach of a portion of this management program. It also provides an explanation of any differences between the proposed action and activities described in the previous SWEIS analysis. DOE proposes to expedite the shipment of legacy TRU waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The Cerro Grande Fire in 2000 and events of September 11, 2001, have focused attention on the potential risk to the public and the credible security hazard posed by the amount of plutonium stored above ground at LANL and the increased necessity to safeguard our nation's nuclear waste. The safest place for defense-generated TRU waste has been determined to be DOE's permitted repository for TRU waste 2100 feet underground at WIPP. The proposed accelerated plan to dispose of TRU waste at WIPP would result in the complete disposition of LANL legacy TRU waste by 2010; this accelerated disposition would be 20 years ahead of schedule, at a savings of $500 million in life-cycle costs and result in 3,000 fewer shipments to WIPP. However, the current individual small facilities at LANL lack the buildings, equipment, and trained personnel to conduct efficient characterization activities on an increased scale. Installing new modular structures and equipment close to the drum storage location at TA-54 in housings designed for a large inventory and high throughput would support DOE's expedited shipment program by increasing the repackaging rate, and it would also decrease on-site transportation vulnerabilities.

  17. A Geophysical Characterization & Monitoring Strategy for Determining Hydrologic Processes in the Hyporheic Corridor at the Hanford 300-Area

    SciTech Connect (OSTI)

    Slater, Lee; Day-Lewis, Frederick; Lane, John; Versteeg, Roelof; Ward, Anderson; Binley, Andrew; Johnson, Timothy; Ntarlagiannis, Dimitrios

    2011-08-31T23:59:59.000Z

    The primary objective of this research was to advance the prediction of solute transport between the Uranium contaminated Hanford aquifer and the Columbia River at the Hanford 300 Area by improving understanding of how fluctuations in river stage, combined with subsurface heterogeneity, impart spatiotemporal complexity to solute exchange along the Columbia River corridor. Our work explored the use of continuous waterborne electrical imaging (CWEI), in conjunction with fiber-optic distributed temperature sensor (FO-DTS) and time-lapse resistivity monitoring, to improve the conceptual model for how groundwater/surface water exchange regulates uranium transport. We also investigated how resistivity and induced polarization can be used to generate spatially rich estimates of the variation in depth to the Hanford-Ringold (H-R) contact between the river and the 300 Area Integrated Field Research Challenge (IFRC) site. Inversion of the CWEI datasets (a data rich survey containing {approx}60,000 measurements) provided predictions of the distributions of electrical resistivity and polarizability, from which the spatial complexity of the primary hydrogeologic units along the river corridor was reconstructed. Variation in the depth to the interface between the overlying coarse-grained, high permeability Hanford Formation and the underlying finer-grained, less permeable Ringold Formation, an important contact that limits vertical migration of contaminants, has been resolved along {approx}3 km of the river corridor centered on the IFRC site in the Hanford 300 Area. Spatial variability in the thickness of the Hanford Formation captured in the CWEI datasets indicates that previous studies based on borehole projections and drive-point and multi-level sampling likely overestimate the contributing area for uranium exchange within the Columbia River at the Hanford 300 Area. Resistivity and induced polarization imaging between the river and the 300 Area IFRC further imaged spatial variability in the depth to the Hanford-Ringold inland over a critical region where borehole information is absent, identifying evidence for a continuous depression in the H-R contact between the IFRC and the river corridor. Strong natural contrasts in temperature and specific conductance of river water compared to groundwater at this site, along with periodic river stage fluctuations driven by dam operations, were exploited to yield new insights into the dynamics of groundwater-surface water interaction. Whereas FO-DTS datasets have provided meter-scale measurements of focused groundwater discharge at the riverbed along the corridor, continuous resistivity monitoring has non-invasively imaged spatiotemporal variation in the resistivity inland driven by river stage fluctuations. Time series and time-frequency analysis of FO-DTS and 3D resistivity datasets has provided insights into the role of forcing variables, primarily daily dam operations, in regulating the occurrence of focused exchange at the riverbed and its extension inland. High amplitudes in the DTS and 3D resistivity signals for long periods that dominate the stage time series identify regions along the corridor where stage-driven exchange is preferentially focused. Our work has demonstrated how time-series analysis of both time-lapse resistivity and DTS datasets, in conjunction with resistivity/IP imaging of lithology, can improve understanding of groundwater-surface water exchange along river corridors, offering unique opportunities to connect stage-driven groundwater discharge observed with DTS on the riverbed to stage-driven groundwater and solute fluctuations captured with resistivity inland.

  18. Determination of leaf area index of loblolly pine (Pinus taeda L.) and its relationship to site water balance across a large precipitation gradient in East Texas

    E-Print Network [OSTI]

    Hebert, Mark Thomas

    1996-01-01T23:59:59.000Z

    was estimated using the Thornthwaite and Mather (1957) model to predict potential and actual evapotranspiration and moisture deficit. LAI and site water balance were estimated in both 1994 and 1995. 1 hypothesized that LAI would be positively correlated...

  19. THE USE OF GROUND-PENETRATING RADAR FOR ARCHAEOLOGY: DETERMINING SITE FORMATION PROCESSES AND SUBSURFACE FEATURES ON TUTUILA ISLAND, AMERICAN SAMOA

    E-Print Network [OSTI]

    Welch, Daniel

    2006-07-11T23:59:59.000Z

    , ceremonial mound (i.e. star mound) construction details were easily seen in radar profiles. Ground penetrating radar has the potential to yield significant details about such mounds, with no physical impact to the site....

  20. ORISE: Characterization surveys

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide...

  1. Managing contaminated sites

    SciTech Connect (OSTI)

    Asante-Duah, D.K.

    1997-12-31T23:59:59.000Z

    This book summarizes the generic principles of contaminated site management. The book walks the reader through contaminated site identification, risk assessment and the evaluation of remediation alternatives. The book is divided into two major sections, problem diagnosis and development of site restoration. In problem diagnosis, the general principles of site investigation are discussed, including the objectives and differences between tier 1,2, and 3 investigations. The principles of data collection and analysis are presented. A small quantitative discussion of statistical analysis is presented but in keeping with the objectives of the text is not sufficient comprehensive or detailed to provide much of a guide for the practitioner. Chapters on contaminant fate and transport processes and risk assessment help the reader understand the role of these issues in site investigation and remedial planning. A chapter is also included on elements of a site characterization activity, which summarizes some of the key considerations in conducting a site investigation.

  2. Characterization Activities to Evaluate Chlorinated Solvent Discharges to Tims Branch from the A/M Area of the Savannah River Site

    SciTech Connect (OSTI)

    Jackson, D.G.

    2001-02-23T23:59:59.000Z

    The objective of this investigation was to identify those regions of plume outcrop along Tims Branch southeast of A/M Area and to establish fixed monitoring points along the seepline to evaluate proposed remediation needs and to support long-term monitoring activities in the vicinity of the seepline. The characterization approach employed in completing these tasks was dynamic and graded. Three stages of characterization were used to evaluate the outcrop region, with the results from each of the previous activities used to direct subsequent characterization.

  3. Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

    2011-04-01T23:59:59.000Z

    This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the southwest corner of the Idaho Nuclear Technology and Engineering Center (INTEC). At Site 5, large area and smaller-scale detailed surveys were performed. At Site 34, a large area survey was performed. The purpose of the surveys was to define the topography of the interface between the surficial alluvium and underlying basalt. Seismic data were first collected and processed using seismic refraction tomographic inversion. Three-dimensional images for both sites were rendered from the data to image the depth and velocities of the subsurface layers. Based on the interpreted top of basalt data at Site 5, a more detailed survey was conducted to refine depth to basalt. This report briefly covers relevant issues in the collection, processing and inversion of the seismic refraction data and in the imaging process. Included are the parameters for inversion and result rendering and visualization such as the inclusion of physical features. Results from the processing effort presented in this report include fence diagrams of the earth model, for the large area surveys and iso-velocity surfaces and cross sections from the detailed survey.

  4. PROBABILISTIC SITE IDENTIFICATION ANALYSIS USING NUPEC RECORDED FREE FIELD MOTIONS.

    SciTech Connect (OSTI)

    XU,J.; COSTANTINO,C.; HOFMAYER,C.; MURPHY,A.; KITADA,Y.

    2002-08-04T23:59:59.000Z

    THIS PAPER DESCRIBES A PROBABILISTIC SITE IDENTIFICATION ANALYSIS PERFORMED BY BNL, USING THE FREE FIELD EARTHQUAKE MOTIONS RECORDED AT THE NUPEC TEST SITE. THE BNL ANALYSIS WAS INTENDED TO PROVIDE ADEQUATE CHARACTERIZATION OF THE SOIL PROPERTIES FOR THE TEST SITE TO BE USED FOR SSI ANALYSES. THE FREE FIELD DATA WERE PROVIDED BY NUPEC. THE METHODOLOGY EMPLOYED IN THE BNL PROBABILISTIC ANALYSIS OF SITE IDENTIFICATION INCLUDES THE MONTE CARLO PROCESS IN CONJUNCTION WITH EQUIVALENT LINEARCONVOLUTION ANALYSES FOR GENERATING A LARGE NUMBER OF SITE PROFILES FOR USE IN CONVOLUTION STUDIES FROM WHICH MEAN ESTIMATES OF RESPONSE CAN BE GENERATED. THE RANDOM VARIABLE SELECTED TO CHARACTERIZE THE SITE PROFILE IS THE SHEAR WAVE VELOCITY IN EACH SOIL LAYER OF THE SITE PROFILE. A LOGNORMAL DISTRIBUTION WAS ASSUMED WITH THE STANDARD DEVIATION DETERMINED FROM AVAILABLE SITE DATA AND APPLICABLE REGULATORY REQUIREMENTS. THE CONVOLUTION ANALYSES WERE PERFORMED USING AN APPROPRIATE SOILDEGRADATION MODEL AN D THE OUTCROP INPUT MOTIONS GENERATED FROM THE RECORDED IN ROCK MOTIONS. THE BNL ANALYSIS PRODUCED RESULTS IN TERMS OF THE MEAN, MEDIAN AND VARIOUS FRACTILES OF FREE FIELD SOIL PROPERTIES AT THE TEST SITE, AND THE CORRESPONDING SURFACE RESPONSE SPECTRA, WHICH ARE PRESENTED IN THIS PAPER.

  5. Discovery and Characterization of a Cell-Permeable, Small-Molecule c-Abl Kinase Activator that Binds to the Myristoyl Binding Site

    SciTech Connect (OSTI)

    Yang, Jingsong; Campobasso, Nino; Biju, Mangatt P.; Fisher, Kelly; Pan, Xiao-Qing; Cottom, Josh; Galbraith, Sarah; Ho, Thau; Zhang, Hong; Hong, Xuan; Ward, Paris; Hofmann, Glenn; Siegfried, Brett; Zappacosta, Francesca; Washio, Yoshiaki; Cao, Ping; Qu, Junya; Bertrand, Sophie; Wang, Da-Yuan; Head, Martha S.; Li, Hu; Moores, Sheri; Lai, Zhihong; Johanson, Kyung; Burton, George; Erickson-Miller, Connie; Simpson, Graham; Tummino, Peter; Copeland, Robert A.; Oliff, Allen (GSKPA)

    2014-10-02T23:59:59.000Z

    c-Abl kinase activity is regulated by a unique mechanism involving the formation of an autoinhibited conformation in which the N-terminal myristoyl group binds intramolecularly to the myristoyl binding site on the kinase domain and induces the bending of the {alpha}I helix that creates a docking surface for the SH2 domain. Here, we report a small-molecule c-Abl activator, DPH, that displays potent enzymatic and cellular activity in stimulating c-Abl activation. Structural analyses indicate that DPH binds to the myristoyl binding site and prevents the formation of the bent conformation of the {alpha}I helix through steric hindrance, a mode of action distinct from the previously identified allosteric c-Abl inhibitor, GNF-2, that also binds to the myristoyl binding site. DPH represents the first cell-permeable, small-molecule tool compound for c-Abl activation.

  6. Site-Specific Seismic Site Response Model for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Rohay, Alan C.; Reidel, Steve P.

    2005-02-24T23:59:59.000Z

    This interim report documents the collection of site-specific geologic and geophysical data characterizing the Waste Treatment Plant site and the modeling of the site-specific structure response to earthquake ground motions.

  7. Field fracturing multi-sites project. Annual technical progress report, July 28, 1993--July 31, 1994

    SciTech Connect (OSTI)

    Not Available

    1995-02-01T23:59:59.000Z

    The objective of the Field Fracturing Multi-Sites Project (M-Site) is to conduct experiments to definitively determine hydraulic fracture dimensions using remote well and treatment well diagnostic techniques. In addition, experiments will be conducted to provide data which will resolve significant unknowns with regard to hydraulic fracture modeling, fluid fracture rheology and fracture treatment design. These experiments will be supported by a well-characterized subsurface environment, as well as surface facilities and equipment that are conducive to acquiring high-quality data. The goal is to develop a fully characterized, tight reservoir-typical, field-scale hydraulic-fracturing test site.

  8. Site Feeds - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System OutagesNewsMaterialsX-rayOur‹Simulation,Site

  9. Site Screening, Site Selection,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administrationcontroller systemsBi (2)Sharing Smartversatileplatform chemical.OfficeScreening, Site

  10. SURFACE GEOPHYSICAL EXPLORATION OF TX-TY TANK FARMS AT THE HANFORD SITE RESULTS OF BACKGROUND CHARACTERIZATION WITH GROUND PENETRATING RADAR

    SciTech Connect (OSTI)

    MYERS DA; CUBBAGE R; BRAUCHLA R; O'BRIEN G

    2008-07-24T23:59:59.000Z

    Ground penetrating radar surveys of the TX and TY tank farms were performed to identify existing infrastructure in the near surface environment. These surveys were designed to provide background information supporting Surface-to-Surface and Well-to-Well resistivity surveys of Waste Management Area TX-TY. The objective of the preliminary investigation was to collect background characterization information with GPR to understand the spatial distribution of metallic objects that could potentially interfere with the results from high resolution resistivity{trademark} surveys. The results of the background characterization confirm the existence of documented infrastructure, as well as highlight locations of possible additional undocumented subsurface metallic objects.

  11. HEFF---A user`s manual and guide for the HEFF code for thermal-mechanical analysis using the boundary-element method; Version 4.1: Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    St. John, C.M.; Sanjeevan, K. [Agapito (J.F.T.) and Associates, Inc., Grand Junction, CO (United States)

    1991-12-01T23:59:59.000Z

    The HEFF Code combines a simple boundary-element method of stress analysis with the closed form solutions for constant or exponentially decaying heat sources in an infinite elastic body to obtain an approximate method for analysis of underground excavations in a rock mass with heat generation. This manual describes the theoretical basis for the code, the code structure, model preparation, and step taken to assure that the code correctly performs its intended functions. The material contained within the report addresses the Software Quality Assurance Requirements for the Yucca Mountain Site Characterization Project. 13 refs., 26 figs., 14 tabs.

  12. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Attachment 3, Ground water hydrology report: Preliminary final

    SciTech Connect (OSTI)

    Not Available

    1994-03-04T23:59:59.000Z

    The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent ground water contamination resulting from processing activities at inactive uranium milling sites (52 FR 36000 (1987)). According to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, 42 USC {section}7901 et seq., the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that for Slick Rock, this assessment shall include hydrogeologic site characterization for two separate uranium processing sites, the Union Carbide (UC) site and the North Continent (NC) site, and for the proposed Burro Canyon disposal site. The water resources protection strategy that describes how the proposed action will comply with the EPA ground water protection standards is presented in Attachment 4. The following site characterization activities are discussed in this attachment: Characterization of the hydrogeologic environment, including hydrostratigraphy, ground water occurrence, aquifer parameters, and areas of recharge and discharge. Characterization of existing ground water quality by comparison with background water quality and the maximum concentration limits (MCL) of the proposed EPA ground water protection standards. Definition of physical and chemical characteristics of the potential contaminant source, including concentration and leachability of the source in relation to migration in ground water and hydraulically connected surface water. Description of local water resources, including current and future use, availability, and alternative supplies.

  13. Infrared studies of CO and CO/sub 2/ adsorption on Pt/CeO/sub 2/: the characterization of active sites

    SciTech Connect (OSTI)

    Daniel, D.W.

    1988-06-30T23:59:59.000Z

    The active sites of a ceria-supported platinum catalysts have been identified by the adsorption/desorption behavior of gases. On the fresh catalyst CO adsorption occurred on both cationic Pt and fully reduced metal. Two CO bands associated with adsorption on reduced Pt have been assigned to open- and close-packed sites. Both CO and CO/sub 2/ dissociation have been observed. Residual C(a) resulting from the dissociation of CO is removed following oxidation by the support at elevated temperature. The decrease in CO absorption which follows a 973 K reduction is reversed by a reoxidation and rereduction at 673 K. Sintering and encapsulation have not been supported by XPS and XRD and an electronic SMSI is proposed.

  14. Enterprise Assessments Targeted Review, Idaho Site AMWTP Report...

    Energy Savers [EERE]

    program (FPP) at the Idaho Site. The AMWTP is established to retrieve, characterize, treat, and package transuranic waste currently stored at the Idaho Site. The AMWTP includes...

  15. Remediation of a Former USAF Radioactive Material Disposal Site

    SciTech Connect (OSTI)

    Hoffman, D. E.; Cushman, M; Tupyi, B.; Lambert, J.

