National Library of Energy BETA

Sample records for disposal site long-term

  1. Grand Junction, Colorado, Disposal Site Long-Term Surveillance...

    Office of Legacy Management (LM)

    ... Grand Junction, Colorado, Disposal Site Long-Term Surveillance and Maintenance Program The Grand Junction Office has provided cost-effective and efficient stewardship for more than ...

  2. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    1997-12-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  3. Long-term surveillance plan for the Maybell, Colorado Disposal Site

    SciTech Connect (OSTI)

    1997-09-01

    This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

  4. Guidance for implementing the long-term surveillance program for UMTRA Project Title I Disposal Sites

    SciTech Connect (OSTI)

    1996-02-01

    This guidance document has two purposes: it provides guidance for writing site-specific long-term surveillance plans (LTSP) and it describes site surveillance, monitoring, and long-term care techniques for Title I disposal sites of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.). Long-term care includes monitoring, maintenance, and emergency measures needed to protect public health and safety and the environment after remedial action is completed. This document applies to the UMTRCA-designated Title I disposal sites. The requirements for long-term care of the Title I sites and the contents of the LTSPs are provided in U.S. Nuclear Regulatory Commission (NRC) regulations (10 CFR Section 40.27) provided in Attachment 1.

  5. Long-term surveillance plan for the Tuba City, Arizona disposal site

    SciTech Connect (OSTI)

    1996-02-01

    This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Tuba City, Arizona, describes the site surveillance activities. The U.S. Department of Energy (DOE) will carry out these activities to ensure the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) (10 CFR {section}40.27).

  6. Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2

    SciTech Connect (OSTI)

    1996-11-01

    The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas.

  7. Long-Term Performance of Transuranic Waste Inadvertently Disposed in a Shallow Land Burial Trench at the Nevada Test Site

    SciTech Connect (OSTI)

    Gregory J. Shott; Vefa Yucel

    2009-07-16

    In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes. The Waste Isolation Pilot Plant is the only facility meeting these requirements. The National Research Council, however, has found that exhumation of buried TRU waste for disposal in a deep geologic repository may not be warranted when the effort, exposures, and expense of retrieval are not commensurate with the risk reduction achieved. The long-term risks of leaving the TRU waste in-place are evaluated in two probabilistic performance assessments. A composite analysis, assessing the dose from all disposed waste and interacting sources of residual contamination, estimates an annual total effective dose equivalent (TEDE) of 0.01 mSv, or 3 percent of the dose constraint. A 40 CFR 191 performance assessment also indicates there is reasonable assurance of meeting all requirements. The 40 CFR 191.15 annual mean TEDE for a member of the public is estimated to reach a maximum of 0.055 mSv at 10,000 years, or approximately 37 percent of the 0.15 mSv individual protection requirement. In both assessments greater than 99 percent of the dose is from co-disposed low-level waste. The simulated probability of the 40 CFR 191.13 cumulative release exceeding 1 and 10 times the release limit is estimated to be 0.0093 and less than 0.0001, respectively. Site characterization data and hydrologic process modeling support a conclusion of no groundwater pathway within 10,000 years. Monte Carlo uncertainty analysis indicates that there is reasonable assurance of meeting all regulatory requirements. Sensitivity analysis indicates that the results are insensitive to TRU waste-related parameters. Limited quantities of TRU waste in a shallow land burial trench can meet DOE performance objectives for disposal of TRU waste and contribute negligibly to disposal site risk. Leaving limited quantities of buried TRU waste in-place may be preferred over retrieval for disposal in a deep geologic repository.

  8. Long-Term Stewardship - Hanford Site

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

    Comprehensive Land-Use Plan - Environmental Impact Statement (HCP EIS), and 64 FR 61615, "Record ... DOE directives, and Hanford Site procedures. hidden Long-Term Stewardship ...

  9. Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance

    Broader source: Energy.gov [DOE]

    Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance...

  10. Site Transition Framework for Long-Term Surveillance and Maintenance...

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

    Framework for Long-Term Surveillance and Maintenance Site Transition Framework for Long-Term Surveillance and Maintenance Site Transition Framework for Long-Term Surveillance and ...

  11. Site Transition Framework for Long-Term Surveillance and Maintenance

    Broader source: Energy.gov [DOE]

    The Site Transition Framework (STF) provides a framework for all U.S. Department of Energy (DOE) facilities and sites where DOE may have anticipated long-term surveillance and maintenance (LTS&...

  12. Relevance of biotic pathways to the long-term regulation of nuclear waste disposal. Topical report on reference eastern humid low-level sites

    SciTech Connect (OSTI)

    McKenzie, D.H.; Cadwell, L.L.; Eberhardt, L.E.; Kennedy, W.E. Jr.; Peloquin, R.A.; Simmons, M.A.

    1983-01-01

    The purpose of the work reported here was to develop an order-of-magnitude estimate for the potential dose to man resulting from biotic transport mechanisms at a humid reference low-level waste site in the eastern US. A description of the reference site is presented that includes the waste inventories, site characteristics and biological communites. Parameter values for biotic transport processes are based on data reported in current literature. Transport and exposure scenarios are developed for assessing biotic transport during 500 years following site closure. Calculations of radionuclide decay and waste container decomposition are made to estimate the quantities available for biotic transport. Doses to man are calculated for the biological transport of radionucludes at the reference site after loss of institutional control. These dose estimates are compared to dose estimates we calculated for the intruder-agricultural scenarios reported in the DEIS for 10 CFR 61 (NRC). Dose to man estimates as a result of cumulative biotic transport are calculated to be of the same order-of-magnitude as the dose resulting from the more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at low-level waste sites in earlier assessment studies is not confirmed by findings presented in this report. Through biotic transport, radionuclides can be moved to locations where they can enter exposure pathways to man.

  13. Research on long term safety of nuclear waste disposal at the research center Karlsruhe, Germany

    SciTech Connect (OSTI)

    Gompper, Klaus; Bosbach, Dirk; Denecke, Melissa A.; Geckeis, Horst; Kienzler, Bernhard; Klenze, Reinhardt

    2007-07-01

    In Germany the safe disposal of radioactive waste is in the responsibility of the federal government. The R and D performed in the Institute for Nuclear Waste Disposal (INE) at the Research Center Karlsruhe contributes to the German provident research in the field of long-term safety for final disposal of high level heat producing nuclear wastes. INE's research is focused on the actinide elements and long lived fission products since these dominate the radiotoxicity over a long time. The research strategy synergistically combines fundamental science of aquatic radionuclide chemistry with applied investigations of real systems (waste form, host rock, aquifer), studied on laboratory scale and in underground laboratories. Because Germany has not yet selected a site for a high-level waste repository, all host rock formations under discussion in the international community (salt, hard rock, clay/tone) are investigated. Emphasis in long-term safety R and D at INE is on the development of actinide speciation methods and techniques in the trace concentration range. (authors)

  14. Site transition framework for long-term surveillance and maintenance

    SciTech Connect (OSTI)

    2014-04-01

    This document provides a framework for all U.S. Department of Energy (DOE) facilities and sites where DOE may have anticipated long-term surveillance and maintenance (LTSM) responsibilities. It is a tool to help facilitate a smooth transition from remediation to LTSM, providing a systematic process for affected parties to utilize in analyzing the baseline to understand and manage the actions from EM mission completion through a site’s transition into LTSM. The framework is not meant to provide an exhaustive list of the specific requirement and information that are needed. Sites will have unique considerations that may not be adequately addressed by this tool, and it is anticipated that a team comprised of the transferring and receiving organization will use judgment in utilizing this augmenting with other DOE guidance. However the framework should be followed to the extent possible at each site; and adapted to accommodate unique site-specific requirements, needs, and documents. Since the objective of the tool is facilitate better understanding of the conditions of the site and the actions required for transfer, the transition team utilizing the checklist is expected to consult with management of both the receiving and transferring organization to verify that major concerns are addressed. Ideally, this framework should be used as early in the remediation process as possible. Subsequent applications of the Site Transition Framework (STF) to the site should be conducted periodically and used to verify that all appropriate steps have been or will be taken to close-out the site and that actions by both organization are identified to transfer the site to LTSM. The requirements are provided herein.

  15. Long-Term Storage of Cesium and Strontium at the Hanford Site

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

    Long-Term Storage of Cesium and Strontium at the Hanford Site OAS-L-14-04 March 2014 ... SUBJECT: INFORMATION: Audit Report on "Long-Term Storage of Cesium and Strontium at ...

  16. Site Transition Summary: Cleanup Completion to Long-Term Stewardship at

    Energy Savers [EERE]

    Department of Energy On-going Mission Sites | Department of Energy Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites Site Transition Summary: Cleanup Completion to Long-Term Stewardship at Department of Energy On-going Mission Sites Long-term stewardship (LTS) includes the physical controls, institutions, information, and other mechanisms needed to ensure protection of people and the environment at sites where the U.S. Department of Energy

  17. Long-Term Surveillance and Monitoring Program Annual Site Inspection...

    Office of Legacy Management (LM)

    Encroachment of vegetation, primarily tumbleweeds, continues on the disposal cell. On ... Encroachment of plants in the northwest diversion channel, reported previously, was ...

  18. A Report to Congress on Long-Term Stewardship. Volume II, Site Summaries

    SciTech Connect (OSTI)

    2001-01-01

    During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as for other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over a 100 sites in 30 States and one U.S. Territory. Hundreds of thousand of acres of residually contaminated soils, contaminated groundwater, surface water and sediment contamination, and contaminated buildings are present at many sites across the country. These sites range in size from less than one acre, containing only a single facility, to large sites spanning over 100,000 acres with huge uranium enrichment plants and plutonium processing canyons. Since 1989, the U.S. Department of Energy’s (DOE) Environmental Management (EM) program has made significant progress in addressing this environmental legacy. Millions of cubic meters of waste have been removed, stabilized, or disposed of, resulting in significant risk and cost reduction. In addition, DOE began disposing of transuranic (i.e., plutonium-contaminated) waste in the nation’s first deep geologic repository – the Waste Isolation Pilot Plant in New Mexico. DOE is now carrying out its long-term stewardship obligations at dozens of sites, including smaller sites where DOE has completed cleanup work for the entire site and many larger sites where DOE has remediated portions of the site.

  19. Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance

    SciTech Connect (OSTI)

    2012-03-01

    This document presents guidance for implementing the process that the U.S. Department of Energy (DOE) Office of Legacy Management (LM) will use for assuming perpetual responsibility for a closed uranium mill tailings site. The transition process specifically addresses sites regulated under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) but is applicable in principle to the transition of sites under other regulatory structures, such as the Formerly Utilized Sites Remedial Action Program.

  20. Disposal Information - Hanford Site

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

    About Us Hanford Site Wide Programs Hanford Site Solid Waste Acceptance Program Tools Disposal Information About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Tools Approved High Integrity Containers Approved Sorbents, Stabilizers, and Void Fillers Disposal Information Points of Contact Disposal Information Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size Disposal of Radioactive Waste at Hanford The Hanford Site

  1. Long-Term Assessment of Critical Radionuclides and Associated Environmental Media at the Savannah River Site

    SciTech Connect (OSTI)

    Jannik, G. T.; Baker, R. A.; Lee, P. L.; Eddy, T. P.; Blount, G. C.; Whitney, G. R.