    2003-02-25T23:59:59.000Z

    This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of the United States Air Force. Included is a discussion of methods and strategies that were used to successfully exhume and characterize the wastes for proper disposal at offsite disposal facilities. Worker and environmental protection measures are also described. Information gained from this project may be used at other similar project sites. A total of nine burial tubes had been identified for excavation, characterization, and removal from the site. The disposal tubes were constructed of 4-ft lengths of concrete pipe buried upright with the upper ends flush with ground surface. Initial ground level observations of the burial tubes indicated that some weathering had occurred; however, the condition of the subsurface portions of the tubes was unknown. Soil excavation occurred in 1-foot lifts in order that the tubes could be inspected and to allow for characterization of the soils at each stage of the excavation. Due to the weight of the concrete pipe and the condition of the piping joints it was determined that special measures would be required to maintain the tubes intact during their removal. Special tube anchoring and handling methods were required to relocate the tubes from their initial positions to a staging area where they could be further characterized. Characterization of the disposal tubes was accomplished using a combination of gamma spectroscopy and activity mapping methods. Important aspects of the project included the use of specialized excavation and disposal tube reinforcement measures to maintain the disposal tubes intact during excavation, removal and subsequent characterization. The non-intrusive gamma spectroscopy and data logging methods allowed for effective characterization of the wastes while minimizing disposal costs. In addition, worker exposures were maintained ALARA as a result of the removal and characterization methods employed.

  16. CX-008005: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Site Characterization and Environmental Monitoring CX(s) Applied: B3.1 Date: 11/28/2011 Location(s): Washington Offices(s): Science, Pacific Northwest Site Office

  17. Feature Detection, Characterization and Confirmation Methodology: Final Report

    E-Print Network [OSTI]

    Karasaki, Kenzi

    2009-01-01T23:59:59.000Z

    modeling and groundwater flow analysis ? strategy for characterizing a new site ? 255 Introduction..

  18. TRACKING SITE

    Energy Science and Technology Software Center (OSTI)

    003235MLTPL00 AASG Geothermal Data submissions tracking application and site.  https://github.com/usgin/aasgtrack 

  19. Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1987-12-01T23:59:59.000Z

    This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.

  20. Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 3

    SciTech Connect (OSTI)

    NONE

    1986-05-01T23:59:59.000Z

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization.

  1. Environmental assessment: Yucca Mountain Site, Nevada Research and Development Area, Nevada; Volume 2

    SciTech Connect (OSTI)

    NONE

    1986-05-01T23:59:59.000Z

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EAs), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that is is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as one of five sites suitable for characterization.

  2. Environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada; Volume 1

    SciTech Connect (OSTI)

    NONE

    1986-05-01T23:59:59.000Z

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high- level radioactive waste. The site is in the Great Basin, which is one of five distinct geohydrologic settings considered for the first repository. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE`s General Guideline for the Recommendation of Sites for the Nuclear Waste Repositories. These evaluations were reported in draft environmental assessments (EA), which were issued for public review and comment. After considering the comments received on the draft EAs, the DOE prepared the final EAs. On the basis of the evaluations reported in this EA, the DOE found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is nominating the Yucca Mountain site as of five sites suitable for characterization.

  3. Characterization Activities to Determine the Extent of DNAPL in the Vadose Zone at the A-014 Outfall of A/M Area

    SciTech Connect (OSTI)

    Jackson, D.G.

    2000-09-05T23:59:59.000Z

    The purpose of this investigation was to perform characterization activities necessary to confirm the presence and extent of DNAPL in the shallow vadose zone near the headwaters of the A-014 Outfall. Following the characterization, additional soil vapor extraction wells and vadose monitoring probes were installed to promote and monitor remediation activities in regions of identified DNAPL.

  4. Environmental assessment, Deaf Smith County site, Texas

    SciTech Connect (OSTI)

    Not Available

    1986-05-01T23:59:59.000Z

    The Nuclear Waste Policy Act of 1982 (42 USC sections 10101-10226) requires the environmental assessment of a proposed site to include a statement of the basis for nominating a site as suitable for characterization. Volume 2 provides a detailed statement evaluating the site suitability of the Deaf Smith County Site under DOE siting guidelines, as well as a comparison of the Deaf Smith County Site to the other sites under consideration. The evaluation of the Deaf Smith County Site is based on the impacts associated with the reference repository design, but the evaluation will not change if based on the Mission Plan repository concept. The second part of this document compares the Deaf Smith County Site to Davis Canyon, Hanford, Richton Dome and Yucca Mountain. This comparison is required under DOE guidelines and is not intended to directly support subsequent recommendation of three sites for characterization as candidate sites. 259 refs., 29 figs., 66 refs. (MHB)

  5. Determinants that contribute to cytoplasmic stability of human c-fos and. beta. -globin mRNAs are located at several sites in each mRNA

    SciTech Connect (OSTI)

    Kabnick, K.S.; Housman, D.E.

    1988-08-01T23:59:59.000Z

    The authors have analyzed the contributions to cytoplasmic stability in an mRNA species with a very short half-life (human c-fos) and an mRNA species with a very long half-life (human ..beta..-globin). When the human c-fos promoter was used to drive the expression of human c-fos, ..beta..-globin, and chimeric DNAs between c-fos and ..beta..-globin in transfected cells, a pulse of mRNA synthesis was obtained following induction of transcription by refeeding quiescent cells with medium containing 15% calf serum. The mRNA half-life was determined by using Northern (RNA) blot analysis of mRNAs prepared at various times following the pulse of transcription. Under these conditions human c-fos mRNA exhibited a half-life of 6.6 min and human ..beta..-globin mRNA exhibited a half-life of 17.5 h. Replacement of the 3' end of the c-fos mRNA with the 3' end of the ..beta..-globin mRNA increased the half-life of the resultant RNA from 6.6 to 34 min. The reciprocal chimera had a half-life of 34.6 min compared with the 17.5-half-life of ..beta..-globin mRNA. These results suggest that sequences which make a major contribution to mRNA stability reside in the 3' end of either or both molecules. A chimera in which the 5' untranslated region of globin was replaced by part of the 5' untranslated region of fos led to destabilization of the encoded mRNA. This construct produced an mRNA with a half-life of 6.8 h instead of the 17.5-h half-life of globin. This result suggests that additional determinants of stability reside in the 5' end of these mRNA molecules. Substitution of part of the 5' untranslated region of fox by the 5' untranslated region of ..beta..-globin yielded an mRNA with stability similar to fos mRNA. These results suggest that interactions among sequences within each mRNA contribute to the stability of the respective molecules.

  6. Competitive Dynamics of Web Sites

    E-Print Network [OSTI]

    Sebastian M. Maurer; Bernardo A. Huberman

    2000-03-17T23:59:59.000Z

    We present a dynamical model of web site growth in order to explore the effects of competition among web sites and to determine how they affect the nature of markets. We show that under general conditions, as the competition between sites increases, the model exhibits a sudden transition from a regime in which many sites thrive simultaneously, to a "winner take all market" in which a few sites grab almost all the users, while most other sites go nearly extinct. This prediction is in agreement with recent measurements on the nature of electronic markets.

  7. Effects of a potential drop of a shipping cask, a waste container, and a bare fuel assembly during waste-handling operations; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Wu, C.L.; Lee, J.; Lu, D.L.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

    1991-12-01T23:59:59.000Z

    This study investigates the effects of potential drops of a typical shipping cask, waste container, and bare fuel assembly during waste-handling operations at the prospective Yucca Mountain Repository. The waste-handling process (one stage, no consolidation configuration) is examined to estimate the maximum loads imposed on typical casks and containers as they are handled by various pieces of equipment during waste-handling operations. Maximum potential drop heights for casks and containers are also evaluated for different operations. A nonlinear finite-element model is employed to represent a hybrid spent fuel container subject to drop heights of up to 30 ft onto a reinforced concrete floor. The impact stress, strain, and deformation are calculated, and compared to the failure criteria to estimate the limiting (maximum permissible) drop height for the waste container. A typical Westinghouse 17 {times} 17 PWR fuel assembly is analyzed by a simplified model to estimate the energy absorption by various parts of the fuel assembly during a 30 ft drop, and to determine the amount of kinetic energy in a fuel pin at impact. A nonlinear finite-element analysis of an individual fuel pin is also performed to estimate the amount of fuel pellet fracture due to impact. This work was completed on May 1990.

  8. Preliminary Site Characterization Report, Rulison Site, Colorado, August 1996

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE Cores" _August..Land Use

  9. Field fracturing multi-sites project. Annual report, August 1, 1995--July 31, 1996

    SciTech Connect (OSTI)

    NONE

    1996-12-31T23:59:59.000Z

    The objective of the Field Fracturing Multi-Sites Project (M-Site) is to conduct experiments to definitively determine hydraulic fracture dimensions using remote well and treatment well diagnostic techniques. In addition, experiments are to be conducted to provide data that will resolve significant unknowns with regard to hydraulic fracture modeling, fracture fluid rheology and fracture treatment design. These experiments will be supported by a well-characterized subsurface environment, as well as surface facilities and equipment conducive to acquiring high-quality data. The primary Project goal is to develop a fully characterized, tight reservoir-typical, field-scale hydraulic fracturing test site to diagnose, characterize, and test hydraulic fracturing technology and performance. It is anticipated that the research work being conducted by the multi-disciplinary team of GRI and DOE contractors will lead to the development of a commercial fracture mapping tool/service.

  10. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Durango, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    For the UMTRA Project site located near Durango, Colorado (the Durango site), the Surface Project cleanup occurred from 1986 to 1991. An evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people`s health. Exposure could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. In addition, environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has mixed with contaminated ground water. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Durango site. The results of this report and further site characterization of the Durango site will be used to determine what is necessary to protect public health and the environment, and to comply with the EPA standards.

  11. Categorical Exclusion Determinations: Lawrence Livermore Site Office |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26, 20149Department of

  12. YUCCA MOUNTAIN SITE DESCRIPTION

    SciTech Connect (OSTI)

    A.M. Simmons

    2004-04-16T23:59:59.000Z

    The ''Yucca Mountain Site Description'' summarizes, in a single document, the current state of knowledge and understanding of the natural system at Yucca Mountain. It describes the geology; geochemistry; past, present, and projected future climate; regional hydrologic system; and flow and transport within the unsaturated and saturated zones at the site. In addition, it discusses factors affecting radionuclide transport, the effect of thermal loading on the natural system, and tectonic hazards. The ''Yucca Mountain Site Description'' is broad in nature. It summarizes investigations carried out as part of the Yucca Mountain Project since 1988, but it also includes work done at the site in earlier years, as well as studies performed by others. The document has been prepared under the Office of Civilian Radioactive Waste Management quality assurance program for the Yucca Mountain Project. Yucca Mountain is located in Nye County in southern Nevada. The site lies in the north-central part of the Basin and Range physiographic province, within the northernmost subprovince commonly referred to as the Great Basin. The basin and range physiography reflects the extensional tectonic regime that has affected the region during the middle and late Cenozoic Era. Yucca Mountain was initially selected for characterization, in part, because of its thick unsaturated zone, its arid to semiarid climate, and the existence of a rock type that would support excavation of stable openings. In 1987, the United States Congress directed that Yucca Mountain be the only site characterized to evaluate its suitability for development of a geologic repository for high-level radioactive waste and spent nuclear fuel.

  13. Savannah River Site Robotics

    ScienceCinema (OSTI)

    None

    2012-06-14T23:59:59.000Z

    Meet Sandmantis and Frankie, two advanced robotic devices that are key to cleanup at Savannah River Site. Sandmantis cleans hard, residual waste off huge underground storage tanks. Frankie is equipped with unique satellite capabilities and sensing abilties that can determine what chemicals still reside in the tanks in a cost effective manner.

  14. Surveillance of Site A and Plot M report for 2010.

    SciTech Connect (OSTI)

    Golchert, N. W. (ESQ)

    2011-05-31T23:59:59.000Z

    The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for Calendar Year 2010 are presented. Based on the results of the 1976-1978 radiological characterization of the site, a determination was made that a surveillance program be established. The characterization study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current surveillance program began in 1980 and consists of sample collection and analysis of surface and subsurface water. The results of the analyses are used to monitor the migration pathway of hydrogen-3 contaminated water from the burial ground (Plot M) to the hand-pumped picnic wells and monitor for the presence of radioactive materials in the environment of the area. Hydrogen-3 in the Red Gate Woods picnic wells was still detected this year, but the average and maximum concentrations were significantly less than found earlier. Hydrogen-3 continues to be detected in a number of wells, boreholes, dolomite holes, and a surface stream. Analyses since 1984 have indicated the presence of low levels of strontium-90 in water from a number of boreholes next to Plot M. The results of the surveillance program continue to indicate that the radioactivity remaining at Site A/Plot M does not endanger the health or safety of the public visiting the site, using the picnic area, or living in the vicinity.

  15. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06T23:59:59.000Z

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

  16. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-01T23:59:59.000Z

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

  17. Site characterization: a spatial estimation approach

    SciTech Connect (OSTI)

    Candy, J.V.; Mao, N.

    1980-10-01T23:59:59.000Z

    In this report the application of spatial estimation techniques or kriging to groundwater aquifers and geological borehole data is considered. The adequacy of these techniques to reliably develop contour maps from various data sets is investigated. The estimator is developed theoretically in a simplified fashion using vector-matrix calculus. The practice of spatial estimation is discussed and the estimator is then applied to two groundwater aquifer systems and used also to investigate geological formations from borehole data. It is shown that the estimator can provide reasonable results when designed properly.

  18. Sitewide Categorical Exclusion for Site Characterization and...

    Broader source: Energy.gov (indexed) [DOE]

    would primarily be standard cable tool, auger, cone penetrometer, sonic drilling, or rotary drilling technologies. When the wells are no longer necessary, they would be...

  19. Site Characterization Awards | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energyof the Americas |DOE FormerEnergy Data Access SilverSioux

  20. Waste Sampling and Characterization Facility - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout Printable VersionProtective ActionsWasteSampling and

  1. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2M HILL Secretary MonizSite Public Tours Hanford Site

  2. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Canonsburg, Pennsylvania. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    For the UMTRA Project site located near Canonsburg, Pennsylvania (the Canonsburg site), the Surface Project cleanup occurred from 1983 to 1985, and involved removing the uranium processing mill tailings and radioactively contaminated soils and materials from their original locations and placing them in a disposal cell located on the former Canonsburg uranium mill site. This disposal cell is designed to minimize radiation emissions and further contamination of ground water beneath the site. The Ground Water Project will evaluate the nature and the extent of ground water contamination resulting from uranium processing at the former Canonsburg uranium mill site, and will determine a ground water strategy for complying with the US Environmental Protection Agency`s (EPA) ground water standards established for the UMTRA Project. For the Canonsburg site, an evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people`s health. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Canonsburg site. The results of this report and further site characterization of the Canonsburg site will be used to determine how to protect public health and the environment, and how to comply with the EPA standards.

  3. Closure Report for Corrective Action Unit 392: Spill Sites and Construction Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    R. B. Jackson

    2002-02-01T23:59:59.000Z

    This Closure Report documents the closure activities that were conducted to close Corrective Action Unit (CAU) 392--Spill Sites and Construction Materials located on the Nevada Test Site (NTS). CAU 392 is listed on in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996) and consists of the following six Corrective Action Sites (CASs) located in Areas 5 and 6 of the NTS: CAS 05-17-02 Construction Materials/Lead Bricks; CAS 06-17-03 Cement Mud Pit; CAS 06-1 9-01 Cable Pile; Powder Piles (3); CAS 06-44-02 Paint Spill; CAS 06-44-03 Plaster Spill; CAS 06-44-04 Cutting Fluid Discharge Ditch. Closure activities were performed in two phases. Phase 1 activities consisted of collecting waste characterization samples of soil and material present on-site, and where appropriate, performing radiological screening of debris at the six CASs. Results were used to determine how waste generated during closure activities would be handled and disposed of, i.e., as nonhazardous sanitary or hazardous waste, etc. Phase 2 activities consisted of closing each CAS by removing debris and/or soil, disposing of the generated waste, and verifying that each CAS was clean closed by visual inspection and/or by the collecting soil verification samples for laboratory analysis. Copies of the analytical results for the site verification samples are included in Appendix A. Copies of the Sectored Housekeeping Site Closure Verification Form for each of the six CASs are included in Appendix 8. Appendix C contains a copy of the Bechtel Nevada (BN) On-site Waste Transport Manifest for the hazardous waste generated during closure of CAS 06-44-02.

  4. Considerations for PV Site Surveys

    E-Print Network [OSTI]

    Johnson, Eric E.

    and building codes determine how a solar-electric (photovoltaic; PV) system is installed. A site survey- grid system, if solar energy is not collected, then the electrical loads may not be supported withoutConsiderations for PV Site Surveys John Wiles Sponsored by the U.S. Department of Energy this loss

  5. The conscience and the dream: an analysis of the influence of Mark Twain's determinism on characterization and thematic unity in Huckleberry Finn.

    E-Print Network [OSTI]

    Capps, Mikie Leslene

    1965-01-01T23:59:59.000Z

    Finn in Review 89 2. The Determinist in 1885 101 BIB LI 0G RAP H Y . 102 CHAPTER I INTRODUCTION The Scholars on the Development of Twain's Determinism Most Mark Twain scholars agree that sometime during the last fifteen years of his life Mark... to his master- piece. Covici, in Mark Twain's Humor: The Ima e of a World, deals more directly with Twain's determinism than Blair; however, his scope of discussion is narrow ? even more so than Bellamy's, though it 10 Walter Blair, Mark Twain...