    2012-11-06

    During the operational history of the Savannah River Site (SRS), many different radionuclides have been released from site facilities. However, only a relatively small number of the released radionuclides have been significant contributors to doses and risks to the public. At SRS dose and risk assessments indicate tritium oxide in air and surface water, and Cs-137 in fish and deer have been, and continue to be, the critical radionuclides and pathways. In this assessment, indepth statistical analyses of the long-term trends of tritium oxide in atmospheric and surface water releases and Cs-137 concentrations in fish and deer are provided. Correlations also are provided with 1) operational changes and improvements, 2) geopolitical events (Cold War cessation), and 3) recent environmental remediation projects and decommissioning of excess facilities. For example, environmental remediation of the F- and H-Area Seepage Basins and the Solid Waste Disposal Facility have resulted in a measurable impact on the tritium oxide flux to the onsite Fourmile Branch stream. Airborne releases of tritium oxide have been greatly affected by operational improvements and the end of the Cold War in 1991. However, the effects of SRS environmental remediation activities and ongoing tritium operations on tritium concentrations in the environment are measurable and documented in this assessment. Controlled hunts of deer and feral hogs are conducted at SRS for approximately six weeks each year. Before any harvested animal is released to a hunter, SRS personnel perform a field analysis for Cs-137 concentrations to ensure the hunter's dose does not exceed the SRS administrative game limit of 0.22 millisievert (22 mrem). However, most of the Cs-137 found in SRS onsite deer is not from site operations but is from nuclear weapons testing fallout from the 1950's and early 1960's. This legacy source term is trended in the SRS deer, and an assessment of the ''effective'' half-life of Cs-137 in deer (including the physical decay half-life and the environmental dispersion half-life) is provided. The ''creek mouth'' fisherman is the next most critical pathway at SRS. On an annual basis, three species of fish (panfish, catfish, and bass) are sampled from the mouths of the five SRS streams. Three composites of up to five fish of each species are analyzed from each sampling location. Long-term trending of the Cs-137 concentrations in fish and the subsequent doses from consumption of SRS fish is provided.

  2. Effect of soil erosion on the long-term stability of FUSRAP near-surface waste-burial sites

    SciTech Connect (OSTI)

    Knight, M.J.

    1983-04-01

    Decontamination of FUSRAP sites could result in the generation of large volumes (in excess of 400,000 m/sup 3/) of low-activity radioactive wastes (primarily contaminated soil and building materials) requiring subsequent disposal. It is likely that near-surface burial will be seriously considered as an option for disposal of these materials. A number of factors - including soil erosion - could adversely affect the long-term stability of a near-surface waste-burial site. The majority of FUSRAP sites are located in the humid eastern United States, where the principal cause of erosion is the action of water. This report examines the effect of soil erosion by water on burial-site stability based on analysis of four hypothetical near-surface burial sites. The Universal Soil Loss Equation was employed to estimate average annual soil loss from burial sites and the 1000-year effects of soil loss on the soil barrier (burial trench cap) placed over low-activity wastes. Results suggest that the land use of the burial site and the slope gradient of the burial trench cap significantly affect the rate of soil erosion. The development of measures limiting the potential land use of a burial site (e.g., mixing large rocks into the burial trench cap) may be required to preserve the integrity of a burial trench for long periods of time.

  3. Guidance for Developing and Implementing Long-Term Surveillance Plans for

    Energy Savers [EERE]

    UMTRCA Title I and Title II Disposal Sites | Department of Energy Guidance for Developing and Implementing Long-Term Surveillance Plans for UMTRCA Title I and Title II Disposal Sites Guidance for Developing and Implementing Long-Term Surveillance Plans for UMTRCA Title I and Title II Disposal Sites Guidance for Developing and Implementing Long-Term Surveillance Plans for UMTRCA Title I and Title II Disposal Sites (November 2012) PDF icon Guidance for Developing and Implementing Long-Term

  4. Long-Term Surveillance Plan...

    Office of Legacy Management (LM)

    AL/62350-235 REV. 1 LONG-TERM SURVEILLANCE PLAN FOR THE ESTES GULCH DISPOSAL SITE NEAR RIFLE, COLORADO November 1997 DOE and DOE contractors can obtain copies of this report from: Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831 (615) 576-8401 This report is publicly available from: National Technical Information Service Department of Commerce 5285 Port Royal Road Springfield, VA 22161 (703) 487-4650 Long-Term Surveillance Plan for the Estes Gulch Disposal Site Near

  5. Shifting the Paradigm for Long Term Monitoring at Legacy Sites to Improve Performance while Reducing Cost

    SciTech Connect (OSTI)

    Eddy-Dilek, Carol A.; Looney, Brian B.; Seaman, John; Kmetz, Thomas

    2013-01-10

    A major issue facing many government and private industry sites that were previously contaminated with radioactive and chemical wastes is that often the sites cannot be cleaned up enough to permit unrestricted human access. These sites will require long-term management, in some cases indefinitely, leaving site owners with the challenge of protecting human health and environmental quality in a cost effective manner. Long-term monitoring of groundwater contamination is one of the largest projected costs in the life cycle of environmental management at the Savannah River Site (SRS), the larger DOE complex, and many large federal and private sites. Currently, most monitoring strategies are focused on laboratory measurements of contaminants measured in groundwater samples collected from wells. This approach is expensive, and provides limited and lagging information about the effectiveness of cleanup activities and the behavior of the residual contamination. Over the last twenty years, DOE and other federal agencies have made significant investments in the development of various types of sensors and strategies that would allow for remote analysis of contaminants in groundwater, but these approaches do not promise significant reductions in risk or cost. Scientists at SRS have developed a new paradigm to simultaneously improve the performance of long term monitoring systems while lowering the overall cost of monitoring. This alternative approach incorporates traditional point measurements of contaminant concentration with measurements of controlling variables including boundary conditions, master variables, and traditional plume/contaminant variables. Boundary conditions are the overall driving forces that control plume movement and therefore provide leading indication to changes in plume stability. These variables include metrics associated with meteorology, hydrology, hydrogeology, and land use. Master variables are the key variables that control the chemistry of the groundwater system, and include redox variables (ORP, DO, chemicals), pH, specific conductivity, biological community (breakdown/decay products), and temperature. A robust suite of relatively inexpensive tools is commercially available to measure these variables. Traditional plume/contaminant variables are various measures of contaminant concentration including traditional analysis of chemicals in groundwater samples. An innovative long term monitoring strategy has been developed for acidic or caustic groundwater plumes contaminated with metals and/or radionuclides. Not only should the proposed strategy be more effective at early identification of potential risks, this strategy should be significantly more cost effective because measurement of controlling boundary conditions and master variables is relatively simple. These variables also directly reflect the evolution of the plume through time, so that the monitoring strategy can be modified as the plume 'ages'. This transformational long-term monitoring paradigm will generate significant cost savings to DOE, other federal agencies and industry and will provide improved performance and leading indicators of environmental management performance.

  6. Influence of Nuclear Fuel Cycles on Uncertainty of Long Term Performance of Geologic Disposal Systems

    Broader source: Energy.gov [DOE]

    Development and implementation of future advanced fuel cycles including those that recycle fuel materials, use advanced fuels different from current fuels, or partition and transmute actinide radionuclides, will impact the waste management system. The UFD Campaign can reasonably conclude that advanced fuel cycles, in combination with partitioning and transmutation, which remove actinides, will not materially alter the performance, the spread in dose results around the mean, the modeling effort to include significant features, events, and processes (FEPs) in the performance assessment, or the characterization of uncertainty associated with a geologic disposal system in the regulatory environment of the US.

  7. Long Term Stewardship Challenges at the St. Louis District FUSRAP Sites

    SciTech Connect (OSTI)

    Dell'Orco, L.; Chambers, D.

    2002-02-27

    Non-Federally owned radioactively contaminated sites in St. Louis, Missouri are currently being remediated by the St. Louis District Corps of Engineers under the Formerly Utilized Sites Remedial Action Program (FUSRAP). When FUSRAP remediation is complete, inaccessible soils which have levels of contamination greater than unrestricted use standards, will remain. The purpose of this paper is to document the initial challenges facing the project team during its development of the Long Term Stewardship plan for the management of these soils. These soils are located under buildings, roads, railroads and bridges. The Long Term Stewardship plan for the majority of the sites is being developed simultaneously with the remedy selection process. A living document, it will ultimately document the remedial action end state and location of inaccessible soils and implement the plan for ensuring these soils are not a threat to human health and the environment. Although these soils are protective in their current configuration, at some point in time, when activities such as maintenance, utility or property improvement occur, the soils will become accessible and need to be addressed by the federal government. Up until that point in time they will need to be effectively managed to ensure they remain protective. The St. Louis District is in the process of collaboratively developing this plan with its regulators, affected stakeholders and interested parties.

  8. LONG-TERM SURVEILLANCE PLAN FOR THE GREEN RIVER, UTAH DISPOSAL...

    Office of Legacy Management (LM)

    ... for the Green River, Utah site ...... 5-8 This plate is not available in PDF form For more information, contact the U.S. Department of Energy Grand Junction ...

  9. Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2

    SciTech Connect (OSTI)

    Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P.

    1997-09-01

    This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

  10. Long-Term Assessment of Isotopic Exchange of Carbon Dioxide in a Subalpine Forest (Niwot Ridge AmeriFlux Site)

    SciTech Connect (OSTI)

    Bowling, David

    2014-12-31

    In 2005 we began a long-term measurement program of CO{sub 2} and its stable isotopes at the Niwot Ridge AmeriFlux site. Measurements are ongoing.

  11. An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities

    SciTech Connect (OSTI)

    Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

    2011-03-01

    Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

  12. Site Transition Summary: Clean-up Completion to Long Term Stewardship

    Broader source: Energy.gov [DOE]

    At the August 13, 2014 Committee meeting Tom Longo DOE, Provided Information on the Long Term Stewardship Process that the Office of Legacy Management is Responsible for.

  13. Long-Term Surveillance Plan for the Site A/Plot M Sites, Palos...

    Office of Legacy Management (LM)

    ... The TRC scrutinizes site status by reviewing annual ... Role of the Department of Energy In 1988, the DOE ... from Site APlot M. Water usage in the area is confined to ...

  14. May 16, 2016- Predicting the Service Life of Geomembranes in Low-Level and Mixed-Waste Disposal Facilities: Findings from a Long-Term Study

    Broader source: Energy.gov [DOE]

    Performance & RIsk Assessment (P&RA) Community of Practice (CoP) Webinar - May 16, 2016 - Predicting the Service Life of Geomembranes in Low-Level and Mixed-Waste Disposal Facilities: Findings from a Long-Term Study. Presented by Dr. Craig Benson (Dean of School of Engineering and Applied Science, and Janet Scott Hamilton and John Downman Hamilton Professor, Univ. of Virginia).

  15. Long-Term Surveillance Plan for the Upper Burbank Disposal Cell, Uravan, Colorado, DOE/AL/62350-250, Revision 1, July 1999

    Office of Legacy Management (LM)

    LONG-TERM SURVEILLANCE PLAN FOR THE UPPER BURBANK DISPOSAL CELL URAUAN, COLORADO July 1999 Prepared for U.S. Department of Energy Environmental Restoration Dhrision U MTRA Project Team Albuquerque, New Mexico DOElAU62350-250 REV. 1 Prepared by Jacobs Engineering Group Inc. Albuquerque, New Mexico This page intentionally left blank LONG-TERM GURMIWNCE P U N FOR THE UPPER BURBANK DrsPosAL CEU. WYAAI. COhORAOD TABLE OF DONENTe TABLE OF CONTENTS 1.0 PURPOSEANDSCOPE

  16. Long-Term Climate Change Assessment Task for the Hanford Site Permanent Isolation Barrier Development Program: Status through FY 1992

    SciTech Connect (OSTI)

    Petersen, K.L.; Chatters, J.C.

    1993-07-01

    The Hanford Site Permanent Isolation Barrier Development Program (Barrier Development Program) was organized (Adams and Wing 1986) to develop the technology needed to provide an in-place disposal capability for the US Department of Energy at the Hanford Site in southeastern Washington. The goals of the Barrier Development Program are to provide defensible evidence that final barrier design(s) will adequately control water infiltration, plant and animal intrusion, and wind and water erosion for a minimum of 1,000 years; to isolate wastes from the accessible environment; and to use markers to warn inadvertent human intruders. Evidence for barrier performance will be obtained by conducting laboratory experiments, field tests, computer modeling, and other studies that establish confidence in the barrier`s ability to meet its 1,000-year design life. The performance and stability of natural barrier analogs that have existed for several millennia and the reconstruction of climate changes during the past 10,000 to 125,000 years also will provide insight into bounding conditions of possible future changes and increase confidence in the barriers design. In the following discussion the term {open_quotes}long-term{close_quotes} references periods of time up to 1000`s of years, distinguishing it from {open_quotes}short-term{close_quotes} weather patterns covering a decade or less. Specific activities focus on planning and conducting a series of studies and tests required to confirm key aspects of the barrier design. The effort is a collaborative one between scientists and engineers from Westinghouse Hanford Company (Westinghouse Hanford) and Pacific Northwest Laboratory (PNL) to design barriers to limit movement of radionuclides and other contaminants to the accessible environment for at least 1,000 years. These activities have been divided into 14 groups of tasks that aid in the complete development of protective barrier and warning marker system.

  17. ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT

    SciTech Connect (OSTI)

    Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

    2012-04-25

    The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

  18. Data Archive of the Harvard Forest, a Long Term Ecological Research (LTER) Site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Since 1907 research and education have been the mission of the Harvard Forest is one of the oldest and most intensively studied forests in North America. Located in Petersham, Massachusetts, its 3000 acres of land have been a center of research and education since 1907. The Long Term Ecological Research (LTER) program, established in 1988 and funded by the National Science Foundation, provides a framework for much of this activity. An understanding of forest responses to natural and human disturbance and environmental change over broad spatial and temporal scales pulls together research topics including biodiversity studies, the effects of invasive organisms, large experiments and permanent plot studies, historical and retrospective studies, soil nutrient dynamics, and plant population and community ecological interactions. Major research in forest-atmosphere exchange, hydrology, and regional studies places the work in regional and global context, aided by modeling tools. Conservation and management research and linkages to policy have been part of the Forest since its beginning, and the approaches used in New England can often apply to international studies. [Copied from http://harvardforest.fas.harvard.edu/research.html] In addition to more than 150 datasets, the Visual Information Access system at Harvard University Library makes nearly 900 images pertaining to Harvard Forest research available online to the public.

  19. Long-Term Surveillance Plan for the Burro Canyon Disposal Cell, Slick Rock, Colorado, DOE/AL/236, Revision 05/1998, May 1998

    Office of Legacy Management (LM)

    DOE/AL/62350-236~v'('/fl) ilWL I . LONG-TERM SURVEILLANCE PLAN -- FOR THE BURRO CANYON DISPOSAL CELL SLICK ROCK., COLORADO *- May 1998 J!f' 1 MASTER Uranium Mill Tailings Berr:ed.ial Action Project DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the

  20. Sherwood, Washington, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site This fact sheet provides information about the Sherwood, Washington, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Sherwood, Washington, Disposal Site Site Description and History The Sherwood disposal site is a former uranium-ore processing site operated by Western Nuclear, Inc. The site is in Stevens County near the

  1. Evaluating, Migrating, and Consolidating Databases and Applications for Long-Term Surveillance and Maintenance Activities at the Rocky Flats Site

    SciTech Connect (OSTI)

    Surovchak, S.; Marutzky, S.; Thompson, B.; Miller, K.; Labonte, E.

    2006-07-01

    The U.S. Department of Energy (DOE) Office of Legacy Management (LM) is assuming responsibilities for long-term surveillance and maintenance (LTS and M) activities at the Rocky Flats Environmental Technology Site (RFETS) during fiscal year 2006. During the transition, LM is consolidating databases and applications that support these various functions into a few applications which will streamline future management and retrieval of data. This paper discussed the process of evaluating, migrating, and consolidating these databases and applications for LTS and M activities and provides lessons learned that will benefit future transitions. (authors)

  2. Maxey Flats, Kentucky, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    3 Fact Sheet Maxey Flats, Kentucky, Disposal Site This fact sheet provides information about the Maxey Flats, Kentucky, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Maxey Flats, Kentucky, Disposal Site Site Description and History The Maxey Flats site is an inactive, low-level radioactive waste disposal site located in eastern Kentucky about 10

  3. Falls City, Texas, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Falls City, Texas, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Falls City, Texas. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Falls City Disposal Site Site Description and History The Falls City disposal site is the location of a former uranium-ore processing facility in Karnes County, Texas, approximately 40 miles southeast of San Antonio

  4. Monticello, Utah, Disposal and Processing Sites

    Office of Legacy Management (LM)

    Monticello, Utah, Disposal and Processing Sites This fact sheet provides information about the Monticello, Utah, Disposal and Processing Sites. These sites are managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Monticello, Utah, Disposal and Processing Sites Site Description and History The Monticello, Utah, Disposal and Processing Sites are located in and near the city of

  5. Long-Term Surveillance and Maintenance Requirements for Remediated...

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

    Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites Long-Term ...

  6. Plutonium Isotopes in the Terrestrial Environment at the Savannah River Site, USA. A Long-Term Study

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Armstrong, Christopher R.; Nuessle, Patterson R.; Brant, Heather A.; Hall, Gregory; Halverson, Justin E.; Cadieux, James R.

    2015-01-16

    This work presents the findings of a long term plutonium study at Savannah River Site (SRS) conducted between 2003 and 2013. Terrestrial environmental samples were obtained at Savannah River National Laboratory (SRNL) in A-area. Plutonium content and isotopic abundances were measured over this time period by alpha spectrometry and three stage thermal ionization mass spectrometry (3STIMS). Here we detail the complete sample collection, radiochemical separation, and measurement procedure specifically targeted to trace plutonium in bulk environmental samples. Total plutonium activities were determined to be not significantly above atmospheric global fallout. However, the 238Pu/239+240Pu activity ratios attributed to SRS are abovemore » atmospheric global fallout ranges. The 240Pu/239Pu atom ratios are reasonably consistent from year to year and are lower than fallout, while the 242Pu/239Pu atom ratios are higher than fallout values. Overall, the plutonium signatures obtained in this study reflect a mixture of weapons-grade, higher burn-up, and fallout material. This study provides a blue print for long term low level monitoring of plutonium in the environment.« less

  7. The Future Through the Past: The Use of Analog Sites for Design Criteria and Long Term Performance Assessment of Evapotranspiration Landfill Covers

    SciTech Connect (OSTI)

    Shafer, D. S.; Miller, J. J.; Young, M. H.; Edwards, S. C.; Rawlinson, S. E.

    2002-02-26

    There is growing support for using evapotranspiration (ET) covers for closure of low-level waste (LLW) and other types of waste disposal sites, particularly in the lower latitude arid regions of the western United States. At the Nevada Test Site (NTS), monolayer ET covers are the baseline technology for closure of LLW and mixed LLW cells. To better predict the long-term performance of monolayer ET covers, as well as to identify design criteria that will potentially improve their performance, the properties of, and processes occurring on, analog sites for ET covers on the NTS are being studied. The project is funded through the Subsurface Contaminants Focus Area of the U.S. Department of Energy. Four analog sites on the NTS have been selected to predict performance of ET covers over a 1,000-year compliance period. Two sites are relatively recently disturbed (within the last 50 years) and have been selected to evaluate processes and changes on ET covers for the early period after active cover maintenance is discontinued. Two other sites, late to mid-Holocene in age, are intended as analogs for the end of the compliance period (1,000 years or more); both surfaces are abandoned alluvial/colluvial deposits. The history of the early post-institutional control analog sites are being evaluated by an archaeologist to help determine when the sites were last disturbed or modified, and the mode of disturbance to help set baseline conditions. Similar to other ''landforms,'' ET covers will evolve over time because of pedogenic, biotic, and climatic processes. Properties of analog sites that could affect ET water balance performance will be evaluated to help understand ET cover performance over time.

  8. Long-Term Surveillance and Maintenance Plan for the U.S. Department of Energy Amchitka, Alaska, Site

    SciTech Connect (OSTI)

    2008-09-01

    This Long-Term Surveillance and Maintenance Plan describes how the U.S. Department of Energy (DOE) intends to fulfill its mission to maintain protection of human health and the environment at the Amchitka, Alaska, Site1. Three underground nuclear tests were conducted on Amchitka Island. The U.S. Department of Defense, in conjunction with the U.S. Atomic Energy Commission (AEC), conducted the first nuclear test (Long Shot) to provide data that would improve the United States' capability of detecting underground nuclear explosions. The second nuclear test (Milrow) was a weapons-related test conducted by AEC as a means to study the feasibility of detonating a much larger device. The final nuclear test (Cannikin), the largest United States underground test, was a weapons-related test. Surface disturbances associated with these tests have been remediated. However, radioactivity remains deep below the surface, contained in and around the test cavities, for which no feasible remediation technology has been identified. In 2006, the groundwater model (Hassan et al. 2002) was updated using 2005 data collected by the Consortium for Risk Evaluation with Stakeholder Participation. Model simulation results indicate there is no breakthrough or seepage of radionuclides into the marine environment within 2,000 years. The Amchitka conceptual model is reasonable; the flow and transport simulation is based on the best available information and data. The simulation results are a quantitative prediction supported by the best available science and technology. This Long-Term Surveillance and Maintenance Plan is an additional step intended for the protection of human health and the environment. This plan may be modified from time to time in the future consistent with the mission to protect human health

  9. Long-Term Surveillance Plan for the Collins Ranch Disposal Site...

    Office of Legacy Management (LM)

    ... and inspection checklist . . . . . . . . . . . . . ...LKVRTSPROCDISP LKVI 2-3 LOW-TERM SURVEYUNQ PUN FOR THE ... QA, quality control (OC), analytical data management. and ...

  10. LGRJ Interim Long-Term Surveillance Plan for the Cheney Disposal Site Near Grand Junction, Colorado

    Office of Legacy Management (LM)

  11. Rifle, Colorado, Processing Sites and Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    5 Fact Sheet UMTRCA Title I UMTRCA Title I Rifle, Colorado, Processing Sites and Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site near Rifle, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Rife Processing Sites and Disposal Site Site Description and History Two former uranium and vanadium processing sites are located near the

  12. Edgemont, South Dakota, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Edgemont, South Dakota, Disposal Site This fact sheet provides information about the Edgemont, South Dakota, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Edgemont, South Dakota, Disposal Site Site Description and History The former Edgemont uranium mill is located in Edgemont, South Dakota, in Fall River County near the southwest corner of South Dakota.