  6. HAZARD CATEGORIZATION OF ENVIRONMENTAL RESTORATION SITES AT HANFORD WASHINGTON

    SciTech Connect (OSTI)

    BISHOP, G.E.

    2001-05-01T23:59:59.000Z

    Environmental restoration activities, defined here as work to identify and characterize contaminated sites and then contain, treat, remove or dispose of the contamination, now comprises a significant fraction of work in the DOE complex. As with any other DOE activity, a safety analysis must be in place prior to commencing restoration. The rigor and depth of this safety analysis is in part determined by the site's hazard category. This category in turn is determined by the facility's hazardous material inventory and the consequences of its release. Progressively more complicated safety analyses are needed as a facility's hazard category increases from radiological to hazard category three (significant local releases) to hazard category two (significant on-site releases). Thus, a facility's hazard category plays a crucial early role in helping to determine the level of effort devoted to analysis of the facility's individual hazards. Improper determination of the category can result in either an inadequate safety analysis in the case of underestimation of the hazard category, or an unnecessarily cumbersome analysis in the case of overestimation. Contaminated sites have been successfully categorized and safely restored or remediated at the former DOE production site at Hanford, Washington. This paper discusses various means used to categorize former plutonium production or support sites at Hanford. Both preliminary and final hazard categorization is discussed. The importance of the preliminary (initial) hazard categorization in guiding further DOE involvement and approval of the safety analyses is discussed. Compliance to DOE direction provided in ''Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports'', DOE-STD-1027-92, is discussed. DOE recently issued 10 CFR 830, Subpart B which codifies previous DOE safety analysis guidance and orders. The impact of 10 CFR 830, Subpart B on hazard categorization is also discussed.

  7. Rocky Flats Environmental Technology Site Ecological Monitoring Program 1995 annual report

    SciTech Connect (OSTI)

    NONE

    1995-05-31T23:59:59.000Z

    The Ecological Monitoring Program (ECMP) was established at the Rocky Flats Environmental Technology Site (Site) in September 1992. At that time, EcMP staff developed a Program Plan that was peer-reviewed by scientists from western universities before submittal to DOE RFFO in January 1993. The intent of the program is to measure several quantitative variables at different ecological scales in order to characterize the Rocky Flats ecosystem. This information is necessary to document ecological conditions at the Site in impacted and nonimpacted areas to determine if Site practices have had ecological impacts, either positive or negative. This information can be used by managers interested in future use scenarios and CERCLA activities. Others interested in impact analysis may also find the information useful. In addition, these measurements are entered into a database which will serve as a long-term information repository that will document long-term trends and potential future changes to the Site, both natural and anthropogenic.

  8. DETERMINATION OF IMPORTANCE EVALUATION FOR THE SURFACE EXPLORATORY STUDIES FACILITY

    SciTech Connect (OSTI)

    C.J. Byrne

    2000-07-25T23:59:59.000Z

    This DIE applies to the surface facilities component of the Yucca Mountain Site Characterization Project (W) ESF. The ESF complex-including surface and subsurface accommodations--encompasses an area that is approximately six miles wide and nine miles long (approximately 30,000 acres total) (United States Department of Energy [DOE] 1997, p. 9.04). It is located on federally withdrawn lands, near the southwest border of the Nevada Test Site (NTS) in southern Nevada (DOE 1997, p. 9.04). Site characterization activities are conducted within the subsurface ESF to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. Most ESF surface facilities are located within the Conceptual Controlled Area Boundary (CCAB) (DOE 1997, p. 9.04), with the exception of the southeastern most portions of the H-Road and the Water Supply System. Various SBT activities are also conducted throughout the Yucca Mountain region as a part of the overall site-characterization effort. In general, the DIE for SBT Activities (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 1998a) evaluates activities associated with SBT. Potential test-to-test interference and waste isolation impacts associated with SBT activities are also evaluated in CRWMS M&O (1998a).

  9. CX-005322: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    project would assist in evaluating and characterizing the site's feasibility for future wave energy conversion deployments and in the development of a proposed Federal Energy...

  10. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 3, Groundwater hydrology report: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-10-01T23:59:59.000Z

    The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR Part 192). According to the Uranium Mill Tailings Radiation Control Act of 1978, (UMTRCA) (48 CFR 590), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that this assessment shall include information on hydrogeologic site characterization. The water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards is presented in Attachment 4. Site characterization activities discussed in this attachment include the following: Characterization of the hydrogeologic environment, including hydro-stratigraphy, groundwater occurrence, aquifer parameters, and areas of recharge and discharge. Characterization of existing groundwater quality by comparison with background water quality and the maximum concentration limits (MCLs) of the proposed EPA groundwater protection standards. Definition of physical and chemical characteristics of the potential contaminant source, including concentration and leachability of the source in relation to migration in groundwater and hydraulically connected surface water. Description of local water resources, including current and future use and value, availability, and alternative supplies.

  11. Historical hydronuclear testing: Characterization and remediation technologies

    SciTech Connect (OSTI)

    Shaulis, L.; Wilson, G.; Jacobson, R.

    1997-09-01T23:59:59.000Z

    This report examines the most current literature and information available on characterization and remediation technologies that could be used on the Nevada Test Site (NTS) historical hydronuclear test areas. Historical hydronuclear tests use high explosives and a small amount of plutonium. The explosion scatters plutonium within a contained subsurface environment. There is currently a need to characterize these test areas to determine the spatial extent of plutonium in the subsurface and whether geohydrologic processes are transporting the plutonium away from the event site. Three technologies were identified to assist in the characterization of the sites. These technologies are the Pipe Explorer{trademark}, cone penetrometer, and drilling. If the characterization results indicate that remediation is needed, three remediation technologies were identified that should be appropriate, namely: capping or sealing the surface, in situ grouting, and in situ vitrification. Capping the surface would prevent vertical infiltration of water into the soil column, but would not restrict lateral movement of vadose zone water. Both the in situ grouting and vitrification techniques would attempt to immobilize the radioactive contaminants to restrict or prevent leaching of the radioactive contaminants into the groundwater. In situ grouting uses penetrometers or boreholes to inject the soil below the contaminant zone with low permeability grout. In situ vitrification melts the soil containing contaminants into a solid block. This technique would provide a significantly longer contaminant immobilization, but some research and development would be required to re-engineer existing systems for use at deep soil depths. Currently, equipment can only handle shallow depth vitrification. After existing documentation on the historical hydronuclear tests have been reviewed and the sites have been visited, more specific recommendations will be made.

  12. Characterization of a soil contaminated by oilfield brine

    SciTech Connect (OSTI)

    Al-Mutairi, K.; Harris, T. [Univ. of Tulsa, OH (United States)

    1995-12-01T23:59:59.000Z

    Brine contamination of soil is a common environmental problem associated with the onshore production of oil and gas. A site of extensive contamination in Oklahoma has been characterized using conductimetry, direct potentiometry (pH- and chloride-selective electrodes), and atomic absorption spectrophotometry (for Na{sup +} and Ca{sup 2+}) to determine the extent of the contamination and the efficacy of various remediation technologies.

  13. Value of Information Analysis Project Gnome Site, New Mexico

    SciTech Connect (OSTI)

    Greg Pohll; Jenny Chapman

    2010-01-01T23:59:59.000Z

    The Project Gnome site in southeastern New Mexico was the location of an underground nuclear detonation in 1961 and a hydrologic tracer test using radionuclides in 1963. The tracer test is recognized as having greater radionuclide migration potential than the nuclear test because the tracer test radionuclides (tritium, 90Sr, 131I, and 137Cs) are in direct contact with the Culebra Dolomite aquifer, whereas the nuclear test is within a bedded salt formation. The tracer test is the topic here. Recognizing previous analyses of the fate of the Gnome tracer test contaminants (Pohll and Pohlmann, 1996; Pohlmann and Andricevic, 1994), and the existence of a large body of relevant investigations and analyses associated with the nearby Waste Isolation Pilot Plant (WIPP) site (summarized in US DOE, 2009), the Gnome Site Characterization Work Plan (U.S. DOE, 2002) called for a Data Decision Analysis to determine whether or not additional characterization data are needed prior to evaluating existing subsurface intrusion restrictions and determining long-term monitoring for the tracer test. Specifically, the Work Plan called for the analysis to weigh the potential reduction in uncertainty from additional data collection against the cost of such field efforts.

  14. FINAL PROJECT REPORT: A Geophysical Characterization & Monitoring Strategy for Determining Hydrologic Processes in the Hyporheic Corridor at the Hanford 300-Area

    SciTech Connect (OSTI)

    Lee Slater

    2011-08-15T23:59:59.000Z

    The primary objective of this research was to advance the prediction of solute transport between the Uranium contaminated Hanford aquifer and the Columbia River at the Hanford 300 Area by improving understanding of how fluctuations in river stage, combined with subsurface heterogeneity, impart spatiotemporal complexity to solute exchange along the Columbia River corridor. Our work explored the use of continuous waterborne electrical imaging (CWEI), in conjunction with fiber-optic distributed temperature sensor (FO-DTS) and time-lapse resistivity monitoring, to improve the conceptual model for how groundwater/surface water exchange regulates uranium transport. We also investigated how resistivity and induced polarization can be used to generate spatially rich estimates of the variation in depth to the Hanford-Ringold (H-R) contact between the river and the 300 Area Integrated Field Research Challenge (IFRC) site. Inversion of the CWEI datasets (a data rich survey containing ~60,000 measurements) provided predictions of the distributions of electrical resistivity and polarizability, from which the spatial complexity of the primary hydrogeologic units along the river corridor was reconstructed. Variation in the depth to the interface between the overlying coarse-grained, high permeability Hanford Formation and the underlying finer-grained, less permeable Ringold Formation, an important contact that limits vertical migration of contaminants, has been resolved along ~3 km of the river corridor centered on the IFRC site in the Hanford 300 Area. Spatial variability in the thickness of the Hanford Formation captured in the CWEI datasets indicates that previous studies based on borehole projections and drive-point and multi-level sampling likely overestimate the contributing area for uranium exchange within the Columbia River at the Hanford 300 Area. Resistivity and induced polarization imaging between the river and the 300 Area IFRC further imaged spatial variability in the depth to the Hanford-Ringold inland over a critical region where borehole information is absent, identifying evidence for a continuous depression in the H-R contact between the IFRC and the river corridor. Strong natural contrasts in temperature and specific conductance of river water compared to groundwater at this site, along with periodic river stage fluctuations driven by dam operations, were exploited to yield new insights into the dynamics of groundwater-surface water interaction. Whereas FO-DTS datasets have provided meter-scale measurements of focused groundwater discharge at the riverbed along the corridor, continuous resistivity monitoring has non-invasively imaged spatiotemporal variation in the resistivity inland driven by river stage fluctuations. Time series and time-frequency analysis of FO-DTS and 3D resistivity datasets has provided insights into the role of forcing variables, primarily daily dam operations, in regulating the occurrence of focused exchange at the riverbed and its extension inland. High amplitudes in the DTS and 3D resistivity signals for long periods that dominate the stage time series identify regions along the corridor where stage-driven exchange is preferentially focused. Our work has demonstrated how time-series analysis of both time-lapse resistivity and DTS datasets, in conjunction with resistivity/IP imaging of lithology, can improve understanding of groundwater-surface water exchange along river corridors, offering unique opportunities to connect stage-driven groundwater discharge observed with DTS on the riverbed to stage-driven groundwater and solute fluctuations captured with resistivity inland.

  15. CX-012427: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Alaska Hydrate Production Testing: Test Site Selection and Characterization CX(s) Applied: A1, A9Date: 41879 Location(s): ColoradoOffices(s): National Energy Technology Laboratory

  16. CX-009686: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Washington River Protection Solutions LLC - Site Characterization and Environmental Monitoring CX(s) Applied: B3.1 Date: 12/14/2012 Location(s): Washington Offices(s): River Protection-Richland Operations Office

  17. Results of Detailed Hydrologic Characterization Tests - Fiscal Year 2003

    SciTech Connect (OSTI)

    Spane, Frank A.; Newcomer, Darrell R.

    2004-09-13T23:59:59.000Z

    This report presents results obtained from detailed hydrologic characterization of the unconfined aquifer system conducted at the Hanford Site.

  18. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2M HILL Secretary Moniz atfacilityrecovery Waste Site

  19. Site Map

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System Highlights Success Stories ContactSite Map

  20. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery:Act-funded KPER TV14 WhiteShimkus CongressmanSite

  1. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpgcommunity200 Wlocalplywoodroadship Shipping Mixed,sites 212R

  2. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpgcommunity200 Wlocalplywoodroadship Shipping Mixed,sites

  3. Site Map

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmitted forHighlightsSeminarsSiliconSite Map TUNL pdf's | FAS pdf's | HTML |

  4. Sacandaga Site

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28Sacandaga Site Certification tp2ket

  5. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visit EdBoard3

  6. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visit

  7. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite visitARRA

  8. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSite

  9. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSiteSubcontract for

  10. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTF PRCGrip Get aSiteSubcontract

  11. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTFIrrigationBasin Waste Site

  12. Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Bigfront.jpg Gallery: VPPDR ReactorFFTFIrrigationBasin Waste SiteReactor

  13. CX-000940: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-000940: Categorical Exclusion Determination Distributed Generation Wind Power at Navy Sites - Second Meteorological tower at Naval Station Newport, Rhode Island;...

  14. CX-001004: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-001004: Categorical Exclusion Determination West Hackberry Site Security Detection Systems Upgrade (Install) CX(s) Applied: B2.2 Date: 03032010...

  15. CX-003514: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-003514: Categorical Exclusion Determination Site Ops - Abatement Services Building 16370, 371, 269, 189, 190, 384; National Renewable Energy...

  16. CX-004834: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-004834: Categorical Exclusion Determination Scott Jenkins Parking Lot Light Emitting Diode Lighting with Solar Arrays and On?site Electric Vehicle Charging...

  17. CX-009516: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009516: Categorical Exclusion Determination Tualatin River Pipeline Crossing Site- Monitoring Well Redevelopment CX(s) Applied: B4.9 Date: 11082012...

  18. CX-009794: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009794: Categorical Exclusion Determination Strategic Petroleum Reserve Site Subsidence Surveys, 2013-2017 CX(s) Applied: B3.1 Date: 01022013...

  19. CX-004173: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination CX-004173: Categorical Exclusion Determination Steam Reforming Treatability Study with Savannah River Site Low Activity Waste (LAW) (Module...

  20. Intraseasonal characterization of tropospheric O3 in the North of the Buenos Aires Province: determining four months cycle and teleconnection evidence

    E-Print Network [OSTI]

    Cionco, Rodolfo G; Quaranta, Nancy; Agosta, Eduardo

    2013-01-01T23:59:59.000Z

    Tropospheric ozone (O3T) is a secondary pollutant whose formation involved primarily solar radiation, NOx and volatile organic compounds. The North of the Buenos Aires Province has great agricultural-industrial activity; therefore, O3T study is an important issue in the area. In this paper, we present the first results tend to estimate and characterize O3T in San Nicol\\'as de los Arroyos, North of Buenos Aires. Due to a lack of in situ data, we analyse the observations of the instrument OMI (Ozone Monitoring Instrument) of land remote sensing satellite AURA (GSFC/NASA). The data cover the years 2004-2013. Applying the multitaper technique (MTM), very suitable for short and noisy data series, spectral analysis is performed on a grid corresponding 1{\\deg} in latitude by 1.5{\\deg} in longitude, centred South of the Province of Santa Fe. The most remarkable result is the emergence of a significant peak (95%) of four months cycle. To test the validity of this signal in San Nicol\\'as, daily solar radiation data (Q)...

  1. Feasibility study for underground coal gasification at the Krabi Coal Mine site, Thailand. Final report

    SciTech Connect (OSTI)

    Boysen, J.; Sole, J.; Schmit, C.R.; Harju, J.A.; Young, B.C.

    1997-01-01T23:59:59.000Z

    This study, conducted by Energy and Environmental Research Center, was funded by the U.S Trade and Development Agency. The report summarizes the accomplishments of field, analytical data evaluation and modeling activities focused on assessment of underground coal gasification (UCG) feasibility at Krabi over a two year period. The overall objective of the project was to determine the technical issues, environmental impact, and economic of developing and commercializing UCG at the site in Krabi. The report contains an Executive Summary followed by these chapters: (1) Project Overview; (2) Project Site Characterization; (3) Inorganic and Thermal Materials Characterization; (4) Technical and Economic Feasibility of UCG At the Krabi Site; (5) Conclusions and Recommendations; (6) Acknowledgments; (7) References.

  2. Planning a site investigation using analogous groups

    SciTech Connect (OSTI)

    Pak, P.M. [USDOE Richland Operations Office, WA (United States); Galgoul, M.J.; Wittreich, C.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-09-01T23:59:59.000Z

    A limited field investigation (LFI) has been designed for the 200-UP-2 Operable Unit within the 200 Areas of the US Department of Energy (DOE) Hanford Site in Washington state using the concept of analogous groups. The LFI is part of a RCRA facility investigation (RFI) corrective measures study (CMS) being conducted in this operable unit. The concept emphasizes that characterization activities can be reduced by identifying select sites (analogous sites) for characterization that represents a group of sites (analogous groups). This concept is particularly applicable to operable units that contain several waste management units that are similar in design, disposal history, and geology. Application of this concept reduced the number of waste management units initially undergoing characterization by more than two-thirds. The work plan is presently in the approval cycle with the field characterization phase expected to begin August 1993.