  13. Green River, Utah, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Green River, Utah, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site near Green River, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Green River, Utah, Disposal Site Site Description and History The Green River disposal site is about 0.5 mile east of the Green River and 1.5 miles southeast of the city of Green River, Utah. The site consists of an

  14. Slick Rock, Colorado, Processing Sites and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Slick Rock, Colorado, Processing Sites and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site at Slick Rock, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Slick Rock, Colorado, Processing and Disposal Sites Site Descriptions and History The Slick Rock processing sites consist of two former uranium- and vanadium-ore processing

  15. A groundwater flow and transport model of long-term radionuclide migration in central Frenchman flat, Nevada test site

    SciTech Connect (OSTI)

    Kwicklis, Edward Michael [Los Alamos National Laboratory; Becker, Naomi M [Los Alamos National Laboratory; Ruskauff, Gregory [NAVARRO-INTERA, LLC.; De Novio, Nicole [GOLDER AND ASSOC.; Wilborn, Bill [US DOE NNSA NSO

    2010-11-10

    A set of groundwater flow and transport models were created for the Central Testing Area of Frenchman Flat at the former Nevada Test Site to investigate the long-term consequences of a radionuclide migration experiment that was done between 1975 and 1990. In this experiment, radionuclide migration was induced from a small nuclear test conducted below the water table by pumping a well 91 m away. After radionuclides arrived at the pumping well, the contaminated effluent was discharged to an unlined ditch leading to a playa where it was expected to evaporate. However, recent data from a well near the ditch and results from detailed models of the experiment by LLNL personnel have convincingly demonstrated that radionuclides from the ditch eventually reached the water table some 220 m below land surface. The models presented in this paper combine aspects of these detailed models with concepts of basin-scale flow to estimate the likely extent of contamination resulting from this experiment over the next 1,000 years. The models demonstrate that because regulatory limits for radionuclide concentrations are exceeded only by tritium and the half-life of tritium is relatively short (12.3 years), the maximum extent of contaminated groundwater has or will soon be reached, after which time the contaminated plume will begin to shrink because of radioactive decay. The models also show that past and future groundwater pumping from water supply wells within Frenchman Flat basin will have negligible effects on the extent of the plume.

  16. DOE Issues Final Mercury Storage Environmental Impact Statement: Texas Site Is Preferred for Long-Term Mercury Storage

    Broader source: Energy.gov [DOE]

    WASHINGTON – The Department of Energy has prepared a Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement to analyze the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven locations

  17. Disposal Practices at the Nevada Test Site 2008 | Department...

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

    Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download PDF icon Disposal ...

  18. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    SciTech Connect (OSTI)

    2013-11-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

  19. DOE - Office of Legacy Management -- Commercial (Burial) Disposal Site

    Office of Legacy Management (LM)

    Maxey Flats Disposal Site - KY 02 Commercial (Burial) Disposal Site Maxey Flats Disposal Site - KY 02 FUSRAP Considered Sites Site: Commercial (Burial) Disposal Site, Maxey Flats Disposal Site (KY.02) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Maxey Flats, Kentucky, Site Documents Related to Commercial (Burial) Disposal Site,

  20. A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford

    SciTech Connect (OSTI)

    Neeway, James J.; Pierce, Eric M.; Freedman, Vicky L.; Ryan, Joseph V.; Qafoku, Nikolla

    2014-08-04

    The federal facilities located on the Hanford Site in southeastern Washington State have been used extensively by the U.S. government to produce nuclear materials for the U.S. strategic defense arsenal. Currently, the Hanford Site is under the stewardship of the U.S. Department of Energy (DOE) Office of Environmental Management (EM). A large inventory of radioactive and mixed waste resulting from the production of nuclear materials has accumulated, mainly in 177 underground single- and double-shell tanks located in the central plateau of the Hanford Site (Mann et al., 2001). The DOE-EM Office of River Protection (ORP) is proceeding with plans to immobilize and permanently dispose of the low-activity waste (LAW) fraction onsite in a shallow subsurface disposal facility (the Integrated Disposal Facility [IDF]). Pacific Northwest National Laboratory (PNNL) was contracted to provide the technical basis for estimating radionuclide release from the engineered portion of the IDF (the source term) as part of an immobilized low-activity waste (ILAW) glass testing program to support future IDF performance assessments (PAs).

  1. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    SciTech Connect (OSTI)

    2014-03-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

  2. Bluewater, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    ... Much of the remainder of the site is covered with fne-grained material deposited by wind and water. The region around the disposal site is sparsely populated, and the main land use ...

  3. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant

    Office of Environmental Management (EM)

    OH EM Project: On-Site Disposal Facility ETR Report Date: February 2008 ETR-12 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did This Review The On-Site Waste Disposal Facility (OSWDF) is proposed for long-term containment of contaminated materials from the planned Decontamination and Decommissioning (D&D) activities at the

  4. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Green River, Utah Page 7-1 7.0 Green River, Utah, Disposal Site 7.1 Compliance Summary The Green River, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on March 18, 2015. The disposal cell was in excellent condition. One missing perimeter sign was replaced during the inspection. Inspectors identified no other maintenance needs or cause for a follow-up or contingency inspection. 7.2 Compliance Requirements Requirements for the long-term surveillance

  5. Grand Junction, Colorado, Processing Site and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Grand Junction, Colorado, Disposal and Processing Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal and processing sites at Grand Junction, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Grand Junction, Colorado, Sites Site Description and History The former Grand Junction processing site, historically known as the Climax uranium mill, sits at an elevation of

  6. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 0913 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 0913 North Face Cell 1 North ...

  7. Sandia National Laboratories: Long-term Stewardship

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

    Long-term Stewardship Environmental Management System Pollution Prevention Information Repository Index Long-term Stewardship About Long-term Stewardship Groundwater sampling The goal of the LTS Program is the long-term protection of human health and the environment from hazards associated with residual contamination at former Environmental Restoration Project (ER) sites, and minimization of Sandia's environmental liability by ensuring environmental compliance with the requirements provided in

  8. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Slick Rock, Colorado Page 17-1 17.0 Slick Rock, Colorado, Disposal Site 17.1 Compliance Summary The Slick Rock, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on May 12, 2015. The site was in good condition. Inspectors identified contact information that needed updating on the entrance sign; no other maintenance needs or cause for a follow-up inspection was required. 17.2 Compliance Requirements Requirements for the long-term surveillance and

  9. Title I Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    I Disposal Sites Annual Report Title I Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) More Documents & Publications Title II

  10. Title II Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    II Disposal Sites Annual Report Title II Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) More Documents & Publications Title I

  11. Disposal Practices at the Savannah River Site | Department of...

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

    Practices at the Savannah River Site Disposal Practices at the Savannah River Site Full Document and Summary Versions are available for download PDF icon Disposal Practices at the ...

  12. Erosion Control and Revegetation at DOE's Lowman Disposal Site...

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

    Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and ...

  13. Nevada Industrial Solid Waste Disposal Site Permit Application...

    Open Energy Info (EERE)

    Nevada Industrial Solid Waste Disposal Site Permit Application Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Nevada Industrial Solid Waste Disposal Site...

  14. Quantification of key long-term risks at CO? sequestration sites: Latest results from US DOE's National Risk Assessment Partnership (NRAP) Project

    SciTech Connect (OSTI)

    Pawar, Rajesh; Bromhal, Grant; Carroll, Susan; Chu, Shaoping; Dilmore, Robert; Gastelum, Jason; Oldenburg, Curt; Stauffer, Philip; Zhang, Yingqi; Guthrie, George

    2014-12-31

    Risk assessment for geologic CO? storage including quantification of risks is an area of active investigation. The National Risk Assessment Partnership (NRAP) is a US-Department of Energy (US-DOE) effort focused on developing a defensible, science-based methodology and platform for quantifying risk profiles at geologic CO? sequestration sites. NRAP has been developing a methodology that centers round development of an integrated assessment model (IAM) using system modeling approach to quantify risks and risk profiles. The IAM has been used to calculate risk profiles with a few key potential impacts due to potential CO? and brine leakage. The simulation results are also used to determine long-term storage security relationships and compare the long-term storage effectiveness to IPCC storage permanence goal. Additionally, we also demonstrate application of IAM for uncertainty quantification in order to determine parameters to which the uncertainty in model results is most sensitive.

  15. Quantification of key long-term risks at CO₂ sequestration sites: Latest results from US DOE's National Risk Assessment Partnership (NRAP) Project

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Pawar, Rajesh; Bromhal, Grant; Carroll, Susan; Chu, Shaoping; Dilmore, Robert; Gastelum, Jason; Oldenburg, Curt; Stauffer, Philip; Zhang, Yingqi; Guthrie, George

    2014-12-31

    Risk assessment for geologic CO₂ storage including quantification of risks is an area of active investigation. The National Risk Assessment Partnership (NRAP) is a US-Department of Energy (US-DOE) effort focused on developing a defensible, science-based methodology and platform for quantifying risk profiles at geologic CO₂ sequestration sites. NRAP has been developing a methodology that centers round development of an integrated assessment model (IAM) using system modeling approach to quantify risks and risk profiles. The IAM has been used to calculate risk profiles with a few key potential impacts due to potential CO₂ and brine leakage. The simulation results are alsomore » used to determine long-term storage security relationships and compare the long-term storage effectiveness to IPCC storage permanence goal. Additionally, we also demonstrate application of IAM for uncertainty quantification in order to determine parameters to which the uncertainty in model results is most sensitive.« less

  16. EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on site, and two off-site management alternatives.

  17. Tuba City, Arizona, Disposal Site Community Information

    Office of Legacy Management (LM)

    C O M M U N I T Y I N F O R M A T I O N Tuba City, Arizona, Disposal Site Tuba City Site Background 1954-1955 Tuba City mill is built. 1956-1966 Rare Metals Corporation and El Paso Natural Gas Company operate the uranium- and vanadium-ore processing mill. Chemicals from tailings piles and ponds leak into the soil and groundwater during milling operations. 1988 U.S. Department of Energy (DOE) cleans up materials from former milling operations. 1990 Mill tailings are placed in a disposal cell. A

  18. Innovative Technique Accelerates Waste Disposal at Idaho Site

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for permanent disposal.

  19. Shirley Basin South, Wyoming, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Shirley Basin South, Wyoming, Disposal Site This fact sheet provides information about the Shirley Basin South, Wyoming, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Shirley Basin South, Wyoming, Disposal Site Site Description and History The Shirley Basin South disposal site is located in rural Carbon County about 60 miles south of Casper and 35 miles

  20. A Serendipitous, Long-Term Infiltration Experiment: Water and Tritium Circulation Beneath the CAMBRIC Ditch at the Nevada Test Site

    SciTech Connect (OSTI)

    Maxwell, R M; Tompson, A B; Kollet, S J

    2008-11-20

    Underground nuclear weapons testing at the Nevada Test Site introduced numerous radionuclides that may be used to characterize subsurface hydrologic transport processes in arid climates. A sixteen year pumping experiment designed to examine radionuclide migration away from the CAMBRIC nuclear test, conducted in groundwater beneath Frenchman Flat in 1965, gave rise to an unintended second experiment involving radionuclide infiltration through the vadose zone, as induced by seepage of pumping effluents beneath an unlined discharge trench. The combined experiments have been reanalyzed using a detailed, three-dimensional numerical model of transient, variably saturated flow and mass transport, tailored specifically for large scale and efficient calculations. Simulations have been used to estimate radionuclide travel and residence times in various parts of the system for comparison with observations in wells. Model predictions of mass transport were able to clearly demonstrate radionuclide recycling behavior between the ditch and pumping well previously suggested by isotopic age dating information; match travel time estimates for radionuclides moving between the ditch, the water table, and monitoring wells; and provide more realistic ways in which to interpret the pumping well elution curves. Collectively, the results illustrate the utility of integrating detailed numerical modeling with diverse observational data in developing accurate interpretations and forecasts of contaminant migration processes.

  1. Evaluation of a deposit in the vicinity of the PBU L-106 Site, North Slope, Alaska, for a potential long-term test of gas production from hydrates

    SciTech Connect (OSTI)

    Moridis, G.J.; Reagan, M.T.; Boyle, K.L.; Zhang, K.

    2010-05-01

    As part of the effort to investigate the technical feasibility of gas production from hydrate deposits, a long-term field test (lasting 18-24 months) is under consideration in a project led by the U.S. Department of Energy. We evaluate a candidate deposit involving the C-Unit in the vicinity of the PBU-L106 site in North Slope, Alaska. This deposit is stratigraphically bounded by impermeable shale top and bottom boundaries (Class 3), and is characterized by high intrinsic permeabilities, high porosity, high hydrate saturation, and a hydrostatic pressure distribution. The C-unit deposit is composed of two hydrate-bearing strata separated by a 30-ft-thick shale interlayer, and its temperatrure across its boundaries ranges between 5 and 6.5 C. We investigate by means of numerical simulation involving very fine grids the production potential of these two deposits using both vertical and horizontal wells. We also explore the sensitivity of production to key parameters such as the hydrate saturation, the formation permeability, and the permeability of the bounding shale layers. Finally, we compare the production performance of the C-Unit at the PBU-L106 site to that of the D-Unit accumulation at the Mount Elbert site, a thinner, single-layer Class 3 deposit on the North Slope of Alaska that is shallower, less-pressurized and colder (2.3-2.6 C). The results indicate that production from horizontal wells may be orders of magnitude larger than that from vertical ones. Additionally, production increases with the formation permeability, and with a decreasing permeability of the boundaries. The effect of the hydrate saturation on production is complex and depends on the time frame of production. Because of higher production, the PBU-L106 deposit appears to have an advantage as a candidate for the long-term test.

  2. Durango, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Durango, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Durango, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Durango Processing and Disposal Sites Site Description and History The Durango processing site is a former uranium-ore processing facility located a quarter of a mile southwest of

  3. Naturita, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Naturita, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Naturita, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Naturita, Colorado, Processing and Disposal Sites Site Description and History The Naturita processing site is a former uranium- and vanadium-ore processing facility in western

  4. Long-Term Surveillance Plan for the Spook, Wyoming, Disposal Site, UMTRA-DOE-AL-350215.0000, January 1993

    Office of Legacy Management (LM)

  5. Application of Probabilistic Performance Assessment Modeling for Optimization of Maintenance Studies for Low-Level Radioactive Waste Disposal Sites at the Nevada Test Site

    SciTech Connect (OSTI)

    Crowe, B.; Yucel, V.; Rawlinson, S.; Black, P.; Carilli, J.; DiSanza, F.

    2002-02-25

    The U.S. Department of Energy (DOE), National Nuclear Security Administration of the Nevada Operations Office (NNSA/NV) operates and maintains two active facilities on the Nevada Test Site (NTS) that dispose defense-generated low-level radioactive waste (LLW), mixed radioactive waste, and ''classified waste'' in shallow trenches and pits. The operation and maintenance of the LLW disposal sites are self-regulated by the DOE under DOE Order 435.1. This Order requires formal review of a performance assessment (PA) and composite analysis (CA; assessment of all interacting radiological sources) for each LLW disposal system followed by an active maintenance program that extends through and beyond the site closure program. The Nevada disposal facilities continue to receive NTS-generated LLW and defense-generated LLW from across the DOE complex. The PA/CAs for the sites have been conditionally approved and the facilities are now under a formal maintenance program that requires testing of conceptual models, quantifying and attempting to reduce uncertainty, and implementing confirmatory and long-term background monitoring, all leading to eventual closure of the disposal sites. To streamline and reduce the cost of the maintenance program, the NNSA/NV is converting the deterministic PA/CAs to probabilistic models using GoldSim, a probabilistic simulation computer code. The output of probabilistic models will provide expanded information supporting long-term decision objectives of the NTS disposal sites.

  6. Assessment of alternatives for long-term management of uranium ore residues and contaminated soils located at DOE's Niagara Falls Storage Site

    SciTech Connect (OSTI)

    Merry-Libby, P.

    1984-11-05

    About 11,000 m/sup 3/ of uranium ore residues and 180,000 m/sup 3/ of wastes (mostly slightly contaminated soils) are consolidated within a diked containment area at the Niagara Falls Storage Site (NFSS) located about 30 km north of Buffalo, NY. The residues account for less than 6% of the total volume of contaminated materials but almost 99% of the radioactivty. The average /sup 226/Ra concentration in the residues is 67,000 pCi/g. Several alternatives for long-term management of the wastes and residues are being considered, including: improvement of the containment at NFSS, modification of the form of the residues, management of the residues separately from the wastes, management of the wastes and residues at another humid site (Oak Ridge, TN) or arid site (Hanford, WA), and dispersal of the wastes in the ocean. Potential radiological risks are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant impacts on the ocean environment or pose any significant radiological risk to humans. It will be necessary to take perpetual care of the near-surface burial sites because the residues and wastes will remain hazardous for thousands of years. If controls cease, the radioactive materials will eventually be dispersed in the environment. Predicted loss of the earthen covers over the buried materials ranges from several hundred to more than two million years, depending primarily on the use of the land surface. Groundwater will eventually be contaminated in all alternatives; however, the groundwater pathway is relatively insignificant with respect to radiological risks to the general population. A person intruding into the residues would incur an extremely high radiation dose.

  7. Hanford Site waste treatment/storage/disposal integration

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    1999-02-24

    In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

  8. Gunnison, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Gunnison, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site at Gunnison, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Location of the Gunnison, Colorado, Sites Site Description and History The Gunnison, Colorado, Processing Site is a former uranium-ore processing site on a 61.5-acre tract of land adjacent to the

  9. Final Scientific/Technical Report--In-Situ Generation of Iron-Chromium Precipitates for Long Term Immobilization of Chromium at the Hanford Site

    SciTech Connect (OSTI)

    Butler, Elizabeth C.; Krumholz, Lee R.; Madden, Andrew S.; Hansel, Colleen M.

    2013-12-13

    Hexavalent chromium (Cr(VI)) is a toxic ground water contaminant widespread at the Hanford site and many other industrial facilities. A common remediation method for Cr(VI) is in situ reduction/immobilization, in which soluble Cr(VI) is reduced to the less soluble trivalent Cr (Cr(III)). If iron (Fe) minerals are present during the process, Cr(III) precipitates as a mixed Fe(III)-Cr(III) (Fe-Cr) solid. The objective of this exploratory research was to obtain preliminary evidence about the relationships among the method of Cr(VI) reduction (i.e., abiotic or microbial), the properties of the resulting Fe-Cr precipitates, and their tendencies to release soluble Cr(VI) in the presence of the common manganese oxide birnessite. The results of this exploratory research project show that the conditions of Cr(VI) reduction—specifically the ratio of Cr to Fe, and/or whether the Cr(VI) reductant is a mineral or a microorganism—can significantly affect the tendency of the resulting Fe-Cr precipitate to release Cr(VI) to the environment in the presence of birnessite. These results suggest the chosen remediation conditions have the potential to strongly influence not only the initial success of in situ Cr(VI) reduction/immobilization, but also the potential for successful long term sequestration of Cr in the form of stable soil precipitates.

  10. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    8947.1 09/13 On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 09/13 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 09/13 North Face Cell 1 North Drainage (looking west) 6319D-6206 6319D-6205 8947.4 09/13 East Face Cell 2 West Face Cell 2 6319D-6230 6319D-6209 8947.5 09/13 East Face Cell 3 West Face Cell 3 6319D-6229 6319D-6210 8947.6 09/13 East Face Cell 4 West Face Cell 4 6319D-6227 6319D-62111 8947.7 09/13 East Face Cell 5 West Face Cell 5 6319D-6226

  11. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    72.1 06/14 On-Site Disposal Facility Inspection Report June 2014 6319-D6320 8972.2 06/14 East Face Cell 1 West Face Cell 1 6319D-6322 6319D-6346 8972.3 06/14 North Face Cell 1 North Drainage (looking west) 6319D-6321 6319D-6320 8972.4 06/14 East Face Cell 2 West Face Cell 2 6319D-6345 6319D-6324 8972.5 06/14 East Face Cell 3 West Face Cell 3 6319D-6344 6319D-6325 8972.6 06/14 East Face Cell 4 West Face Cell 4 6319D-6342 6319D-63261 8972.7 06/14 East Face Cell 5 West Face Cell 5 6319D-6341

  12. Long-Term Surveillance and Maintenance Requirements for Remediated...

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

    Requirements for Remediated FUSRAP Sites Long-Term Surveillance and Maintenance ... to the U.S. Department of Energy (DOE) for long-term surveillance and maintenance (LTS&M). ...

  13. Tuba City, Arizona, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    ... A lined solar evaporation pond receives the waste liquid (brine) and the softener ... Disposal Cell Design The fve-sided disposal cell occupies an area of 50 acres on the ...

  14. Radionuclide disequilibria studies for investigating the integrity of potential nuclear waste disposal sites: subseabed studies.

    SciTech Connect (OSTI)

    Laul, J.C.; Thomas, C.W.; Petersen, M.R.; Perkins, R.W.

    1981-09-01

    This study of subseabed sediments indicates that natural radionuclides can be employed to define past long-term migration rates and thereby evaluate the integrity of potential disposal sites in ocean sediments. The study revealed the following conclusions: (1) the sedimentation rate of both the long and short cores collected in the North Pacific is 2.5 mm/1000 yr or 2.5 m/m.yr in the upper 3 meters; (2) the sedimentation rate has been rather constant over the last one million years; and (3) slow diffusive processes dominate within the sediment. Reworking of the sediment by physical processes or organisms is not observed.

  15. Long-Term Stewardship Resource Center | Department of Energy

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

    Long-Term Stewardship Resource Center Long-Term Stewardship Resource Center WELCOME TO THE DEPARTMENT OF ENERGY'S LONG-TERM STEWARDSHIP RESOURCE CENTER The purpose of this web site is to provide the public and the Department of Energy's (DOE) community with a variety of information resources for long-term stewardship (LTS) responsibilities. LTS includes the physical controls, institutions, information and other mechanisms needed to ensure protection of people and the environment at sites or

  16. Changes in Vegetation at the Monticello, Utah, Disposal Site...

    Energy Savers [EERE]

    the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site Monitoring the Performance of an Alternative Cover Using Caisson...

  17. Ocean disposal option for bulk wastes containing naturally occurring radionuclides: an assessment case history. [From Niagara Falls storage site

    SciTech Connect (OSTI)

    Stull, E.A.; Merry-Libby, P.

    1985-01-01

    There are 180,000 m/sup 3/ of slightly contaminated radioactive wastes (36 pCi/g radium-226) currently stored at the US Department of Energy's Niagara Falls Storage Site (NFSS), near Lewiston, New York. These wastes resulted from the cleanup of soils that were contaminated above the guidelines for unrestricted use of property. An alternative to long-term management of these wastes on land is dispersal in the ocean. A scenario for ocean disposal is present

  18. Summary - Disposal Practices at the Nevada Test Site

    Energy Savers [EERE]

    Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been

  19. LANL completes excavation of 1940s waste disposal site

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

    LANL completes excavation LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 22, 2011 Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation. Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, September 22, 2011-Los Alamos

  20. Disposal Practices at the Nevada Test Site 2008

    Office of Environmental Management (EM)

    Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other ...