  3. PUNCTURE TEST CHARACTERIZATION OF GLOVEBOX GLOVES

    SciTech Connect (OSTI)

    Korinko, P.; Chapman, G.

    2012-02-29T23:59:59.000Z

    An experiment was conducted to determine the puncture resistance of 15 gloves that are used or proposed for use in the Tritium Facility at Savannah River Site (SRS). These data will serve as a baseline for characterization and may be incorporated into the glove procurement specification. The testing was conducted in agreement with ASTM D120 and all of the gloves met or exceeded the minimum requirements. Butyl gloves exhibited puncture resistance nearly 2.5 times the minimum requirements at SRS while Polyurethane was nearly 7.5x the minimum.

  4. Defect site prediction based upon statistical analysis of fault signatures

    E-Print Network [OSTI]

    Trinka, Michael Robert

    2004-09-30T23:59:59.000Z

    Good failure analysis is the ability to determine the site of a circuit defect quickly and accurately. We propose a method for defect site prediction that is based on a site's probability of excitation, making no assumptions about the type...

  5. CX-005708: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-005708: Categorical Exclusion Determination Phase 3 - Seismic Fracture Characterization Methodologies for Enhanced Geothermal Systems CX(s) Applied: A9,...

  6. CX-003495: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-003495: Categorical Exclusion Determination Seismic Fracture Characterization Methodologies for Enhanced Geothermal Systems CX(s) Applied: A9,...

  7. CX-009327: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009327: Categorical Exclusion Determination Gas Hydrate Dynamics on the Alaskan Beaufort Continental Slope: Modeling and Field Characterization CX(s)...

  8. CX-009329: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009329: Categorical Exclusion Determination Gas Hydrate Dynamics on the Alaskan Beaufort Continental Slope: Modeling and Field Characterization CX(s)...

  9. CX-009330: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009330: Categorical Exclusion Determination Gas Hydrate Dynamics on the Alaskan Beaufort Continental Slope: Modeling and Field Characterization CX(s)...

  10. CX-009328: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination CX-009328: Categorical Exclusion Determination Gas Hydrate Dynamics on the Alaskan Beaufort Continental Slope: Modeling and Field Characterization CX(s)...

  11. CX-002474: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Full Scale Testing Characterization, System Optimization, Demonstration of Grid Connected Wind Turbines and Wind Powered Water Desalination...

  12. Geothermal: Sponsored by OSTI -- Fracture Characterization in...

    Office of Scientific and Technical Information (OSTI)

    Fracture Characterization in Enhanced Geothermal Systems by Wellbore and Reservoir Analysis Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us | Admin Log...

  13. A Multiattribute Utility Analysis of Sites Nominated For Characterizat...

    Broader source: Energy.gov (indexed) [DOE]

    A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository - A Decision Aiding Methodology A Multiattribute Utility...

  14. CX-006598: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Site Characterization, Monitoring, and General Research Activities, Fiscal Year 2012-2013CX(s) Applied: B3.1, B3.6, B3.8Date: 08/23/2011Location(s): Amarillo, TexasOffice(s): NNSA-Headquarters, Pantex Site Office

  15. Nest site selection and partitioning among sympatric white-winged, mourning, and Inca doves in Mason, Texas

    E-Print Network [OSTI]

    Mathewson, Heather Alexis

    2002-01-01T23:59:59.000Z

    ; and (3) compare nest-site characteristics, nest-site partitioning, and assess the role of interspecific competition on nest-site selection. Nest searching, monitoring, nest-site characterizations, and vegetation measurements were conducted during June...

  16. Site environmental report for calendar year 1996: Yucca Mountain site, Nye County, Nevada

    SciTech Connect (OSTI)

    NONE

    1997-11-01T23:59:59.000Z

    The environmental program established by the Yucca Mountain Site Characterization Office (YMSCO) has been designed and implemented to protect, maintain, and restore environmental quality, minimize potential threats to the environment and the public, and comply with environmental policies and US Department of Energy (DOE) Orders. In accordance with DOE Order 5400.1, General Environmental Protection Program (DOE, 1990a), to be superseded by DOE Order 231.1 (under review), the status of the Yucca Mountain Site Characterization Project (YMP) environmental program has been summarized in this annual Site Environmental Report (SER) to characterize performance, document compliance with environmental requirements, and highlight significant programs and efforts during calendar year 1996.

  17. Site Monitoring Area Maps

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to the Site Monitoring Area (SMA) The Site Monitoring Area sampler Control measures (best management practices) installed at the Site Monitoring Area Structures such as...

  18. Baseline risk assessment of groundwater contamination at the uranium mill tailings site, near Gunnison, Colorado. Revision 2

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    This report is the second site-specific risk assessment document prepared for the Ground Water Project at the Gunnison site. A preliminary risk assessment was conducted in 1990 to determine whether long-term use of ground water from private wells near the Gunnison site had the potential for adverse health effects. Due to the results of that preliminary risk assessment, the residents were provided bottled water on an interim basis. In July 1994, the residents and the nearby Valco cement/concrete plant were given the option to connect to anew alternate water supply system, eliminating the bottled water option. This document evaluates current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether more action is needed to protect human health and the environment and to comply with the EPA standards.

  19. Development of the INEEL Site Wide Vadose Zone Roadmap

    SciTech Connect (OSTI)

    Yonk, Alan Keith

    2001-09-01T23:59:59.000Z

    The INEEL Vadose Zone Roadmap was developed to identify inadquacies in current knowledge, to assist in contaminant management capabilities relative to the INEEL vadose zone, and to ensure that ongoing and planned Science and Technology developments will meet the risk management challenges facing the INEEL in coming years. The primary objective of the Roadmap is to determine the S&T needs that will facilitate monitoring, characterization, prediction, and assessment activities necessary to support INEEL risk management decisions and to ensure that long-term stewardship of contaminated sites at the INEEL is achieved. The mission of the Roadmap is to insure that the long-term S&T strategy is aligned with site programs, that it takes advantage of progress made to date, and that it can assist in meeting the milestones and budgets of operations.

  20. Expedited Site Characterization Geophysics: Geophysical Methods and Tools for Site Characterization

    E-Print Network [OSTI]

    Goldstein, N.E.

    2009-01-01T23:59:59.000Z

    total system control. Non-volatile configuration parameters, and automatic configuration maximize data quality,

  1. Expedited Site Characterization Geophysics: Geophysical Methods and Tools for Site Characterization

    E-Print Network [OSTI]

    Goldstein, N.E.

    2009-01-01T23:59:59.000Z

    APPLICATIONS Gamma-ray spectrometry is a tool for geologicGAMMA-RAY SPECTROMETRY .Seismic reflection • Gamma-ray • Metal-specific spectrometry

  2. 2011 ANNUAL SITE ENVIRONMENTAL REPORT

    SciTech Connect (OSTI)

    Meyer, A.; Eddy, T.; Jannik, T.; Terry, B.; Cauthen, K.; Coward, L.; Dunaway-Ackerman, J.; Wilson, M.; Hutchison, J.; O'Quinn, S.

    2012-10-01T23:59:59.000Z

    The Savannah River Site Environmental Report for 2011 (SRNS-STI-2012-00200) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1 B, “Environment, Safety and Health Reporting." The annual SRS Environmental Report has been produced for more than 50 years. Several hundred copies are and interested individuals. The report’s purpose is to: present summary environmental data that characterize site environmental management performance; describe compliance status with respect to environmental standards and requirements; highlight significant programs and efforts.

  3. Tank characterization reference guide

    SciTech Connect (OSTI)

    De Lorenzo, D.S.; DiCenso, A.T.; Hiller, D.B.; Johnson, K.W.; Rutherford, J.H.; Smith, D.J. [Los Alamos Technical Associates, Kennewick, WA (United States); Simpson, B.C. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-09-01T23:59:59.000Z

    Characterization of the Hanford Site high-level waste storage tanks supports safety issue resolution; operations and maintenance requirements; and retrieval, pretreatment, vitrification, and disposal technology development. Technical, historical, and programmatic information about the waste tanks is often scattered among many sources, if it is documented at all. This Tank Characterization Reference Guide, therefore, serves as a common location for much of the generic tank information that is otherwise contained in many documents. The report is intended to be an introduction to the issues and history surrounding the generation, storage, and management of the liquid process wastes, and a presentation of the sampling, analysis, and modeling activities that support the current waste characterization. This report should provide a basis upon which those unfamiliar with the Hanford Site tank farms can start their research.

  4. Site Analysis Shadow Analysis Site Objectives

    E-Print Network [OSTI]

    Kyte, Michael

    On ­ Site Rainwater Collection o Composting Toilets o Green Roof o Indigenous Landscape - Wetlands Building

  5. Proposed Changes to EPA's Transuranic Waste Characterization Approval Process

    SciTech Connect (OSTI)

    Joglekar. R. D.; Feltcorn, E. M.; Ortiz, A. M.

    2003-02-25T23:59:59.000Z

    This paper describes the changes to the waste characterization (WC) approval process proposed in August 2002 by the U.S. Environmental Protection Agency (EPA or the Agency or we). EPA regulates the disposal of transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) repository in Carlsbad, New Mexico. EPA regulations require that waste generator/storage sites seek EPA approval of WC processes used to characterize TRU waste destined for disposal at WIPP. The regulations also require that EPA verify, through site inspections, characterization of each waste stream or group of waste streams proposed for disposal at the WIPP. As part of verification, the Agency inspects equipment, procedures, and interviews personnel to determine if the processes used by a site can adequately characterize the waste in order to meet the waste acceptance criteria for WIPP. The paper discusses EPA's mandate, current regulations, inspection experience, and proposed changes. We expect that th e proposed changes will provide equivalent or improved oversight. Also, they would give EPA greater flexibility in scheduling and conducting inspections, and should clarify the regulatory process of inspections for both Department of Energy (DOE) and the public.

  6. Health assessment for Fadrowski Drum Disposal Site, Franklin, Wisconsin, Region 5. CERCLIS No. WID980901227. Preliminary report

    SciTech Connect (OSTI)

    Not Available

    1989-06-06T23:59:59.000Z

    The Fadrowski Drum Disposal Site is listed on the National Priorities List. Virtually no testing has been conducted at the Fadrowski site. Site characterization was only beginning at the time of the site visit. The only testing that had been done was of the contents of drums uncovered during excavations involved in construction. Samples of the contents of the drums - sludges, oily water, and paint waste - showed concentrations of lead (400 - 32,700 ppm), chromium (< 100 - 6,800 ppm), DDT (p.p. DDT - 1,000 ppm; o.p. DDT - 450 ppm), and petroleum distillates. The uncovered wastes were re-covered with clay. At that time, the presence of hazardous materials on site was verified, but the extent and limits of contamination were not and have not yet been determined.

  7. CORRECTIVE ACTION PLAN FOR CORRECTIVE ACTION UNIT 536: AREA 3 RELEASE SITE, NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    NONE

    2005-09-01T23:59:59.000Z

    CAU 536 consists of CAS 03-44-02, Steam Jenny Discharge, located in Area 3 of the NTS. The site was characterized in 2004 according to the approved CAIP and the site characterization results are reported in the CAU 536 CADD. The purpose of this Corrective Action Plan (CAP) is to provide the detailed scope of work required to implement the recommended corrective actions as specified in the approved CAU 536 CADD.

  8. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Green River, Utah. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase 1) and the Ground Water Project (phase 2). For the UMTRA Project site located near Green River, Utah, the Surface Project cleanup occurred from 1988 to 1989. The tailings and radioactively contaminated soils and materials were removed from their original locations and placed into a disposal cell on the site. The disposal cell is designed to minimize radiation emissions and minimize further contamination of ground water beneath the site. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. For the Green River site, the risk assessment helps determine whether human health risks result from exposure to ground water contaminated by uranium processing. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Green River site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.

  9. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Salt Lake City, Utah. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the first is the Surface Project, and the second is the Ground Water Project. For the UMTRA Project site known as the Vitro site, near Salt Lake City, Utah, Surface Project cleanup occurred from 1985 to 1987. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. A risk assessment is the process of describing a source of contamination and showing how that contamination may reach people and the environment. The amount of contamination people or the environment may be exposed to is calculated and used to characterize the possible health or environmental effects that may result from this exposure. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Vitro site. The results of this report and further site characterization of the Vitro site will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.

  10. Human Health and Ecological Risk Assessment Work Plan Mud Pit Release Sites, Amchitka Island, Alaska

    SciTech Connect (OSTI)

    DOE /NV

    2001-03-12T23:59:59.000Z

    This Work Plan describes the approach that will be used to conduct human health and ecological risk assessments for Amchitka Island, Alaska, which was utilized as an underground nuclear test site between 1965 and 1971. During this period, the U.S. Atomic Energy Commission (now the U.S. Department of Energy) conducted two nuclear tests (known as Long Shot and Milrow) and assisted the U.S. Department of Defense with a third test (known as Cannikin). Amchitka Island is approximately 42 miles long and located 1,340 miles west-southwest of Anchorage, Alaska, in the western end of the Aleutian Island archipelago in a group of islands known as the Rat Islands. Historically including deep drilling operations required large volumes of drilling mud, a considerable amount of which was left on the island in exposed mud pits after testing was completed. Therefore, there is a need for drilling mud pit remediation and risk assessment of historical mud pit releases. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the constituents in soil, surface water, and sediment at these former testing sites. Its goal is the collection of data in sufficient quantity and quality to determine current site conditions, support a risk assessment for the site surfaces, and evaluate what further remedial action is required to achieve permanent closure of these three sites that will protect both human health and the environment. Suspected compounds of potential ecological concern for investigative analysis at these sites include diesel-range organics, polyaromatic hydrocarbons, polychlorinated biphenyls, volatile organic compounds, and chromium. The results of these characterizations and risk assessments will be used to evaluate corrective action alternatives to include no further action, the implementation of institutional controls, capping on site, or off-sit e disposal of contaminated waste. The results of this evaluation will be presented in a subsequent corrective action decision document.

  11. Middlesex FUSRAP Site - A Path to Site-Wide Closure - 13416

    SciTech Connect (OSTI)

    Miller, David M. [ECC, 110 Fieldcrest Ave, Ste 31, Edison, NJ, 08837 (United States)] [ECC, 110 Fieldcrest Ave, Ste 31, Edison, NJ, 08837 (United States); Edge, Helen [US Army Corps of Engineers - NYD, 26 Federal Plaza, Room 1811, New York, NY, 10278 (United States)] [US Army Corps of Engineers - NYD, 26 Federal Plaza, Room 1811, New York, NY, 10278 (United States)

    2013-07-01T23:59:59.000Z

    The road-map to obtaining closure of the Middlesex Sampling Plant FUSRAP site in Middlesex, New Jersey (NJ) has required a multi-faceted approach, following the CERCLA Process. Since 1998, the US ACE, ECC, and other contractors have completed much of the work required for regulatory acceptance of site closure with unrestricted use. To date, three buildings have been decontaminated, demolished, and disposed of. Two interim storage piles have been removed and disposed of, followed by the additional removal and disposal of over 87,000 tons of radiologically and chemically-impacted subsurface soils by the summer of 2008. The US ACE received a determination from the EPA for the soils Operable Unit, (OU)-1, in September 2010 that the remedial excavations were acceptable, and meet the criteria for unrestricted use as required by the 2004 Record of Decision (ROD) for OU-1. Following the completion of OU-1, the project delivery team performed additional field investigation of the final Operable Unit for Middlesex, OU-2, Groundwater. As of December 2012, the project delivery team has completed a Supplemental Remedial Investigation, which will be followed with a streamlined Feasibility Study, Proposed Plan, and ROD. Several years of historical groundwater data was available from previous investigations and the FUSRAP Environmental Surveillance Program. Historical data indicated sporadic detections of Volatile Organic Compounds (VOCs), primarily trichloroethylene (TCE), carbon tetrachloride (CT), and methyl tert-butyl ether (MTBE), with no apparent trend or pattern indicating extent or source of the VOC impact. In 2008, the project delivery team initiated efforts to re-assess the Conceptual Site Model (CSM) for groundwater. The bedrock was re-evaluated as a leaky multi-unit aquifer, and a plan was developed for additional investigations for adequate bedrock characterization and delineation of groundwater contaminated primarily by CT, TCE, and tetrachloroethene (PCE). The investigation was designed to accumulate multiple lines of evidence to determine the source and to delineate the extent of contamination, as required to complete the CERCLA Process and gain regulatory acceptance. Investigative techniques included in-well vertical flow tracing, borehole geophysics and packer testing of temporary test holes to characterize contamination in the bedrock fractures beneath the site, and to delineate likely source areas. (authors)

  12. Nevada National Security Site Industrial Sites Project Closeout - 12498

    SciTech Connect (OSTI)

    Cabble, Kevin [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Las Vegas, Nevada 89193 (United States); Krauss, Mark [S.M. Stoller for Navarro-Intera, LLC, Las Vegas, Nevada 89193 (United States); Matthews, Pat [Navarro-Intera, LLC, Las Vegas, Nevada 8919 (United States)

    2012-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office is responsible for environmental restoration (ER) at the Nevada National Security Site (NNSS). This includes remediation at Industrial Sites where past nuclear testing activities and activities that supported nuclear testing may have or are known to have resulted in the release of contaminants into the environment. Industrial Sites at the NNSS have included nuclear facilities that supported the nuclear rocket/missile development programs, gas stations, landfills, spill sites, ordnance sites, and numerous other waste disposal and release sites. The NNSS Industrial Sites activities neared completion at the end of fiscal year 2011 while other activities required under the Federal Facility Agreement and Consent Order (FFACO) and part of the same NNSS ER Project are forecasted to extend to 2027 or beyond. With the majority of Industrial Sites corrective action units (CAUs) completed (more than 250 CAUs and over 1,800 corrective action sites), it was determined that an activity closeout process should be implemented to ensure that the work completed over the past 15 years is well documented in a comprehensive and concise summary. While the process used to close each individual CAU is described in approved documents, no single document describes in summary fashion the work completed to close the many individual Industrial Sites. The activity closeout process will be used to develop an Industrial Sites closeout document that describes these years of work. This document will summarize the number of Industrial Sites closed under the FFACO and provide general descriptions of projects, contaminants removed, and sites closed in place with corresponding Use Restrictions. Other pertinent information related to Industrial Sites work such as the project history, closure decisions, historical declarations, remediation strategies, and final CAU status will be included in the closeout document, along with a table listing each CAU and corresponding corrective action sites within each CAU. Using this process of conducting the activity closeout and developing a closeout document may prove useful for other ER projects within the DOE complex in describing how a long period of ER can be summarized in a single document. The NNSS Industrial Sites activities were completed over the span of 15 years and involved the investigation, cleanup or Use Restriction, and closure of more than 260 CAUs and over 1,800 sites. These activities will conclude in FY 2012 (with the exception of one CAU). In order to capture the work completed over this length of time and document decisions made during the activities, a closeout effort was initiated. The closeout will review the work conducted during the Industrial Sites activities and produce a single document that summarizes Industrial Sites activities. This closeout is being conducted at an interim stage in the overall NNSA/NSO ER Project since the Soils and UGTA activities will continue for a number of years, but the completion of the Industrial Sites project warrants conducting a closeout now while personnel are available and information is still current. The process followed by NNSA/NSO in conducing project closeout for the Industrial Sites portion of the ER program may prove useful within the DOE complex in demonstrating how a large ER project can be summarized. (authors)

  13. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-07-01T23:59:59.000Z

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  14. Salt site performance assessment activities

    SciTech Connect (OSTI)

    Kircher, J.F.; Gupta, S.K.

    1983-01-01T23:59:59.000Z

    During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables.

  15. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

    SciTech Connect (OSTI)

    Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

    2012-02-26T23:59:59.000Z

    The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: ? Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. ? DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. ? DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators.

  16. CX-011224: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination Replacement of Deep-Anode Ground Bed Sites for Big Hill Cavern 104 and Site Unit 1 "A", and BC Cavern 18 CX(s) Applied: B1.3 Date: 10012013...

  17. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Naturita, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase I), and the Ground Water Project (phase II). For the UMTRA Project site located near Naturita, Colorado (the Naturita site), phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado, about 13 road miles (mi) (21 kilometers [km]) to the northwest. No uranium mill tailings are involved because the tailings were removed from the Naturita site and placed at Coke Oven, Colorado, during 1977 to 1979. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health or the environment; and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has received contaminated ground water. Therefore, a risk assessment is conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.

  18. SUBCONTRACTOR SITE ACCESS GUIDELINES

    E-Print Network [OSTI]

    Eisen, Michael

    .............................................................. 5 5. Projects with Off-site Parking Arrangements.................................................................................6 5.1 Initial Screening and Off-site Parking Process................................................................. 9 7.2 Substitute Contractors with Off-site Parking

  19. Site study plan for Transportation, Deaf Smith County Site, Texas: Preliminary draft

    SciTech Connect (OSTI)

    Not Available

    1987-06-01T23:59:59.000Z

    This site study plan describes transportation field studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. The studies are needed to identify and assess potential project impacts to transportation infrastructure and systems in the project vicinity and along potential transportation routes to the site across the State of Texas. The studies are also needed to locate and design project transportation facilities, and to evaluate and design impact mitigation. After identifying the transportation information requirements needed to comply with Federal, State, and local regulations and repository program requirements, the site study plan describes the study design and rationale, the field data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs for the characterization of site vicinity rail corridors and highway corridors, characterization of alternative statewide transportation routes, monitoring of site characterization effects on transportation, characterization of aircraft overflight patterns and hazardous material transportation patterns, and assessment of emergency response preparedness along alternative statewide transportation routes. 34 refs., 10 figs., 2 tabs.

  20. Isolation, Characterization of an Intermediate in an Oxygen Atom...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Characterization of an Intermediate in an Oxygen Atom-Transfer Reaction, and the Determination of the Bond Isolation, Characterization of an Intermediate in an Oxygen Atom-Transfer...

  1. Hanford Site Development Plan

    SciTech Connect (OSTI)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

    1990-01-01T23:59:59.000Z

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

  2. Fiscal year 1992 report on archaeological surveys of the 100 Areas, Hanford Site, Washington

    SciTech Connect (OSTI)

    Wright, M.K.

    1993-09-01T23:59:59.000Z

    During FY 1992, the Hanford Cultural Resources Laboratory (HCRL) conducted a field survey of the 100-HR-3 Operable Unit (600 Area) and tested three sites near the 100 Area reactor compounds on the US Department of Energy`s Hanford Site at the request of Westinghouse Hanford Company. These efforts were conducted in compliance with Section 106 of the National Historic Preservation Act (NHPA) and are part of a cultural resources review of 100 Area Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) operable units in support of CERCLA characterization studies.The results of the FY 1992 survey and test excavation efforts are discussed in this report. 518 ha in the 100-HR-3 Operable Unit and conducted test excavations at three prehistoric sites near the 100-F and 100-K reactors to determine their eligibility for listing on the National Register of Historic Places.

  3. Hanford site transuranic waste sampling plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-13T23:59:59.000Z

    This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed.

  4. Lawrence Berkeley Laboratory 1993 Site Environmental Report

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    This annual Site Environmental Report summarizes Lawrence Berkeley Laboratory`s (LBL`s) environmental activities in calendar year (CY) 1993. The purpose of this report is to characterize site environmental management performance, confirm compliance status with environmental standards and requirements, and highlight significant programs and efforts. Its format and content are consistent with the requirements of the US Department of Energy (DOE) Order 5400.1, General Environmental Protection Program.

  5. Comment and response document for the ground water protection strategy for the Uranium Mill Tailings Site at Green River, Utah

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The US Department of Energy (DOE) responses to comments from both the US Nuclear Regulatory Commission (NRC) and the state of Utah are provided in this document. The Proposed Ground Water Protection Strategy for the Uranium Mill Tailings Site at Green River, Utah, presents the proposed (modified) ground water protection strategy for the disposal cell at the Green River disposal site for compliance with Subpart A of 40 CFR Part 192. Before the disposal cell was constructed, site characterization was conducted at the Green River Uranium Mill Tailings Remedial Action (UMTRA) Project site to determine an acceptable compliance strategy. Results of the investigation are reported in detail in the final remedial action plan (RAP) (DOE, 1991a). The NRC and the state of Utah have accepted the final RAP. The changes in this document relate only to a modification of the compliance strategy for ground water protection.

  6. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect (OSTI)

    Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

    2012-11-12T23:59:59.000Z

    Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1 considerations. This DQO report also updates the discussion of the Environmental Monitoring Plan for the PNNL Site air samples and how existing Hanford Site monitoring program results could be used. This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs.

  7. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 2: Appendix A -- Waste sites, source terms, and waste inventory report; Appendix B -- Description of the field activities and report database; Appendix C -- Characterization of hydrogeologic setting report

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix A includes descriptions of waste areas and estimates of the current compositions of the wastes. Appendix B contains an extensive database of environmental data for the Bear Creek Valley Characterization Area. Information is also presented about the number and location of samples collected, the analytes examined, and the extent of data validation. Appendix C describes the hydrogeologic conceptual model for Bear Creek Valley. This model is one of the principal components of the conceptual site models for contaminant transport in BCV.

  8. St. Louis Sites Fact Sheet RISK ASSESSMENT

    E-Print Network [OSTI]

    US Army Corps of Engineers

    -3905 or write to the St. Louis District, Corps of Engineers, FUSRAP Project Office, 8945 Latty Avenue, BerkeleySt. Louis Sites Fact Sheet RISK ASSESSMENT "Gateway to Excellence" U.S. Army Corps of Engineers St. Together, they help determine the most effective way to clean up a site while reducing the overall risk

  9. CX-000471: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-000471: Categorical Exclusion Determination Limited Prescribed Burning on the Hanford Site During October, November, and December of 2010 to Maintain Critical Fire...

  10. CX-004182: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Wackenhut Services, Incorporated-Savannah River Site Range 3 Modifications and Live Fire Shoot House Expansion at the Bobby Davis...

  11. CX-004180: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Three Wackenhut Services, Incorporated-Savannah River Site Infrastructure Improvement Projects in B-Area CX(s) Applied: B1.15 Date: 0923...

  12. ENVIRONMENTAL REVIEW FOR CATEGORICAL EXCLUSION DETERMINATION

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    sites outside of rights-of-way in nearby previously disturbed or developed areas. 1 ENVIRONMENTAL REVIEW FOR CATEGORICAL EXCLUSION DETERMINATION Rocky Mountain Region, Western Area...

  13. CX-001597: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination Recovery Act: Direct Confirmation of Commercial Geothermal Resources in Colorado Using Remote Sensing and On-Site Exploration, Testing and Analysis CX(s) Applied: A9...

  14. PROBABILISTIC SITE IDENTIFICATION ANALYSIS USING NUPEC RECORDED FREE FIELD MOTIONS.

    SciTech Connect (OSTI)

    XU,J.; COSTANTINO,C.; HOFMAYER,C.; MURPHY,A.; KITADA,Y.

    2002-08-04T23:59:59.000Z

    THIS PAPER DESCRIBES A PROBABILISTIC SITE IDENTIFICATION ANALYSIS PERFORMED BY BNL, USING THE FREE FIELD EARTHQUAKE MOTIONS RECORDED AT THE NUPEC TEST SITE. THE BNL ANALYSIS WAS INTENDED TO PROVIDE ADEQUATE CHARACTERIZATION OF THE SOIL PROPERTIES FOR THE TEST SITE TO BE USED FOR SSI ANALYSES. THE FREE FIELD DATA WERE PROVIDED BY NUPEC. THE METHODOLOGY EMPLOYED IN THE BNL PROBABILISTIC ANALYSIS OF SITE IDENTIFICATION INCLUDES THE MONTE CARLO PR...

  15. Technical guidance for siting criteria development

    SciTech Connect (OSTI)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01T23:59:59.000Z

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  16. Collector/Receiver Characterization (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2010-08-01T23:59:59.000Z

    Fact sheet describing NREL CSP Program capabilities for collector/receiver characterization: determining optical efficiency, measuring heat loss, developing and testing concentrators, concentrating the sun's power, and optically characterizing CSP plants.

  17. Vegetation communities associated with the 100-Area and 200-Area facilities on the Hanford Site

    SciTech Connect (OSTI)

    Stegen, J.A.

    1994-01-17T23:59:59.000Z

    The Hanford Site, Benton County, Washington, lies within the broad semi-arid shrub-steppe vegetation zone of the Columbia Basin. Thirteen different habitat types on the Hanford Site have been mapped in Habitat Types on the Hanford Site: Wildlife and Plant Species of Concern (Downs et al. 1993). In a broad sense, this classification is correct. On a smaller scale, however, finer delineations are possible. This study was conducted to determine the plant communities and estimate vegetation cover in and directly adjacent to the 100 and 200 Areas, primarily in relation to waste sites, as part of a comprehensive ecological study for the Compensation Environmental Response, Compensation, and Liability Act (CERCLA) characterization of the 100 and 200 Areas. During the summer of 1993, field surveys were conducted and a map of vegetation communities in each area, including dominant species associations, was produced. The field surveys consisted of qualitative community delineations. The community delineations described were made by field reconnaissance and are qualitative in nature. The delineations were made by visually determining the dominant plant species or vegetation types and were based on the species most apparent at the time of inspection. Additionally, 38 transects were run in these plant communities to try to obtain a more accurate representation of the community. Because habitat disturbances from construction/operations activities continue to occur in these areas, users of this information should be cautious in applying these maps without a current ground survey. This work will complement large-scale habitat maps of the Hanford Site.

  18. CX-005689: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Exclusion Determination Joint Inversion of Electrical and Seismic Data for Fracture Characterization and Imaging of Fluid Flow in Geothermal Systems CX(s) Applied: A9,...

  19. CX-001057: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    new wells. The project will also focus on determining the location of the fractures, fracture spacing and orientation during drilling as well as characterizing open fractures...

  20. CX-009465: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Temporal Characterization of Hydrates System Dynamics Beneath Seafloor Mounds: Integrating Time-Lapse CX(s) Applied: B3.6 Date: 10182012...

  1. CX-009462: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Temporal Characterization of Hydrates System Dynamics Beneath Seafloor Mounds: Integrating Time-Lapse CX(s) Applied: A9, A11 Date: 1018...

  2. CX-009463: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Temporal Characterization of Hydrates System Dynamics Beneath Seafloor Mounds: Integrating Time-Lapse CX(s) Applied: B3.6 Date: 10182012...

  3. CX-009464: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Categorical Exclusion Determination Temporal Characterization of Hydrates System Dynamics beneath Seafloor Mounds: Integrating Time-Lapse CX(s) Applied: A9, A11 Date: 1018...

  4. CX-002604: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-002604: Categorical Exclusion Determination Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region CX(s)...

  5. CX-002605: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-002605: Categorical Exclusion Determination Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region CX(s)...

  6. CX-000413: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-000413: Categorical Exclusion Determination Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region CX(s)...

  7. CX-000416: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-000416: Categorical Exclusion Determination Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region CX(s)...

  8. CX-000415: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    CX-000415: Categorical Exclusion Determination Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region CX(s)...

  9. CX-000579: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Site Characterization for Strategically Hardened Facility Defeat Project (Socorro, New Mexico) CX(s) Applied: B3.1 Date: 12042009 Location(s): Socorro, New Mexico Office(s):...

  10. Closure Report for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-09-01T23:59:59.000Z

    Corrective Action Unit (CAU) 121 is identified in the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008) as Storage Tanks and Miscellaneous Sites. CAU 121 consists of the following three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada: (1) CAS 12-01-01, Aboveground Storage Tank; (2) CAS 12-01-02, Aboveground Storage Tank; and (3) CAS 12-22-26, Drums; 2 AST's. CAU 121 closure activities were conducted according to the FFACO and the Streamlined Approach for Environmental Restoration Plan for CAU 121 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007). Field work took place from February through September 2008. Samples were collected to determine the path forward to close each site. Closure activities were completed as defined in the plan based on sample analytical results and site conditions. No contaminants of concern (COCs) were present at CAS 12-01-01; therefore, no further action was chosen as the corrective action alternative. As a best management practice (BMP), the empty aboveground storage tank (AST) was removed and disposed as sanitary waste. At CAS 12-01-02, polychlorinated biphenyls (PCBs) were present above the preliminary action level (PAL) in the soil beneath the AST that could possibly have originated from the AST contents. Therefore, PCBs were considered COCs, and the site was clean closed by excavating and disposing of soil containing PCBs. Approximately 5 cubic yards (yd{sup 3}) of soil were excavated and disposed as petroleum hydrocarbon PCB remediation waste, and approximately 13 yd3 of soil were excavated and disposed as PCB remediation waste. Cleanup samples were collected to confirm that the remaining soil did not contain PCBs above the PAL. Other compounds detected in the soil above PALs (i.e., total petroleum hydrocarbons [TPH] and semi-volatile organic compounds [SVOCs]) were determined to not likely have originated from the tank. Additional sample results showed that the compounds were likely present as a result of degraded asphalt around the adjacent, active water tank and not from the abandoned AST; therefore, they were not considered COCs. As a BMP, the empty AST was removed and disposed as sanitary waste. No COCs were present at CAS 12-22-26; therefore, no further action was chosen as the corrective action alternative. Although TPH was present at concentrations that exceeded the PAL, the volatile organic compound and SVOC hazardous constituents of TPH did not exceed the final action levels (FALs); therefore, TPH was not considered a COC. As a BMP, the empty AST was removed and disposed as sanitary waste. Closure activities generated sanitary waste, petroleum hydrocarbon PCB remediation waste, PCB remediation waste, and hazardous waste. Waste was appropriately managed and disposed. Waste that is currently staged on site is being appropriately managed and will be disposed under approved waste profiles in permitted landfills. Waste minimization activities included waste characterization sampling and segregation of waste streams.

  11. Characterization of reproduction and growth of American robins at the Fernald Environmental Management Project, 1991

    SciTech Connect (OSTI)

    Osborne, D.R.; Ambrose, D.M.; Simpson, J.C. [Miami Univ., Oxford, OH (United States)

    1992-11-01T23:59:59.000Z

    As part of a Biological and Ecological Site Characterization of the Fernald Environmental Management Project (FEMP), suppressed growth in onsite American robin nestlings was discovered in 1987 and in 1990. However, the causal factors relating to suppressed growth were not investigated. This study was initiated to determine if growth suppression still existed, and if so, the possible relationship of FEMP land management practices and soil contaminants through food chains to growth and reproductive fitness. This study was expanded to include five offsite sampling sites, as well as analyses of soils and earthworms for uranium, pesticides/herbicides, and heavy metals.