  1. Summary - Disposal Practices at the Savannah River Site

    Office of Environmental Management (EM)

    Nevada Test Site, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5.

  2. Deep Borehole Disposal Research: Demonstration Site Selection...

    Office of Environmental Management (EM)

    The deep borehole disposal concept consists of drilling a borehole on the order of 5,000 m deep, emplacing waste canisters in the lower part of the borehole, and sealing the upper ...

  3. Long-Term Stewardship Study

    Energy Savers [EERE]

    Environmental Management Office of Long Term Stewardship LONG-TERM STEWARDSHIP STUDY Volume I - Report Prepared to comply with the terms of a settlement agreement: Natural Resources Defense Council, et al. v. Richardson, et al., Civ. No. 97-936 (SS) (D.D.C. Dec. 12, 1998). Final Study October 2001 - i - Foreword The Department of Energy (DOE) has prepared this Long-term Stewardship Study ("Study" or "Final Study") to comply with the terms of a settlement agreement between

  4. COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE

    SciTech Connect (OSTI)

    Colarusso, Angela; Crowe, Bruce; Cochran, John R.

    2003-02-27

    Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance assessment, inclusion of dose calculations from collocated low-level waste in the boreholes for the individual protection requirements, further assessments of engineered barriers and conditions associated with the assurance requirements, and expansion of documentation provided for assessing the groundwater protection requirements. The Transuranic Waste Disposal Federal Review Group approved the performance assessment for Greater Confinement Disposal boreholes in 2001 and did not approve the Application of the Assurance Requirements. Remaining issues concerned with engineered barriers and the multiple aspects of the Assurance Requirements will be resolved at the time of closure of the Area 5 Radioactive Waste Management Site. This is the first completion and acceptance of a performance assessment for transuranic materials under the U.S. Department of Energy self-regulation. The Greater Confinement Disposal boreholes are only the second waste disposal configuration to meet the safety regulatory requirements of 40 CFR 191.

  5. Mexican Hat, Utah, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    The U.S. Department of Energy (DOE) completed surface remedial action at the site in 1995. ... operations, the natural water quality near the site is unsuitable for human consumption. ...

  6. Canonsburg, Pennsylvania, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Processing operations at the site ceased in 1957. For the next 9 years, the site was used ... In recent years, uranium concentrations in groundwater samples collected beneath Area C ...

  7. Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP

    Energy Savers [EERE]

    Sites | Department of Energy Requirements for Remediated FUSRAP Sites Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP Sites This document summarizes radiological conditions at sites remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP) and transferred to the U.S. Department of Energy (DOE) for long-term surveillance and maintenance (LTS&M). Source document citations are presented. Most of these sites meet criteria for unrestricted use; a

  8. Spook, Wyoming, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    site. The floor of the open-pit mine was leveled and a 3-foot-thick layer of low-permeability material was placed in the bottom of the pit. The pit was backfilled with...

  9. DOE - Office of Legacy Management -- Maybell Mill Site - CO 0...

    Office of Legacy Management (LM)

    Cell Design, and Program Act Long-Term Surveillance Plan for the Maybell, Colorado (UMTRCA Title I) Disposal Site Moffat County, Colorado April 2008 Office of Legacy Management

  10. Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

    SciTech Connect (OSTI)

    Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H.; Price, L.L.

    1997-09-01

    This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd{sup 3} (4,580 m{sup 3}) of glass gems prior to disposal. This report documents Sandia National Laboratories` preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment.

  11. Potential long-term chemical effects of diesel fuel emissions on a mining environment: A preliminary assessment based on data from a deep subsurface tunnel at Rainer Mesa, Nevada test site

    SciTech Connect (OSTI)

    Meike, A.; Bourcier, W.L.; Alai, M.

    1995-09-01

    The general purpose of the Yucca Mountain Site Characterization Project (YMSCP) Introduced Materials Task is to understand and predict potential long-term modifications of natural water chemistry related to the construction and operation of a radioactive waste repository that may significantly affect performance of the waste packages. The present study focuses on diesel exhaust. Although chemical information on diesel exhaust exists in the literature, it is either not explicit or incomplete, and none of it establishes mechanisms that might be used to predict long-term behavior. In addition, the data regarding microbially mediated chemical reactions are not well correlated with the abiotic chemical data. To obtain some of the required long-term information, we chose a historical analog: the U12n tunnel at Rainier Mesa, Nevada Test Site. This choice was based on the tunnel`s extended (30-year) history of diesel usage, its geological similarity to Yucca Mountain, and its availability. The sample site within the tunnel was chosen based on visual inspection and on information gathered from miners who were present during tunnel operations. The thick layer of dark deposit at that site was assumed to consist primarily of rock powder and diesel exhaust. Surface samples and core samples were collected with an intent to analyze the deposit and to measure potential migration of chemical components into the rock. X-ray diffraction (XRD), x-ray fluorescence (XRF), scanning electron microscopy (SEM) with energy dispersive spectra (EDS) analysis, secondary-ion mass spectrometry (SIMS), and Fourier transform infrared (FTIR) analysis were used to measure both spatial distribution and concentration for the wide variety of chemical components that were expected based on our literature survey.

  12. US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges

    SciTech Connect (OSTI)

    Seitz, Roger R.; Suttora, Linda C.; Phifer, Mark

    2014-03-01

    On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the assumptions used for performance assessments and risk assessments (PA/RAs) for on-site disposal cells, requirements and assumptions related to assessment of inadvertent intrusion, DOE Manual 435.1-1 requirements, and approaches for consideration of the long-term performance of liners and covers in the context of PAs. The working group has improved communication among the staff and oversight personnel responsible for onsite disposal cells and has provided a forum to identify and resolve common concerns.

  13. Long Term Care | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Care icon Federal employees can elect to participate in the Federal Long Term Care Insurance Program (FLTCIP) which provides long term care insurance to Federal employees,...

  14. Demonstrating the Safety of Long-Term Dry Storage - 13468

    SciTech Connect (OSTI)

    McCullum, Rod; Brookmire, Tom; Kessler, John; Leblang, Suzanne; Levin, Adam; Martin, Zita; Nesbit, Steve; Nichol, Marc; Pickens, Terry

    2013-07-01

    Commercial nuclear plants in the United States were originally designed with the expectation that used nuclear fuel would be moved directly from the reactor pools and transported off site for either reprocessing or direct geologic disposal. However, Federal programs intended to meet this expectation were never able to develop the capability to remove used fuel from reactor sites - and these programs remain stalled to this day. Therefore, in the 1980's, with reactor pools reaching capacity limits, industry began developing dry cask storage technology to provide for additional on-site storage. Use of this technology has expanded significantly since then, and has today become a standard part of plant operations at most US nuclear sites. As this expansion was underway, Federal programs remained stalled, and it became evident that dry cask systems would be in use longer than originally envisioned. In response to this challenge, a strong technical basis supporting the long term dry storage safety has been developed. However, this is not a static situation. The technical basis must be able to address future challenges. Industry is responding to one such challenge - the increasing prevalence of high burnup (HBU) used fuel and the need to provide long term storage assurance for these fuels equivalent to that which has existed for lower burnup fuels over the past 25 years. This response includes a confirmatory demonstration program designed to address the aging characteristics of HBU fuel and set a precedent for a learning approach to aging management that will have broad applicability across the used fuel storage landscape. (authors)

  15. Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous...

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

    Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Full Document and Summary Versions...

  16. Upcoming Long-Term Operating Schedule

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

    Upcoming Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  17. Upcoming Long-Term Operating Schedule

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

    Upcoming Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  18. Upcoming Long-Term Operating Schedule

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

    Upcoming Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  19. Current Long-Term Operating Schedule

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

    Current Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  20. Current Long-Term Operating Schedule

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

    Current Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  1. Current Long-Term Operating Schedule

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

    Current Long-Term Operating Schedule Print This schedule is also available as an .xls spreadsheet.

  2. Long-term control of root growth

    DOE Patents [OSTI]

    Burton, Frederick G.; Cataldo, Dominic A.; Cline, John F.; Skiens, W. Eugene

    1992-05-26

    A method and system for long-term control of root growth without killing the plants bearing those roots involves incorporating a 2,6-dinitroaniline in a polymer and disposing the polymer in an area in which root control is desired. This results in controlled release of the substituted aniline herbicide over a period of many years. Herbicides of this class have the property of preventing root elongation without translocating into other parts of the plant. The herbicide may be encapsulated in the polymer or mixed with it. The polymer-herbicide mixture may be formed into pellets, sheets, pipe gaskets, pipes for carrying water, or various other forms. The invention may be applied to other protection of buried hazardous wastes, protection of underground pipes, prevention of root intrusion beneath slabs, the dwarfing of trees or shrubs and other applications. The preferred herbicide is 4-difluoromethyl-N,N-dipropyl-2,6-dinitro-aniline, commonly known as trifluralin.

  3. Long-term Performance of Engineered Barrier Systems (PEBS) - An International EURATOM Project on the Study and Testing of Engineered Barriers for the Final Disposal of HAW Using PEBS as an Example - 13299

    SciTech Connect (OSTI)

    Mente, M.

    2013-07-01

    The main aim of the PEBS project is to evaluate the sealing and barrier performance of the EBS over time, through development of a comprehensive approach involving experiments, model development, and consideration of the potential impacts on long-term safety functions. The experiments and models cover the full range of conditions, from initial emplacement of wastes (high heat generation and EBS re-saturation) through to later stage establishment of near steady state conditions, i.e. full re-saturation and thermal equilibrium with the host rock. These aspects will be integrated in a manner that will lead to greater certainty and thus greater confidence regarding the development from the initial transient state of the EBS to its long-term state, which provides the required isolation of the wastes. The work proposed within the project builds on existing knowledge and experience generated during recent years and supported by ongoing national and EC research programs. The project aims to provide a more complete description of the THM and THMC (thermo-hydro-mechanical- chemical) evolution of the EBS system, a more quantitative basis for relating the evolutionary behavior to the safety functions of the system, and a further clarification of the significance of residual uncertainties for long-term performance assessment. The importance of uncertainties arising from potential disagreement between the process models and the laboratory and in-situ experiments to be performed within PEBS, and their implications for an extrapolation of the results, will be reviewed, with particular emphasis on possible impacts on safety functions. In addition to the scientific-technical aims, the consortium will disseminate the basic findings to the broad scientific community within the EU, China and Japan, use expertise gained for public information purposes, and promote knowledge and technology transfer through training. (authors)

  4. Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-07-31

    Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

  5. Savannah River Site waste vitrification projects initiated throughout the United States: Disposal and recycle options

    SciTech Connect (OSTI)

    Jantzen, C.M.

    2000-04-10

    A vitrification process was developed and successfully implemented by the US Department of Energy's (DOE) Savannah River Site (SRS) and at the West Valley Nuclear Services (WVNS) to convert high-level liquid nuclear wastes (HLLW) to a solid borosilicate glass for safe long term geologic disposal. Over the last decade, SRS has successfully completed two additional vitrification projects to safely dispose of mixed low level wastes (MLLW) (radioactive and hazardous) at the SRS and at the Oak Ridge Reservation (ORR). The SRS, in conjunction with other laboratories, has also demonstrated that vitrification can be used to dispose of a wide variety of MLLW and low-level wastes (LLW) at the SRS, at ORR, at the Los Alamos National Laboratory (LANL), at Rocky Flats (RF), at the Fernald Environmental Management Project (FEMP), and at the Hanford Waste Vitrification Project (HWVP). The SRS, in conjunction with the Electric Power Research Institute and the National Atomic Energy Commission of Argentina (CNEA), have demonstrated that vitrification can also be used to safely dispose of ion-exchange (IEX) resins and sludges from commercial nuclear reactors. In addition, the SRS has successfully demonstrated that numerous wastes declared hazardous by the US Environmental Protection Agency (EPA) can be vitrified, e.g. mining industry wastes, contaminated harbor sludges, asbestos containing material (ACM), Pb-paint on army tanks and bridges. Once these EPA hazardous wastes are vitrified, the waste glass is rendered non-hazardous allowing these materials to be recycled as glassphalt (glass impregnated asphalt for roads and runways), roofing shingles, glasscrete (glass used as aggregate in concrete), or other uses. Glass is also being used as a medium to transport SRS americium (Am) and curium (Cm) to the Oak Ridge Reservation (ORR) for recycle in the ORR medical source program and use in smoke detectors at an estimated value of $1.5 billion to the general public.