  12. PHP SCILAB | .. | 1 (Web Site) Web Site ,

    E-Print Network [OSTI]

    Kovintavewat, Piya

    PHP SCILAB | .. | 1 Chapter 1 , (Web Site) Web Site , (World Wide Web) : http://school.obec.go.th/borkruwitt/inter/internet01.gif HTML PHP,JavaScript,ASP PHP SCILAB AppServ PHP http://www.appservnetwork.com #12; PHP SCILAB | .. | 2 1. 2. Next 3. I

  13. Sequential Extraction Versus Comprehensive Characterization of Heavy Metal Species in Brownfield Soils

    SciTech Connect (OSTI)

    Dahlin, Cheryl L.; Williamson, Connie A.; Collins, W. Keith; Dahlin, David C.

    2002-06-01T23:59:59.000Z

    The applicability of sequential extraction as a means to determine species of heavy-metals was examined by a study on soil samples from two Superfund sites: the National Lead Company site in Pedricktown, NJ, and the Roebling Steel, Inc., site in Florence, NJ. Data from a standard sequential extraction procedure were compared to those from a comprehensive study that combined optical- and scanning-electron microscopy, X-ray diffraction, and chemical analyses. The study shows that larger particles of contaminants, encapsulated contaminants, and/or man-made materials such as slags, coke, metals, and plastics are subject to incasement, non-selectivity, and redistribution in the sequential extraction process. The results indicate that standard sequential extraction procedures that were developed for characterizing species of contaminants in river sediments may be unsuitable for stand-alone determinative evaluations of contaminant species in industrial-site materials. However, if employed as part of a comprehensive, site-specific characterization study, sequential extraction could be a very useful tool.

  14. CX-010629: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Characterization of Sites for Near Miscible Carbon Dioxide Applications to Improve Oil Recovery in Arbuckle Reser CX(s) Applied: A9, B3.1, B3.6 Date: 07/09/2013 Location(s): Kansas Offices(s): National Energy Technology Laboratory

  15. CX-010628: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Characterization of Sites for Near Miscible Carbon Dioxide Applications to Improve Oil Recovery in Arbuckle... CX(s) Applied: A9, B3.6, B4.4 Date: 07/09/2013 Location(s): Kansas Offices(s): National Energy Technology Laboratory

  16. CX-009693: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    CH2MHill Plateau Remediation Company - Site Characterization and Environmental Monitoring, December 2012 to December 2013 CX(s) Applied: B3.1 Date: 12/14/2012 Location(s): Washington Offices(s): River Protection-Richland Operations Office

  17. CX-011596: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Mission Support Alliance Annual Categorical Exclusion for Site Characterization and Environmental Monitoring under 10 CFR 1021, Subpart D, Appendix B, B3.1 for Calendar Year 2014 CX(s) Applied: B3.1 Date: 12/02/2013 Location(s): Washington Offices(s): River Protection-Richland Operations Office

  18. Advanced 3D Geophysical Imaging Technologies for Geothermal Resource Characterization

    E-Print Network [OSTI]

    Zhang, Haijiang

    2012-01-01T23:59:59.000Z

    We describe the ongoing development of joint geophysical imaging methodologies for geothermal site characterization and demonstrate their potential in two regions: Krafla volcano and associated geothermal fields in ...

  19. Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado. Appendix A of Attachment 3: Calculations, Final

    SciTech Connect (OSTI)

    Not Available

    1994-03-01T23:59:59.000Z

    This report contains calculations for: hydraulic gradients for Alluvial Aquifer and Salt Wash Aquifer; slug test analysis to determine hydraulic conductivity for Alluvial Aquifer and Salt Wash Aquifer; average linear groundwater velocity for Alluvial Aquifer and Salt Wash Aquifer; statistical analysis of the extent of existing groundwater contamination; hydraulic gradients for Dakota/Burro Canyon Formation and Salt Wash Aquifer; slug test analysis to determine hydraulic conductivity for Dakota/Burro Canyon Formation and Perched Salt Wash Aquifer; determination of hydraulic conductivity of the Dakota/Burro Canyon Formation from Packer Tests; average linear groundwater velocity for Dakota/Burro Canyon and Salt Wash Aquifer; chemical and mineralogical characterization of core samples from the Dry Flats Disposal Site; and demonstration of low groundwater yield from Uppermost Aquifer.

  20. CX-010191: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-010191: Categorical Exclusion Determination Site Arc Flash Electrical Upgrades CX(s) Applied: B1.3, B2.5 Date: 04162013 Location(s): Oregon Offices(s):...

  1. Performance Characterization

    Broader source: Energy.gov [DOE]

    Performance characterization efforts within the SunShot Systems Integration activities focus on collaborations with U.S. solar companies to:

  2. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Maybell, Colorado

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, building foundations, and materials associated with the former processing of uranium ore at UMTRA sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further contamination of ground water. One UMTRA Project site is near Maybell, Colorado. Surface cleanup at this site is under way and is scheduled for completion in 1996. The tailings are being stabilized in-place at this site. The disposal area has been withdrawn from public use by the DOE and is referred to as the permanent withdrawal area. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from past uranium ore processing activities. The Ground Water Project at this site is in its beginning stages. This report is a site-specific document that will be used to evaluate current and future potential impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will determine whether any action is needed to protect human health or the environment. Currently, no points of exposure (e.g. a drinking water well); and no receptors of contaminated ground water have been identified at the Maybell site. Therefore, there are no current human health and ecological risks associated with exposure to contaminated ground water. Furthermore, if current site conditions and land- and water-use patterns do not change, it is unlikely that contaminated ground water would reach people or the ecological communities in the future.

  3. Workbook for prioritizing petroleum industry exploration and production sites for remediation

    SciTech Connect (OSTI)

    White, G.J.

    1998-08-03T23:59:59.000Z

    The purpose of this Workbook is to provide a screening-level method for prioritizing petroleum exploration and production sites for remediation that is based on readily available information, but which does not require a full characterization of the sites being evaluated. The process draws heavily from the Canadian National Classification System for Contaminated Sites, and fits into the framework for ecological risk assessment provided in guidance from the US Environmental Protection Agency. Using this approach, scoring guidelines are provided for a number of Evaluation Factors relating to: (1) the contaminants present at the site; (2) the potential exposure pathways for these contaminants; and (3) the potential receptors of those contaminants. The process therefore incorporates a risk-based corrective action (RBCA) framework to estimate the relative threat posed by a site to human health and to ecological systems. Physical (non-toxic) disturbance factors have also been incorporated into the process. It should also be noted that the process described in this Workbook has not yet been field tested at petroleum E and P sites. The first logical step in the field testing of this process is to apply the method at a small number of sites to assess the availability of the information that is needed to score each evaluation factor. Following this evaluation, the Workbook process should be applied at a series of sites to determine the effectiveness of the process at ranking sites according to their relative need for remediation. Upon completion of these tests, the Workbook should be revised to reflect the findings of the field tests.

  4. CX-000515: Categorical Exclusion Determination | Department of...

    Broader source: Energy.gov (indexed) [DOE]

    Determination CX-000515: Categorical Exclusion Determination Characterization of the Coal Pile Runoff Basin 788-3A, Ash Pile 788-A, Outfalls A-013 and A-024 CX(s) Applied: B3.1...

  5. Savannah River Site Environmental Report for 1999

    SciTech Connect (OSTI)

    Arnett, M.

    2000-06-30T23:59:59.000Z

    The purpose of this report is to present summary environmental data that characterize site environmental management performance, confirm compliance with environmental standards and requirements, highlight significant programs and efforts, and assess the impact of SRS operations on the public and the environment.

  6. Voluntary Protection Program Onsite Review, Savannah River Site- May 2010

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether the Savannah River Site is continuing to perform at a level deserving DOE-VPP Star recognition.

  7. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona. Apendix D, Site characteriztion

    SciTech Connect (OSTI)

    Not Available

    1987-05-01T23:59:59.000Z

    This appendix assesses the present conditions and data for the inactive uranium mill site near Tuba City, Arizona. It consolidates available engineering, radiological, geotechnical, hydrological, meterological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill and tailings site so that the Remedial Action Contractor (RAC) may complete final designs of the remedial actions.

  8. Characterization of Amorphous Zinc Tin Oxide Semiconductors....

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Amorphous Zinc Tin Oxide Semiconductors. Characterization of Amorphous Zinc Tin Oxide Semiconductors. Abstract: Amorphous zinc tin oxide (ZTO) was investigated to determine the...

  9. Baseline risk assessment of ground water contamination at the uranium mill tailings site near Falls City, Texas: Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This baseline risk assessment of ground water contamination of the uranium mill tailings site near Falls City, Texas, evaluates potential impact to public health and the environment resulting from ground water contamination at the former Susquehanna Western, Inc. (SWI), uranium mill processing site. This document fulfills the following objectives: determine if the site presents immediate or potential future health risks, determine the need for interim institutional controls, serve as a key input to project planning and prioritization, and recommend future data collection efforts to more fully characterize risk. The Uranium Mill Tailings Remedial Action (UMTRA) Project has begun its evaluation of ground water contamination at the Falls City site. This risk assessment is one of the first documents specific to this site for the Ground Water Project. The first step is to evaluate ground water data collected from monitor wells at or near the site. Evaluation of these data show the main contaminants in the Dilworth ground water are cadmium, cobalt, fluoride, iron, nickel, sulfate, and uranium. The data also show high levels of arsenic and manganese occur naturally in some areas.

  10. Investigation of coal tar mobility at a former MGP site

    SciTech Connect (OSTI)

    Moo-Young, H.K.; Mo, X.H.; Waterman, R.; Coleman, A.; Saroff, S. [California State University Los Angeles, Los Angeles, CA (United States)

    2009-11-15T23:59:59.000Z

    The presence of coal tar in the subsurface of former manufactured gas plant sites poses an environmental hazard and a potential threat to public health. Coal tar can release various chemical compounds that are transported into the groundwater. Before any efforts can be made to remove coal tar from contaminated subsurface soils, it is recommended to characterize coal tar properties and composition and to delineate the residual saturation point between mobile and immobile coal tar. This paper presents a new innovative field device, the Res-SAT field tool, and laboratory procedures that can be used to determine the saturation-capillary pressure relationship for a soil-water coal-tar system and the critical pressure for coal tar mobility.

  11. Environmental assessment: Deaf Smith County site, Texas

    SciTech Connect (OSTI)

    Not Available

    1986-05-01T23:59:59.000Z

    In February 1983, the US Department of Energy (DOE) identified a location in Deaf Smith County, Texas, as one of the nine potentially acceptable sites for mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Deaf Smith County site and eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. The Deaf Smith County site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. On the basis of the evaluations reported in this EA, the DOE has found that the Deaf Smith County site is not disqualified under the guidelines.

  12. area geological characterization: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Utilization Websites Summary: Geological Characterization of California's Offshore Carbon Dioxide Storage Capacity ENVIRONMENTAL sequestration pilot studies to determine...

  13. Regional Analysis of Seafloor Characteristics at Reef Fish Spawning Aggregation Sites in the Caribbean

    E-Print Network [OSTI]

    Kobara, Shinichi

    2011-02-22T23:59:59.000Z

    of the study were: (1) to map the seafloor at historically known grouper and snapper spawning aggregation sites in three different countries, and (2) to characterize quantitatively the geomorphology of the sites including horizontal and vertical curvature...

  14. Complexity of Groundwater Contaminants at DOE Sites

    SciTech Connect (OSTI)

    Hazen, T.C.; Faybishenko, B.; Jordan, P.

    2010-12-03T23:59:59.000Z

    The U.S. Department of Energy (DOE) is responsible for the remediation and long-term stewardship of one of the world's largest groundwater contamination portfolios, with a significant number of plumes containing various contaminants, and considerable total mass and activity. As of 1999, the DOE's Office of Environmental Management was responsible for remediation, waste management, or nuclear materials and facility stabilization at 144 sites in 31 states and one U.S. territory, out of which 109 sites were expected to require long-term stewardship. Currently, 19 DOE sites are on the National Priority List. The total number of contaminated plumes on DOE lands is estimated to be 10,000. However, a significant number of DOE sites have not yet been fully characterized. The most prevalent contaminated media are groundwater and soil, although contaminated sediment, sludge, and surface water also are present. Groundwater, soil, and sediment contamination are present at 72% of all DOE sites. A proper characterization of the contaminant inventory at DOE sites is critical for accomplishing one of the primary DOE missions -- planning basic research to understand the complex physical, chemical, and biological properties of contaminated sites. Note that the definitions of the terms 'site' and 'facility' may differ from one publication to another. In this report, the terms 'site,' 'facility' or 'installation' are used to identify a contiguous land area within the borders of a property, which may contain more than one plume. The term 'plume' is used here to indicate an individual area of contamination, which can be small or large. Even though several publications and databases contain information on groundwater contamination and remediation technologies, no statistical analyses of the contaminant inventory at DOE sites has been prepared since the 1992 report by Riley and Zachara. The DOE Groundwater Data Base (GWD) presents data as of 2003 for 221 groundwater plumes at 60 DOE sites and facilities. Note that Riley and Zachara analyzed the data from only 18 sites/facilities including 91 plumes. In this paper, we present the results of statistical analyses of the data in the GWD as guidance for planning future basic and applied research of groundwater contaminants within the DOE complex. Our analyses include the evaluation of a frequency and ranking of specific contaminants and contaminant groups, contaminant concentrations/activities and total contaminant masses and activities. We also compared the results from analyses of the GWD with those from the 1992 report by Riley and Zachara. The difference between our results and those summarized in the 1992 report by Riley and Zachara could be caused by not only additional releases, but also by the use of modern site characterization methods, which more accurately reveal the extent of groundwater contamination. Contaminated sites within the DOE complex are located in all major geographic regions of the United States, with highly variable geologic, hydrogeologic, soil, and climatic conditions. We assume that the information from the 60 DOE sites included in the GWD are representative for the whole DOE complex. These 60 sites include the major DOE sites and facilities, such as Rocky Flats Environmental Technology Site, Colorado; Idaho National Laboratory, Idaho; Savannah River Site, South Carolina; Oak Ridge Reservation, Tennessee; and Hanford Reservation, Washington. These five sites alone ccount for 71% of the value of the remediation work.

  15. Unraveling the Active Site in Copper-Ceria Systems for the Water-Gas Shift Reaction: In Situ Characterization of an Inverse Powder CeO2-x/CuO-Cu Catalyst

    SciTech Connect (OSTI)

    Barrio, L.; Estrella, M; Zhou, G; Wen, W; Hanson, J; Hungria, A; Hornes, A; Fernandez-Garcia, M; Martinez-Arias, A; Rodriguez, J

    2010-01-01T23:59:59.000Z

    An inverse powder system composed of CeO{sub 2} nanoparticles dispersed over a CuO-Cu matrix is proposed as a novel catalyst for the water-gas shift reaction. This inverse CeO{sub 2}/CuO-Cu catalyst exhibits a higher activity than standard Cu/CeO{sub 2} catalysts. In situ synchrotron characterization techniques were employed to follow the structural changes of CeO{sub 2}/CuO-Cu under reaction conditions. Time-resolved X-ray diffraction experiments showed the transformation of CuO to metallic Cu via a Cu{sub 2}O intermediate. Short-order structural changes were followed by pair distribution function analysis and corroborated the results obtained by diffraction. Moreover, X-ray absorption spectroscopy also revealed oxidation state changes from Cu{sup 2+} to Cu{sup 0} and the partial reduction of CeO{sub x} nanoparticles. The activity data obtained by mass spectrometry revealed that hydrogen production starts once the copper has been fully reduced. The strong interaction of ceria and copper boosted the catalytic performance of the sample. The inverse catalyst was active at low temperatures, stable to several reaction runs and to redox cycles. These characteristics are highly valuable for mobile fuel cell applications. The active phases of the inverse CeO{sub 2}/CuO-Cu catalyst are partially reduced ceria nanoparticles strongly interacting with metallic copper. The nature and structure of the ceria nanoparticles are of critical importance because they are involved in processes related to water dissociation over the catalyst surface.

  16. Unraveling the Active Site in Copper-ceria Systems for the Water Gas Shift Reaction: In-situ Characterization of an Inverse Powder CeO2-x/CuO-Cu Catalyst

    SciTech Connect (OSTI)

    Rodriguez, J.A.; Barrio, L.; Estrella, M.; Zhou, G.; Wen, W.; Hanson, J.C.; Hungría, A.B.; Hornés, A.; Fernández-García, M.; Arturo Martínez-Arias, A.

    2010-03-04T23:59:59.000Z

    An inverse powder system composed of CeO{sub 2} nanoparticles dispersed over a CuO-Cu matrix is proposed as a novel catalyst for the water-gas shift reaction. This inverse CeO{sub 2}/CuO-Cu catalyst exhibits a higher activity than standard Cu/CeO{sub 2} catalysts. In situ synchrotron characterization techniques were employed to follow the structural changes of CeO{sub 2}/CuO-Cu under reaction conditions. Time-resolved X-ray diffraction experiments showed the transformation of CuO to metallic Cu via a Cu{sub 2}O intermediate. Short-order structural changes were followed by pair distribution function analysis and corroborated the results obtained by diffraction. Moreover, X-ray absorption spectroscopy also revealed oxidation state changes from Cu{sup 2+} to Cu{sup 0} and the partial reduction of CeOx nanoparticles. The activity data obtained by mass spectrometry revealed that hydrogen production starts once the copper has been fully reduced. The strong interaction of ceria and copper boosted the catalytic performance of the sample. The inverse catalyst was active at low temperatures, stable to several reaction runs and to redox cycles. These characteristics are highly valuable for mobile fuel cell applications. The active phases of the inverse CeO{sub 2}/CuO-Cu catalyst are partially reduced ceria nanoparticles strongly interacting with metallic copper. The nature and structure of the ceria nanoparticles are of critical importance because they are involved in processes related to water dissociation over the catalyst surface.

  17. A strategy for the quantification of protein polyethylene glycol (PEG) derivatized sites using iTRAQ

    E-Print Network [OSTI]

    Monk, Rebecca Helen

    2011-01-01T23:59:59.000Z

    for characterization of polyethylene glycol-derivatizedof the attachment sites in polyethylene glycol-derivatizedfor the Quantification of Protein Polyethylene Glycol (PEG)

  18. Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Naturita, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project, and the Ground Water Project. For the UMTRA Project site located near Naturita, Colorado, phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado. The surface cleanup will reduce radon and other radiation emissions from the former uranium processing site and prevent further site-related contamination of ground water. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health and the environment, and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water or surface water that has mixed with contaminated ground water. Therefore, a risk assessment was conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.

  19. Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Rifle, Colorado. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase 1) and the Ground Water Project (Phase 2). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment.

  20. Site maps and facilities listings

    SciTech Connect (OSTI)

    Not Available

    1993-11-01T23:59:59.000Z

    In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities.

  1. Hanford Site Environmental Report for Calendar Year 2007

    SciTech Connect (OSTI)

    Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

    2008-06-05T23:59:59.000Z

    The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights signifi cant environmental and public protection programs and efforts. Some historical and early 2008 information is included where appropriate.

  2. Hanford Site Environmental Report for Calendar Year 2009

    SciTech Connect (OSTI)

    Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

    2010-09-01T23:59:59.000Z

    The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2010 information is included where appropriate.

  3. Hanford Site Environmental Report for Calendar Year 2008

    SciTech Connect (OSTI)

    Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

    2009-09-15T23:59:59.000Z

    The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2009 information is included where appropriate.

  4. Waste site grouping for 200 Areas soil investigations

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models.

  5. Hanford Site background: Part 1, Soil background for nonradioactive analytes. Revision 1, Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    The determination of soil background is one of the most important activities supporting environmental restoration and waste management on the Hanford Site. Background compositions serve as the basis for identifying soil contamination, and also as a baseline in risk assessment processes used to determine soil cleanup and treatment levels. These uses of soil background require an understanding of the extent to which analytes of concern occur naturally in the soils. This report documents the results of sampling and analysis activities designed to characterize the composition of soil background at the Hanford Site, and to evaluate the feasibility for use as Sitewide background. The compositions of naturally occurring soils in the vadose Zone have been-determined for-nonradioactive inorganic and organic analytes and related physical properties. These results confirm that a Sitewide approach to the characterization of soil background is technically sound and is a viable alternative to the determination and use of numerous local or area backgrounds that yield inconsistent definitions of contamination. Sitewide soil background consists of several types of data and is appropriate for use in identifying contamination in all soils in the vadose zone on the Hanford Site. The natural concentrations of nearly every inorganic analyte extend to levels that exceed calculated health-based cleanup limits. The levels of most inorganic analytes, however, are well below these health-based limits. The highest measured background concentrations occur in three volumetrically minor soil types, the most important of which are topsoils adjacent to the Columbia River that are rich in organic carbon. No organic analyte levels above detection were found in any of the soil samples.

  6. Implementation of Revision 19 of the TRUPACT-II Safety Analysis Report at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    D'Amico, E.; O'Leary, J.; Bell, S.; Djordjevic, S.; Givens, C,; Shokes, T.; Thompson, S.; Stahl, S.

    2003-02-25T23:59:59.000Z

    The U.S. Nuclear Regulatory Commission on July 27, 2001 approved Revision 19 of the TRUPACT-II Safety Analysis Report (SAR) and the associated TRUPACT-II Authorized Methods for Payload Control (TRAMPAC). Key initiatives in Revision 19 included matrix depletion, unlimited mixing of shipping categories, a flammability assessment methodology, and an alternative methodology for the determination of flammable gas generation rates. All U.S. Department of Energy (DOE) sites shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) were required to implement Revision 19 methodology into their characterization and waste transportation programs by May 20, 2002. An implementation process was demonstrated by the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The three-part process used by RFETS included revision of the site-specific TRAMPAC, an evaluation of the contact-handled TRU waste inventory against the regulations in Revision 19, and design and development of software to facilitate future inventory analyses.

  7. Hanford Site Environmental Report for Calendar Year 2002

    SciTech Connect (OSTI)

    Poston, Ted M.; Hanf, Robert W.; Dirkes, Roger L.; Morasch, Launa F.

    2003-09-01T23:59:59.000Z

    This report is prepared annually to satisfy the requirements of DOE Orders. The report provides an overview of activities at the Hanford Site during 2002 and demonstrates the site's compliance with applicable federal, state, and local environmental laws, regulations, executive orders, and DOE policies; and to summarize environmental data that characterize Hanford Site environmental management performance. The purpose of the report is to provide useful summary information to members of the public, public officials, regulators, Hanford contractors, and elected representatives.

  8. Hanford Site Environmental Report for Calendar Year 2005

    SciTech Connect (OSTI)

    Poston, Ted M.; Hanf, Robert W.; Dirkes, Roger L.; Morasch, Launa F.

    2006-09-28T23:59:59.000Z

    This report, published annually since 1958, includes information and summary analytical data that (1) provide an overview of activities at the Hanford Site during calendar year 2005; (2) demonstrate the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and U.S. Department of Energy (DOE) policies and directives; (3) characterize Hanford Site environmental management performance; and (4) highlight significant environmental programs.

  9. Hanford Site Environmental Report for Calendar Year 2004

    SciTech Connect (OSTI)

    Poston, Ted M.; Hanf, Robert W.; Dirkes, Roger L.

    2005-09-29T23:59:59.000Z

    This report, published annually since 1958, includes information and summary analytical data that (1) provide an overview of activities at the Hanford Site during calendar year 2003; (2) demonstrate the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and U.S. Department of Energy (DOE) policies and directives; (3) characterize Hanford Site environmental management performance; and (4) highlight significant environmental programs.

  10. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado

    SciTech Connect (OSTI)

    Not Available

    1992-02-01T23:59:59.000Z

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  11. NGNP SITE 2 HAZARDS ASSESSMENT

    SciTech Connect (OSTI)

    Wayne Moe

    2011-10-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) Project initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy pursuant to the 2005 Energy Policy Act, is based on research and development activities supported by the Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of the high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite-moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. Accordingly, it can be applied in many industrial applications as a substitute for burning fossil fuels, such as natural gas, to generate process heat in addition to producing electricity, which is the principal application of current LWRs. Nuclear energy in the form of LWRs has been used in the U.S. and internationally principally for the generation of electricity. However, because the HTGR operates at higher temperatures than LWRs, it can be used to displace the use of fossil fuels in many industrial applications. It also provides a carbon emission-free energy supply. For example, the energy needs for the recovery and refining of petroleum, for the petrochemical industry and for production of transportation fuels and feedstocks using coal conversion processes require process heat provided at temperatures approaching 800 C. This temperature range is readily achieved by the HTGR technology. This report summarizes a site assessment authorized by INL under the NGNP Project to determine hazards and potential challenges that site owners and HTGR designers need to be aware of when developing the HTGR design for co-location at industrial facilities, and to evaluate the site for suitability considering certain site characteristics. The objectives of the NGNP site hazard assessments are to do an initial screening of representative sites in order to identify potential challenges and restraints to be addressed in design and licensing processes; assure the HTGR technology can be deployed at variety of sites for a range of applications; evaluate potential sites for potential hazards and describe some of the actions necessary to mitigate impacts of hazards; and, provide key insights that can inform the plant design process. The report presents a summary of the process methodology and the results of an assessment of hazards typical of a class of candidate sites for the potential deployment of HTGR reactor technology. The assessment considered health and safety, and other important siting characteristics to determine the potential impact of identified hazards and potential challenges presented by the location for this technology. A four reactor module nuclear plant (2000 to 2400 MW thermal), that co-generates steam, electricity for general use in the plant, and hot gas for use in a nearby chemical processing facility, to provide the requisite performance and reliability was assumed for the assessment.

  12. 1999 Site Environmental Report

    SciTech Connect (OSTI)

    NONE

    2000-09-01T23:59:59.000Z

    The Site Environmental Report for Brookhaven National Laboratory for the calendar year 1999, as required by DOE Order 231.1.

  13. Nevada National Security Site

    Broader source: Energy.gov [DOE]

    HISTORYIn 1950, President Truman established what is now known as the Nevada National Security Site (NNSS) to perform nuclear weapons testing activities.  In support of national defense initiatives...

  14. 2001 SITE ENVIRONMENTAL REPORT

    SciTech Connect (OSTI)

    BROOKHAVEN NATIONAL LABORATORY

    2002-09-01T23:59:59.000Z

    THE SITE ENVIRONMENTAL REPORT FOR BROOKHAVEN NATIONAL LABORATORY FOR THE CALENDAR YEAR 2001, AS REQUIRED BY DOE ORDER 231.1.

  15. Site observational work plan for the UMTRA Project Site at Grand Junction, Colorado

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has prepared this initial site observational work plan (SOWP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project site in Grand Junction, Colorado. This SOWP is one of the first UMTRA Ground Water Project documents developed to select a compliance strategy that meets the UMTRA ground water standards (40 CFR Part 192, as amended by 60 FR 2854) for the Grand Junction site. This SOWP applies information about the Grand Junction site to the compliance strategy selection framework developed in the UMTRA Ground Water Project draft programmatic environmental impact statement (PEIS). This risk-based, decision-making framework identifies the decision logic for selecting compliance strategies that could be used to meet the ground water standards. The DOE goal is to use the observational method to implement a cost-effective site strategy that complies with the ground water standards and protects human health and the environment. Based on an evaluation of the site characterization and risk assessment data available for the preparation of this SOWP, DOE proposes that the most likely compliance strategy for the Grand Junction site is no remediation based on the application of supplemental standards. This proposed strategy is based on a conceptual site model that indicates site-related contamination is confined to a limited-use aquifer as defined in the ground water standards.

  16. Site observational work plan for the UMTRA project site at Grand Junction, Colorado

    SciTech Connect (OSTI)

    NONE

    1996-01-01T23:59:59.000Z

    This site observational work plan (SOWP) is one of the first Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project documents developed to select a compliance strategy that meets the UMTRA ground water standards for the Grand Junction site. This SOWP applies information about the Grand Junction site to the compliance strategy selection framework developed in the UMTRA Ground Water Project draft programmatic environmental impact statement. This risk-based, decision-making framework identifies the decision logic for selecting compliance strategies that could be used to meet the ground water standards. The US Department of Energy (DOE) goal is to implement a cost-effective site strategy that complies with the ground water standards and protects human health and the environment. Based on an evaluation of the site characterization and risk assessment data available for the preparation of this SOWP, DOE proposes that the most likely compliance strategy for the Grand Junction site is no remediation with the application of supplemental standards. This proposed strategy is based on a conceptual site model that indicates site-related contamination is confined to a limited-use aquifer as defined in the ground water standards. The conceptual model demonstrates that the uranium processing-related contamination at the site has affected the unconfined alluvial aquifer, but not the deeper confined aquifer.

  17. Enterprise Assessments Review, Savannah River Site 2014 Site...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    More Documents & Publications Independent Oversight Inspection, Savannah River Site - January 2010 Independent Oversight Review, Savannah River Site Tritium Facilities - December...

  18. Hanford Site Regional Population - 2010 Census

    SciTech Connect (OSTI)

    Hamilton, Erin L.; Snyder, Sandra F.

    2011-08-12T23:59:59.000Z

    The U.S. Department of Energy conducts radiological operations in south-central Washington State. Population dose estimates must be performed to provide a measure of the impact from site radiological releases. Results of the U.S. 2010 Census were used to determine counts and distributions for the residential population located within 50-miles of several operating areas of the Hanford Site. Year 2010 was the first census year that a 50-mile population of a Hanford Site operational area exceeded the half-million mark.

  19. Site and Operations Overview 1-1 1. Site and Operations Overview

    E-Print Network [OSTI]

    Pennycook, Steve

    undertaking that produced the materials for the first atomic bombs. The reservation's role has evolved over restoration remedial investigation reports and waste manage- ment characterization sampling, are presented Reservation 1-2 Site and Operations Overview surement of contaminants in air, water, groundwa- water skiing

  20. Savannah River Site Environmental Report for 2004

    SciTech Connect (OSTI)

    Mamatey, Albert R.

    2005-06-07T23:59:59.000Z

    The Savannah River Site Environmental Report for 2004 (WSRC-TR-2005-00005) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting,'' and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

  1. Nevada Test Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-10-01T23:59:59.000Z

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  2. Site environmental report for calendar year 1996

    SciTech Connect (OSTI)

    NONE

    1997-08-01T23:59:59.000Z

    The purpose of this Site Environmental Report (SER) is to characterize site environmental management performance, confirm compliance with environmental standards and requirements, and highlight significant programs and efforts to the US Department of Energy (DOE) Strategic Petroleum Reserve (SPR). The SER, provided annually in accordance with DOE Order 5400.1, serves the public by summarizing monitoring data collected to assess how the SPR impacts the environment. The SER provides a balanced synopsis of non-radiological monitoring and regulatory compliance data and affirms that the SPR has been operating within acceptable regulatory limits.

  3. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2007

    SciTech Connect (OSTI)

    Mamatey, A

    2008-08-27T23:59:59.000Z

    The Savannah River Site Environmental Report for 2007 (WSRC-STI-2008-00057) prepared for the US Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting', and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; (4) assess the impact of SRS operations on the public and the environment.

  4. SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2005

    SciTech Connect (OSTI)

    Mamatey, A

    2006-07-18T23:59:59.000Z

    The ''Savannah River Site Environmental Report for 2005'' (WSRC-TR-2006-00007) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

  5. Nevada Test Site Environmental Report 2005

    SciTech Connect (OSTI)

    Cathy A. Wills

    2006-10-01T23:59:59.000Z

    The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

  6. The remedial investigation of marine sediment at the United Heckathorn Superfund site

    SciTech Connect (OSTI)

    White, P.J.; Kohn, N.P.; Gardiner, W.W.; Word, J.Q. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1994-02-01T23:59:59.000Z

    The former United Heckathom site in Richmond, California, was used to process and package chlorinated pesticides from the 1940s to the mid-1960s. These activities resulted in the contamination of upland soils and marine sediment in the adjacent waterways. Battelle/Marine Sciences Laboratory (MSL) was requested by USEPA to conduct a remedial investigation and feasibility study (RI/FS). of the marine portion of the site. The objectives of this RI are to determine the extent of pesticide contamination in inner Richmond Harbor, estimate the total volume of contaminated sediment, characterize the subsurface geology; characterize the biological effects of contaminated sediment; and characterize the quality of effluent derived from dewatered sediment through treatability testing. Sediment cores were collected from 53 stations. Vertical subsamples from each sediment core were analyzed for chlorinated pesticides. Sediment from selected cores was also analyzed for other contaminants. Younger Bay Mud (YBM) sediment from multiple stations was mixed to form composite samples representing various segments of the study area. These composites were used for solid-phase toxicity and bioaccumulation tests, and the preparation of liquid-phase samples for treatability testing. The probable quality of effluent produced by dewatering sediment was evaluated by chemical and toxicological testing of suspended-particulate-phase (SPP) and elutriate samples.

  7. DOE Issues Salt Waste Determination for the Savannah River Site |

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomenthe HouseStudents2.2at Multipleorder suppliesArgonne National LaboratoryDepartment

  8. Categorical Exclusion Determinations: Kansas City Site Office | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26, 20149Department of Energy| Departmentof

  9. Categorical Exclusion Determinations: Los Alamos Site Office | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26, 20149Department ofEnergy Legacyof

  10. Categorical Exclusion Determinations: Nevada Site Office | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26,Energy Service CenterNebraska

  11. Categorical Exclusion Determinations: Pantex Site Office | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26,EnergyOregon Categorical

  12. Categorical Exclusion Determinations: Sandia Site Office | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:JuneNovember 26,EnergyOregonRMOTC Categorical

  13. Site Energy Reduction Program

    E-Print Network [OSTI]

    Jagen, P. R.

    2007-01-01T23:59:59.000Z

    DuPont’s Sabine River Works site is the largest energy consuming location within DuPont. In the year 2000, each production area was encouraged to reduce energy costs. By 2003 site energy consumption was down 16% on an absolute basis and 12% on a BTU...

  14. Protein active sites, interaction

    E-Print Network [OSTI]

    Sjölander, Kimmen

    for active site identification ! Manual MSA and structure analysis ! Catalytic Site Atlas (homology-based) ! Evolutionary Trace (MSA subfamily- and family-wide conservation; phylogenetic tree and structure analysis) ! 3D", Bartlett et al. J Mol Biol. 2002 Nov 15;324(1):105-21. · "An evolutionary trace method defines binding

  15. Site observational work plan for the UMTRA Project site at Falls City, Texas

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    Produced by the US Department of Energy (DOE), this site observational work plan (SOWP) will be used to determine site-specific activities to comply with the US Environmental Protection Agency (EPA) ground water standards at this Uranium Mill Tailings Remedial Action (UMTRA) Project site. The purpose of the SOWP is to recommend a site-specific ground water compliance strategy at the Falls City UMTRA Project site. The Falls City SOWP presents a comprehensive summary of site hydrogeological data, delineates a conceptual model of the aquifer system, and discusses the origins of milling-related ground water contamination. It also defines the magnitude of ground water contamination, potential environmental and health risks associated with ground water contamination and data gaps, and targets a proposed compliance strategy.