  6. Classified Component Disposal at the Nevada National Security Site

    SciTech Connect (OSTI)

    Poling, J.; Arnold, P.; Saad, M.; DiSanza, F.; Cabble, K.

    2012-11-05

    The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012.

  7. Update on DOE/NNSA Long Term Stewardship Programs

    Broader source: Energy.gov [DOE]

    At the August 13, 2014 Committee meeting Tom Longo DOE, Explained What the Office of Legacy Management Does and how the Sites Across the DOE Complex are Managed for Long Term Stewardship.

  8. 1994 Characterization report for the state approved land disposal site

    SciTech Connect (OSTI)

    Swanson, L.C.

    1994-09-19

    This report summarizes the results of characterization activities at the proposed state-approved land disposal site (SALDS); it updates the original characterization report with studies completed since the first characterization report. The initial characterization report discusses studies from two characterization boreholes, 699-48-77A and 699-48-77B. This revision includes data from implementation of the Groundwater Monitoring Plan and the Aquifer Test Plan. The primary sources of data are two down-gradient groundwater monitoring wells, 699-48-77C and 699-48-77D, and aquifer testing of three zones in well 699-48-77C. The SALDS is located on the Hanford Site, approximately 183 m north of the 200 West Area on the north side of the 200 Areas Plateau. The SALDS is an infiltration basin proposed for disposal of treated effluents from the 200 Areas of Hanford.

  9. The U.S. regulatory framework for long-term management of uranium mill tailings

    SciTech Connect (OSTI)

    Smythe, C.; Bierley, D.; Bradshaw, M.

    1995-03-01

    The US established the regulatory structure for the management, disposal, and long-term care of uranium mill tailings in 1978 with the passage of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (Pub. L. 95-604). This legislation has governed the cleanup and disposal of uranium tailings at both inactive and active sites. The passage of the UMTRCA established a federal regulatory program for the cleanup and disposal of uranium mill tailings in the US. This program involves the DOE, the NRC, the EPA, various states and tribal governments, private licensees, and the general public. The DOE has completed surface remediation at 14 sites, with the remaining sites either under construction or in planning. The DOE`s UMTRA Project has been very successful in dealing with public and agency demands, particularly regarding disposal site selection and transportation issues. The active sites are also being cleaned up, but at a slower pace than the inactive sites, with the first site tentatively scheduled for completion in 1996.

  10. Long-term Contract Information and Registrations

    Broader source: Energy.gov [DOE]

    DOE/FE orders granting long-term authorization to export liquefied natural gas by vessel require authorization holders to file long-term contract information with DOE/FE for LNG exports and long...

  11. Long-Term Stewardship Baseline Report and Transition Guidance

    SciTech Connect (OSTI)

    Kristofferson, Keith

    2001-11-01

    Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after facility cleanup is complete. As the Department of Energys (DOE) lead laboratory for environmental management programs, the Idaho National Engineering and Environmental Laboratory (INEEL) administers DOEs long-term stewardship science and technology efforts. The INEEL provides DOE with technical, and scientific expertise needed to oversee its long-term environmental management obligations complexwide. Long-term stewardship is administered and overseen by the Environmental Management Office of Science and Technology. The INEEL Long-Term Stewardship Program is currently developing the management structures and plans to complete INEEL-specific, long-term stewardship obligations. This guidance document (1) assists in ensuring that the program leads transition planning for the INEEL with respect to facility and site areas and (2) describes the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete. Additionally, this document summarizes current information on INEEL facilities, structures, and release sites likely to enter long-term stewardship at the completion of DOEs cleanup mission. This document is not intended to function as a discrete checklist or local procedure to determine readiness to transition. It is an overarching document meant as guidance in implementing specific transition procedures. Several documents formed the foundation upon which this guidance was developed. Principal among these documents was the Long-Term Stewardship Draft Technical Baseline; A Report to Congress on Long-Term Stewardship, Volumes I and II; Infrastructure Long-Range Plan; Comprehensive Facility Land Use Plan; INEEL End-State Plan; and INEEL Institutional Plan.

  12. Long-Term Engineered Cap Performance

    Broader source: Energy.gov [DOE]

    Summary Notes from 22 July 2008 Generic Technical Issue Discussion on Long-Term Engineered Cap Performance

  13. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...

    Office of Environmental Management (EM)

    Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did This Review The On-Site Waste Disposal Facility (OSWDF) is ...

  14. Pyramiding tumuli waste disposal site and method of construction thereof

    DOE Patents [OSTI]

    Golden, Martin P.

    1989-01-01

    An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

  15. August 2015 Groundwater and Surface Water Sampling at the Tuba City, Arizona, Disposal Site

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2015 LMS/TUB/S00815 This page intentionally left blank U.S. Department of Energy DVP-August 2015, Tuba City, Arizona, Disposal Site November 2015 RIN 15087262 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal Site, Sample Location Map

  16. Analyses of soils at commercial radioactive waste disposal sites

    SciTech Connect (OSTI)

    Piciulo, P.L.; Shea, C.E.; Barletta, R.E.

    1983-01-01

    Brookhaven National Laboratory, in order to provide technical assistance to the NRC, has measured a number of physical and chemical characteristics of soils from three commercial low-level radioactive waste disposal sites. Samples were collected from an area adjacent to the disposal site at Sheffield, IL, and from two operating sites: one at Barnwell, SC, and the other near Richland, WA. The soil samples, which were analyzed from each site, were believed to include soil which was representative of that in contact with buried waste forms. Results of field measurements of earth resistivity and of soil pH will be presented. Additionally, the results of laboratory measurements of resistivity, moisture content, pH, exchange acidity and the soluble ion content of the soils will be discussed. The soluble ion content of the soils was determined by analysis of aqueous extracts of saturated soil pastes. The concentrations of the following ions were determined: Ca/sup 2 +/, Mg/sup 2 +/, K/sup +/, Na/sup +/, HCO/sub 3//sup -/, CO/sub 3//sup 2 -/, SO/sub 4//sup 2 -/, Cl/sup -/, S/sup 2 -/.

  17. Application for Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-08-05

    The NTS is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. NNSA/NSO is the federal lands management authority for the NTS and NSTec is the Management & Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The U10C Disposal Site is located in the northwest corner of Area 9 at the NTS (Figure 1) and is located in a subsidence crater created by two underground nuclear events, one in October 1962 and another in April 1964. The disposal site opened in 1971 for the disposal of rubbish, refuse, pathological waste, asbestos-containing material, and industrial solid waste. A Notice of Intent form to operate the disposal site as a Class II site was submitted to the state of Nevada on January 26, 1994, and was acknowledged in a letter to the DOE on February 8, 1994. It operated as a state of Nevada Class II Solid Waste Disposal Site (SWDS) until it closed on October 5, 1995, for retrofit as a Class III SWDS. The retrofit consisted of the installation of a minimum four-foot compacted soil layer to segregate the different waste types and function as a liner to inhibit leachate and water flow into the lower waste zone. Five neutron monitoring tubes were installed in this layer to monitor possible leachate production and water activity. Upon acceptance of the installed barrier and approval of an Operating Plan by NDEP/BFF, the site reopened in January 1996 as a Class III SWDS for the disposal of industrial solid waste and other inert waste.

  18. Long-Term Surveillance Plan for the Ambrosia Lake, New Mexico, Disposal Site, DOE/AL/62350-211, Revision 1, July 1996

    Office of Legacy Management (LM)

  19. Long-Term Surveillance Plan for South Clive Disposal Site, Clive, Utah, DOE/AL/62350-228, Revision 2, September 1997

    Office of Legacy Management (LM)

  20. Long-Term Surveillance Plan for the Gunnison, Colorado, Disposal Site, DOE/AL/62350-222, Revision 2, April 1997

    Office of Legacy Management (LM)

  1. News Release: 2010 UMTRCA Title I and Title II Disposal Sites...

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

    Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites and the 2010 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation ...

  2. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Volume 2

    SciTech Connect (OSTI)

    Not Available

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723). DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations: Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho; Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  3. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Volume1

    SciTech Connect (OSTI)

    Not Available

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723).DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations:Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho;Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  4. Disposal of Draeger Tubes at Savannah River Site

    SciTech Connect (OSTI)

    Malik, N.P.

    2000-10-13

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed.

  5. Long-Term Ecological Monitoring Field Sampling Plan for 2007

    SciTech Connect (OSTI)

    T. Haney R. VanHorn

    2007-07-31

    This field sampling plan describes the field investigations planned for the Long-Term Ecological Monitoring Project at the Idaho National Laboratory Site in 2007. This plan and the Quality Assurance Project Plan for Waste Area Groups 1, 2, 3, 4, 5, 6, 7, 10, and Removal Actions constitute the sampling and analysis plan supporting long-term ecological monitoring sampling in 2007. The data collected under this plan will become part of the long-term ecological monitoring data set that is being collected annually. The data will be used t determine the requirements for the subsequent long-term ecological monitoring. This plan guides the 2007 investigations, including sampling, quality assurance, quality control, analytical procedures, and data management. As such, this plan will help to ensure that the resulting monitoring data will be scientifically valid, defensible, and of known and acceptable quality.

  6. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Office of Legacy Management (LM)

    Bluewater, New Mexico Page 1-1 1.0 Bluewater, New Mexico, Disposal Site 1.1 Compliance Summary The Bluewater, New Mexico, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on August 19 and 20, 2015. A significant pond was present on the top slope of the main tailings disposal cell cover in an area where shallow depressions are present; disposal cell performance is being evaluated to determine if additional monitoring or cover enhancement is necessary.

  7. Recent ORNL experience in site performance prediction: the Gas Centrifuge Enrichment Plant and the Oak Ridge Central Waste Disposal Facility

    SciTech Connect (OSTI)

    Pin, F.G.

    1985-01-01

    The suitability of the Portsmouth Gas Centrifuge Enrichment Plant Landfill and the Oak Ridge, Tennessee, Central Waste Disposal Facility for disposal of low-level radioactive waste was evaluated using pathways analyses. For these evaluations, a conservative approach was selected; that is, conservatism was built into the analyses when assumptions concerning future events had to be made or when uncertainties concerning site or waste characteristics existed. Data from comprehensive laboratory and field investigations were used in developing the conceptual and numerical models that served as the basis for the numerical simulations of the long-term transport of contamination to man. However, the analyses relied on conservative scenarios to describe the generation and migration of contamination and the potential human exposure to the waste. Maximum potential doses to man were calculated and compared to the appropriate standards. Even under this conservative framework, the sites were found to provide adequate buffer to persons outside the DOE reservations and conclusions concerning site capacity and site acceptability were drawn. Our experience through these studies has shown that in reaching conclusions in such studies, some consideration must be given to the uncertainties and conservatisms involved in the analyses. Analytical methods to quantitatively assess the probability of future events to occur and to quantitatively determine the sensitivity of the results to data uncertainty may prove useful in relaxing some of the conservatism built into the analyses. The applicability of such methods to pathways analyses is briefly discussed.