  16. Savannah River Site's Site Specific Plan

    SciTech Connect (OSTI)

    Not Available

    1991-08-01T23:59:59.000Z

    This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering.

  17. Site decommissioning management plan

    SciTech Connect (OSTI)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01T23:59:59.000Z

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  18. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 540: Spill Sites Nevada Test Site, Nevada, Rev. No.: 0, with Errata

    SciTech Connect (OSTI)

    Pastor, Laura

    2005-11-01T23:59:59.000Z

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses closure for Corrective Action Unit (CAU) 540, Spill Sites, identified in the ''Federal Facility Agreement and Consent Order''. Corrective Action Unit 540 consists of the nine following Corrective Action Sites (CASs) located in Areas 12 and 19 of the Nevada Test Site: (1) 12-44-01, ER 12-1, Well Site Release; (2) 12-99-01, Oil Stained Dirt; (3) 19-25-02, Oil Spill; (4) 19-25-04, Oil Spill; (5) 19-25-05, Oil Spill; (6) 19-25-06, Oil Spill; (7) 19-25-07, Oil Spill; (8) 19-25-08, Oil Spills (3); and (9) 19-44-03, U-19bf Drill Site Release. This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 540 using the SAFER process. The data quality objective process developed for this CAU identified the following expected closure options: (1) investigation and confirmation that no contamination exists above the final action levels (FALs), leading to a no further action declaration; (2) characterization of the nature and extent of contamination, leading to closure in place with use restrictions; or (3) clean closure by remediation and verification. The expected closure options were selected based on available information including contaminants of potential concern (COPC), future land use, and assumed risks. A decision flow process was developed to define an approach necessary to achieve closure. There are two decisions that need to be resolved for closure. Decision I is to conduct an investigation to determine whether COPCs are present in concentrations exceeding the FALs. If COPCs are found to be present above FALs, excavation of the contaminated material will occur with the collection of confirmation samples to ensure removal of contaminants below FALs.

  19. Oak Ridge Reservation Annual Site Environmental Report for 2009

    SciTech Connect (OSTI)

    Bechtel Jacobs

    2010-09-01T23:59:59.000Z

    The Oak Ridge Reservation Annual Site Environmental Report is prepared animally and presents summary environmental data to (1) characterize environmental performance, (2) summarize environmental occurrences reported during the year, (3) confirm compliance with environmental standards and requirements, and (4) highlight significant program activities. The report fulfills the requirement contained in DOE Order 231.1 A, Environment, Safety and Health Reporting (DOE 2004) that an integrated annual site environmental report be prepared. The results summarized in this report are based on data collected prior to and through 2009. This report is not intended to nor does it present the results of all environmental monitoring associated with the ORR. Data collected for other site and regulatory purposes, such as environmental restoration/remedial investigation reports, waste management characterization sampling data, and environmental permit compliance data, are presented in other documents that have been prepared in accordance with applicable DOE guidance and/or laws and are referenced herein as appropriate. Appendix A to this report identifies corrections to the 2008 report. Appendix B contains a glossary of technical terms that may be useful for understanding the terminology used in this document. Environmental monitoring on the ORR consists primarily of two major activities: effluent monitoring and environmental surveillance. Effluent monitoring involves the collection and analysis of samples or measurements of liquid and gaseous effluents at the points of release to the environment; these measurements allow the quantification and official reporting of contaminant levels, assessment of radiation and chemical exposures to the public, and demonstration of compliance with applicable standards and permit requirements. Environmental surveillance consists of direct measurements and collection and analysis of samples taken from the site and its environs exclusive of effluents; these activities provide information on contaminant concentrations in air, water, groundwater, soil, foods, biota, and other media. Environmental surveillance data support determinations regarding environmental compliance and, when combined with data from effluent monitoring, support chemical and radiation dose and exposure assessments regarding the potential effects of ORR operations, if any, on the local environment.

  20. Oak Ridge Reservation Annual Site Environmental Report, 2003

    SciTech Connect (OSTI)

    Hughes, JF

    2004-08-24T23:59:59.000Z

    This document is prepared annually to summarize environmental activities, primarily environmental-monitoring activities, on the ORR and within the ORR surroundings. The document fulfills the requirement of U.S. Department of Energy (DOE) Order 231.1, ''Environment, Safety and Health Reporting,'' for an annual summary of environmental data to characterize environmental performance. The environmental monitoring criteria are described in DOE Order 450.1, ''Environmental Protection Program''. The results summarized in this report are based on data collected prior to and through 2003. This report is not intended to provide the results of all sampling on the ORR. Additional data collected for other site and regulatory purposes, such as environmental restoration remedial investigation reports, waste management characterization sampling data, and environmental permit compliance data, are presented in other documents that have been prepared in accordance with applicable DOE guidance and/or laws. Corrections to the report for the previous year are found in Appendix A. Environmental monitoring on the ORR consists primarily of two major activities: effluent monitoring and environmental surveillance. Effluent monitoring involves the collection and analysis of samples or measurements of liquid and gaseous effluents at the point of release to the environment; these measurements allow the quantification and official reporting of contaminants, assessment of radiation and chemical exposures to the public, and demonstration of compliance with applicable standards and permit requirements. Environmental surveillance consists of the collection and analysis of environmental samples from the site and its environs; these activities provide direct measurement of contaminants in air, water, groundwater, soil, foods, biota, and other media subsequent to effluent release into the environment. Environmental surveillance data provide information regarding conformity with applicable DOE orders and, combined with data from effluent monitoring, allow the determination of chemical and radiation dose/exposure assessments of ORR operations and effects, if any, on the local environment.

  1. Oak Ridge Reservation Annual Site Environmental Report for 2006

    SciTech Connect (OSTI)

    ORNL,Y-12,ETTP

    2007-09-01T23:59:59.000Z

    This document is prepared annually to summarize environmental activities, primarily environmental-monitoring activities, on the Oak Ridge Reservation (ORR) and within the ORR surroundings. The document fulfills the requirement of Department of Energy (DOE) Order 23l.IA, 'Environment, Safety and Health Reporting,' for an annual summary of environmental data to characterize environmental performance. The environmental-monitoring criteria are described in DOE Order 450.1, 'Environmental Protection Program.' The results summarized in this report are based on data collected prior to and through 2006. This report is not intended to provide the results of all sampling on the ORR. Additional data collected for other site and regulatory purposes, such as environmental restoration remedial investigation reports, waste management characterization sampling data, and environmental permit compliance data, are presented in other documents that have been prepared in accordance with applicable DOE guidance and/or laws and are referenced herein as appropriate. Corrections to the report for the previous year are found in Appendix A. Environmental monitoring on the ORR consists primarily of two major activities: effluent monitoring and environmental surveillance. Effluent monitoring involves the collection and analysis of samples or measurements of liquid and gaseous effluents at the point of release to the environment; these measurements allow the quantification and official reporting of contaminants, assessment of radiation and chemical exposures to the public, and demonstration of compliance with applicable standards and permit requirements. Environmental surveillance consists of the collection and analysis of environmental samples from the site and its environs; these activities provide direct measurement of contaminant concentrations in air, water, groundwater, soil, foods, biota, and other media. Environmental surveillance data provide information regarding conformity with applicable DOE orders and, combined with data from effluent monitoring, allow the determination of chemical and radiation dose/exposure assess ments of ORR operations and effects, if any, on the local environment.

  2. Plutonium-aerosol emission rates and human pulmonary deposition calculations for Nuclear Site 201, Nevada Test Site

    SciTech Connect (OSTI)

    Shinn, J.H.; Homan, D.N.

    1982-06-21T23:59:59.000Z

    This study determined the plutonium-aerosol fluxes from the soil to quantify (1) the extent of potential human exposure by deep-lung retention of alpha-emitting particles; (2) the source term should there be any significant, long-term, transport of plutonium aerosols; and (3) the resuspension factor and rate so that, for the first time at any nuclear site, one may calculate how long it will take for wind erosion to carry away a significant amount of the contaminated soil. High-volume air samplers and cascade impactors were used to characterize the plutonium aerosols. Meteorological flux-profile methods were used to calculate dust and plutonium aerosol emission rates. A floorless wind tunnel (10-m long) was used to examine resuspension under steady-state, high wind speed. The resuspension factor was two orders of magnitude lower than the other comparable sites at NTS and elsewhere, and the average resuspension rate of 5.3 x 10/sup -8//d was also very low, so that the half-time for resuspension by wind erosion was about 36,000 y.

  3. Monitoring Soil Erosion on a Burned Site in the Mojave-Great Basin Transition Zone: Final Report for the Jacob Fire Site

    SciTech Connect (OSTI)

    Miller, Julianne [DRI] DRI; Etyemezian, Vic [DRI] DRI; Cablk, Mary E. [DRI] DRI; Shillito, Rose [DRI] DRI; Shafer, David [DOE Grand Junction, Colorado] DOE Grand Junction, Colorado

    2013-06-01T23:59:59.000Z

    A historic return interval of 100 years for large fires in the U.S. southwestern deserts is being replaced by one where fires may reoccur as frequently as every 20 to 30 years. The shortened return interval, which translates to an increase in fires, has implications for management of Soil Corrective Action Units (CAUs) and Corrective Action Sites (CASs) for which the Department of Energy, National Nuclear Security Administration Nevada Field Office has responsibility. A series of studies was initiated at uncontaminated analog sites to better understand the possible impacts of erosion and transport by wind and water should contaminated soil sites burn. The first of these studies was undertaken at the Jacob Fire site approximately 12 kilometers (7.5 miles) north of Hiko, Nevada. A lightning-caused fire burned approximately 200 hectares during August 6-8, 2008. The site is representative of a transition between Mojave and Great Basin desert ecoregions on the Nevada National Security Site (NNSS), where the largest number of Soil CAUs/CASs are located. The area that burned at the Jacob Fire site was primarily a Coleogyne ramosissima (blackbrush) and Ephedra nevadensis (Mormon tea) community, also an abundant shrub assemblage in the similar transition zone on the NNSS. This report summarizes three years of measurements after the fire. Seven measurement campaigns at the Jacob Fire site were completed. Measurements were made on burned ridge (upland) and drainage sites, and on burned and unburned sites beneath and between vegetation. A Portable In-Situ Wind Erosion Lab (PI-SWERL) was used to estimate emissions of suspended particles at different wind speeds. Context for these measurements was provided through a meteorological tower that was installed at the Jacob Fire site to obtain local, relevant environmental parameters. Filter samples, collected from the exhaust of the PI-SWERL during measurements, were analyzed for chemical composition. Runoff and water erosion were quantified through a series of rainfall/runoff simulation tests in which controlled amounts of water were delivered to the soil surface in a specified amount of time. Runoff data were collected from understory and interspace soils on burned ridge and drainage areas. Runoff volume and suspended sediment in the runoff were sampled; the particle size distribution of the sediment was determined by laboratory analysis. Several land surface and soil characteristics associated with runoff were integrated by the calculation of site-specific curve numbers. Several vegetation surveys were conducted to assess post-burn recovery. Data from plots in both burned and unburned areas included species identification, counts, and location. Characterization of fire-affected area included measures at both the landscape scale and at specific sites. Although wind erosion measurements indicate that there are seasonal influences on almost all parameters measured, several trends were observed. PI-SWERL measurements indicated the potential for PM10 windblown dust emissions was higher on areas that were burned compared to areas that were not. Among the burned areas, understory soils in drainage areas were the most emissive, and interspace soils along burned ridges were least emissive. By 34 months after the burn (MAB), at the end of the study, emissions from all burned soil sites were virtually indistinguishable from unburned levels. Like the amount of emissions, the chemical signature of the fire (indicated by the EC-Soil ratio) was elevated immediately after the fire and approached pre-burn levels by 24 MAB. Thus, the potential for wind erosion at the Jacob Fire site, as measured by the amount and type of emissions, increased significantly after the fire and returned to unburned levels by 24 MAB. The effect of fire on the potential for water erosion at the Jacob Fire site was more ambiguous. Runoff and sediment from ridge interspace soils and unburned interspace soils were similar throughout the study period. Seldom, if ever, did runoff and sediment occur in burned drainage area soils. Fo

  4. Colorado, Processing Sites

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North SiteD&D

  5. Site observational work plan for the UMTRA Project site at Monument Valley, Arizona

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    The site observational work plan (SOWP) for the Monument Valley, Arizona, US Department of Energy (DOE) Uranium Mill Tailings Remedial Action(UMTRA) Project site is one of the first site-specific documents developed to achieve ground water compliance at the site. This SOWP applies information about the Monument Valley site to a regulatory compliance framework that identifies strategies that could be used to meet ground water compliance. The compliance framework was developed in the UMTRA Ground Water programmatic environmental impact statement (DOE, 1996). The DOE`s goal is to implement a cost-effective site strategy that complies with the US Environmental Protection Agency (EPA) ground water standards and protects human health and the environment. The compliance strategy that emerges in the final version of the SOWP will be evaluated in the site-specific environmental assessment to determine potential environmental impacts and provide stakeholders a forum for review and comment. When the compliance strategy is acceptable, it will be detailed in a remedial action plan that will be subject to review by the state and/or tribe and concurrence by the US Nuclear Regulatory Commission (NRC). Information for the preparation of this SOWP indicates active remediation is the most likely compliance strategy for the Monument Valley site. Additional data are needed to determine the most effective remediation technology.

  6. Hanford Site Environmental Report for Calendar Year 2010

    SciTech Connect (OSTI)

    Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

    2011-07-12T23:59:59.000Z

    The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2011 information is included where appropriate.

  7. Electrochemical Characterization Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01T23:59:59.000Z

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Electrochemical Characterization Laboratory at the Energy Systems Integration Facility. The research focus at the Electrochemical Characterization Laboratory at NREL's Energy Systems Integration Facility (ESIF) is evaluating the electrochemical properties of novel materials synthesized by various techniques and understanding and delineating the reaction mechanisms to provide practical solutions to PEMFCs commercialization issues of cost, performance and durability. It is also involved in the development of new tools and techniques for electrochemical characterization. The laboratory concentrates on the development and characterization of new materials for PEMFCs such as electrocatalysts, catalyst supports in terms of electrochemical activity, electrochemical surface area and corrosion/durability. The impact of impurities and/or contaminants on the catalyst activity is also under study. Experiments that can be performed include: (1) Determination and benchmarking of novel electrocatalyst activity; (2) Determination of electrochemical surface area; (3) Determination of electrocatalyst and support corrosion resistance and durability; (4) Synthesis and characterization of novel electrocatalyst; (5) Determination of fundamental electrochemical parameters; and (6) Estimation of electrocatalyst utilization.

  8. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    and A.M. Jessop, Hydraulic fracturing experiment at theor pressures at which hydraulic fracturing of the cap rocka high potential for hydraulic fracturing occurs in the case

  9. DOE Awards Small Business Contract for Site Characterization...

    Energy Savers [EERE]

    them for various contaminates, reporting the findings, and for building a permanent soil erosion control system. The mission of the Office of Environmental Management is to...

  10. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    in depleted or abandoned oil and gas reservoirs; how- ever,abandoned wells represent a potentially direct route from reservoirabandoned in the 1930s with no barrier installed after it encountered a natural CO 2 reservoir

  11. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    in depleted or abandoned oil and gas reservoirs; how- ever,oil well abandoned in the 1930s with no barrier installed after it encountered a natural CO 2 reservoir

  12. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    IN DEPLETED AND NEAR- DEPLETED OIL RESERVOIRS V. A. KuuskraaDEPLETED AND NEAR-DEPLETED OIL RESERVOIRS Vello A. Kuuskraaof CO 2 in a depleted oil reservoir: an overview,

  13. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    coal bed methane recovery (ECBM). Data from reservoirs incoal bed methane (ECBM) recovery. Also, since oil and gas reservoirs

  14. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    Marchetti, C. , On geoengineering and the CO2 prob- lem.to the location of geoengineering activities seems to be

  15. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    of the rock volume. Oil-production data indicate that theal. , 2006). Historical oil production at depths around 2400logs in regionally dis- oil production tributed wells Well

  16. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    Basin. The successful drill stem test re- covered 84.1 m (and fluid data from drill stem tests (as shown in Figure 3

  17. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    be necessary to extract coal seam methane or groundwater inCalifornia, March 20-22, 2006 Unmineable coal seams Finally,unmineable coal seams pose substantial chal- lenges in all

  18. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    157 WELL INTEGRITY IN CO 2 ENVIRONMENTS: PERFORMANCE, RISK,of CO 2 injection, wells integrity and long term behavior ofcan compromise the well integrity and thus its functional

  19. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    Treatise of Petroleum Geology, Atlas of Oil and Gas Fields,A-A’). phy, geology, stratigraphic contacts, oil and gas andgeology, initial information available from hydrogeology, oil

  20. International Symposium on Site Characterization for CO2 Geological Storage

    E-Print Network [OSTI]

    Tsang, Chin-Fu

    2006-01-01T23:59:59.000Z

    EOR) and enhanced coalbed methane recovery (ECBMR) becauseand potential for coalbed methane. The Mannville coals areCO 2 injectivity and coalbed methane producibility. Thus,