  8. Overview of Low-Level Waste Disposal Operations at the Nevada Test Site

    SciTech Connect (OSTI)

    DOE /Navarro

    2007-02-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future.

  9. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-09-14

    The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325, Nevada Test Site Waste Acceptance Criteria (NTSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NTS Class III Permit and the NTSWAC.

  10. A Report to Congress on Long-Term Stewardship. Volume I - Summary Report

    SciTech Connect (OSTI)

    2001-01-01

    During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as for other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over a 100 sites in 30 States and one U.S. Territory. Hundreds of thousands of acres of residually contaminated soils, contaminated groundwater, surface water and sediment contamination, and contaminated buildings are present at many sites across the country. These sites range in size from less than one acre, containing only a single facility, to large sites spanning over 100,000 acres with huge uranium enrichment plants and plutonium processing canyons. Since 1989, the U.S. Department of Energy’s (DOE) Environmental Management (EM) program has made significant progress in addressing this environmental legacy. Millions of cubic meters of waste have been removed, stabilized, or disposed of, resulting in significant risk and cost reduction. In addition, DOE began disposing of transuranic (i.e., plutonium-contaminated) waste in the nation’s first deep geologic repository – the Waste Isolation Pilot Plant in New Mexico. DOE is now carrying out its long-term stewardship obligations at dozens of sites, including smaller sites where DOE has completed cleanup work for the entire site and many larger sites where DOE has remediated portions of the site.

  11. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Report March 2016 Canonsburg, Pennsylvania Page 3-1 3.0 Canonsburg, Pennsylvania, Disposal Site 3.1 Compliance Summary The Canonsburg, Pennsylvania, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on October 27, 2015. The site was in excellent condition. No evidence of erosion or slope instability was observed on the disposal cell. A trespass campsite was discovered hidden among the trees in the southwest corner of the property, outside the perimeter

  12. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Lakeview, Oregon Page 9-1 9.0 Lakeview, Oregon, Disposal Site 9.1 Compliance Summary The Lakeview, Oregon, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected September 16 and 17, 2015. Other than some ongoing concern with erosion-control rock riprap degradation, the disposal cell was in good condition. Some minor fence repairs and vegetation removal, and minor erosion repair work along the west site fence is planned. Inspectors identified no other

  13. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Rifle, Colorado Page 14-1 14.0 Rifle, Colorado, Disposal Site 14.1 Compliance Summary The Rifle, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 30, 2015. The disposal cell and all associated surface-water diversion and drainage structures were in good condition and functioning as designed. Vegetation on the site was in excellent condition. Minor fence repairs and perimeter sign maintenance will be conducted prior to the next inspection.

  14. Risk assessment of landfill disposal sites - State of the art

    SciTech Connect (OSTI)

    Butt, Talib E. Lockley, Elaine; Oduyemi, Kehinde O.K.

    2008-07-01

    A risk assessment process can assist in drawing a cost-effective compromise between economic and environmental costs, thereby assuring that the philosophy of 'sustainable development' is adhered to. Nowadays risk analysis is in wide use to effectively manage environmental issues. Risk assessment is also applied to other subjects including health and safety, food, finance, ecology and epidemiology. The literature review of environmental risk assessments in general and risk assessment approaches particularly regarding landfill disposal sites undertaken by the authors, reveals that an integrated risk assessment methodology for landfill gas, leachate or degraded waste does not exist. A range of knowledge gaps is discovered in the literature reviewed to date. From the perspective of landfill leachate, this paper identifies the extent to which various risk analysis aspects are absent in the existing approaches.

  15. Application for Permit to Operate a Class II Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-03-31

    The Nevada Test Site (NTS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NTS and National Security Technologies LLC (NSTec) is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The site will be used for the disposal of refuse, rubbish, garbage, sewage sludge, pathological waste, Asbestos-Containing Material (ACM), industrial solid waste, hydrocarbon-burdened soil, hydrocarbon-burdened demolition and construction waste, and other inert waste (hereafter called permissible waste). Waste containing free liquids or regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA) will not be accepted for disposal at the site. Waste regulated under the Toxic Substance Control Act (TSCA), excluding Polychlorinated Biphenyl [PCB], Bulk Product Waste (see Section 6.2.5) and ACM (see Section 6.2.2.2) will not be accepted for disposal at the site. The disposal site will be used as the sole depository of permissible waste which is: (1) Generated by entities covered under the U.S. Environmental Protection Agency (EPA) Hazardous Waste Generator Identification Number for the NTS; (2) Generated at sites identified in the Federal Facilities Agreement and Consent Order (FFACO); (3) Sensitive records and media, including documents, vugraphs, computer disks, typewriter ribbons, magnetic tapes, etc., generated by NNSA/NSO or its contractors; (4) ACM generated by NNSA/NSO or its contractors according to Section 6.2.2.2, as necessary; (5) Hydrocarbon-burdened soil and solid waste from areas covered under the EPA Hazardous Waste Generator Identification Number for the NTS; (6) Other waste on a case-by-case concurrence by NDEP/BFF. The generator of permissible waste is responsible for preparing documentation related to waste acceptance criteria, waste characterization, and load verification. Waste and Water (WW) personnel are responsible for operating the disposal site and reviewing documentation to determine if the waste is acceptable.

  16. Long-Term Stewardship Program Science and Technology Requirements

    SciTech Connect (OSTI)

    Joan McDonald

    2002-09-01

    Many of the United States’ hazardous and radioactively contaminated waste sites will not be sufficiently remediated to allow unrestricted land use because funding and technology limitations preclude cleanup to pristine conditions. This means that after cleanup is completed, the Department of Energy will have long-term stewardship responsibilities to monitor and safeguard more than 100 sites that still contain residual contamination. Long-term stewardship encompasses all physical and institutional controls, institutions, information, and other mechanisms required to protect human health and the environment from the hazards remaining. The Department of Energy Long-Term Stewardship National Program is in the early stages of development, so considerable planning is still required to identify all the specific roles and responsibilities, policies, and activities needed over the next few years to support the program’s mission. The Idaho National Engineering and Environmental Laboratory was tasked with leading the development of Science and Technology within the Long-Term Stewardship National Program. As part of that role, a task was undertaken to identify the existing science and technology related requirements, identify gaps and conflicts that exist, and make recommendations to the Department of Energy for future requirements related to science and technology requirements for long-term stewardship. This work is summarized in this document.

  17. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Durango, Colorado Page 4-1 4.0 Durango, Colorado, Disposal Site 4.1 Compliance Summary The Durango, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 2, 2015. The disposal cell was in good condition. Vegetation on top of the disposal cell was healthy, and several small shrubs growing on the side slopes will be controlled. A small depression observed in 2014 on the disposal cell side slope was no longer apparent. Inspectors identified no

  18. Long-Term Surveillance and Maintenance Program 2003 Report |...

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

    Program 2003 Report Long-Term Surveillance and Maintenance Program 2003 Report Long-Term Surveillance and Maintenance Program 2003 Report PDF icon Long-Term Surveillance and ...

  19. Recommendation 188: Long-Term Stewardship Implementation | Department...

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

    88: Long-Term Stewardship Implementation Recommendation 188: Long-Term Stewardship Implementation ORSSAB offers Recommendations and Comments on the Long-Term Stewardship ...

  20. Sustainable Disposal Cell Covers: Legacy Management Practices,

    Energy Savers [EERE]

    Improvements, and Long-Term Performance | Department of Energy Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance PDF icon Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance More

  1. 2015 Annual Inspection Report for the Parkersburg, West Virginia Disposal Site

    Office of Legacy Management (LM)

    Annual Inspection Report December 2015 Parkersburg, West Virginia Page 1 2015 Annual Inspection Report for the Parkersburg, West Virginia Disposal Site 1.0 Inspection Summary The Parkersburg, West Virginia, Nuclear Waste Policy Act Section 151(c) Disposal Site was inspected on October 29, 2015. The site was in excellent condition. No evidence of erosion or slope instability on the disposal cell was noted during the inspection. A follow-up or contingency inspection is not required. No evidence of

  2. Performance Assessment of the Portsmouth On-Site Waste Disposal Facility |

    Office of Environmental Management (EM)

    Department of Energy of the Portsmouth On-Site Waste Disposal Facility Performance Assessment of the Portsmouth On-Site Waste Disposal Facility Presentation from the 2015 Annual Performance and Risk Assessment (P&RA) Community of Practice (CoP) Technical Exchange Meeting held in Richland, Washington on December 15-16, 2015. PDF icon Performance Assessment of the Portsmouth On-Site Waste Disposal Facility More Documents & Publications EA-1815: Finding of No Significant Impact

  3. Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site

    SciTech Connect (OSTI)

    BROWN,THERESA J.; WIRTH,SHARON

    1999-09-01

    This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here. Parameters necessary for estimating surface contaminant flux due to native plants expected to inhabit the NTS RWMSS are developed in this report. The model is specific to the plant communities found at the NTS and is designed for both short-term (<1,000 years) and long-term (>1,000 years) modeling efforts. While the model has been crafted for general applicability to any NTS PA, the key radionuclides considered are limited to the transuranic (TRU) wastes disposed of at the NTS.

  4. Cogeneration of electricity: Cost-effective over long term

    SciTech Connect (OSTI)

    Barger, R.L.; Barham, J. )

    1991-08-01

    This article describes the determination of the cost-effectiveness of a cogeneration project five years after it became operational in 1984. The cogeneration project uses digester sludge gas from a wastewater treatment plant. The topics covered include the history of electrical cogeneration at the site, cogeneration economics in the short term and the long term, and the factors in cost-effectiveness.

  5. Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Arnold, P.

    2012-10-31

    This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

  6. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    UMTRCA Title I Annual Report March 2016 Grand Junction, Colorado Page 6-1 6.0 Grand Junction, Colorado, Disposal Site 6.1 Compliance Summary The Grand Junction, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on December 8, 2015. A portion of the disposal cell remains open to receive low-level radioactive materials from various sources; the open cell and its supporting structures and facilities are not included in the annual inspection. Ongoing

  7. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Gunnison, Colorado Page 8-1 8.0 Gunnison, Colorado, Disposal Site 8.1 Compliance Summary The Gunnison, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on July 1, 2015. The disposal cell and all associated surface water diversion and drainage structures were in excellent condition and functioning as designed. Six riprap test areas on the cell apron and diversion ditches were visually inspected; no rock degradation was noted when compared to 2012

  8. Tuba City, Arizona, Disposal Site Groundwater Compliance Path Forward Fact Sheet

    Office of Legacy Management (LM)

    Tuba City, Arizona, Disposal Site Groundwater Compliance Path Forward Fact Sheet Fact Sheet The U.S. Department of Energy Office of Legacy Management is responsible for site management and for ensuring that the selected groundwater compliance strategy at the Tuba City, Arizona, Disposal Site continues to be protective of human health and the environment. Southwesterly view of Tuba City mill in operation, circa 1966. Tuba City site, 2010. Tuba City Site background The Tuba City uranium mill

  9. Siting process for disposal site of low level radiactive waste in Thailand

    SciTech Connect (OSTI)

    Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K. )

    1992-01-01

    The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand.

  10. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    SciTech Connect (OSTI)

    Wickline, Alfred

    2005-12-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action alternatives.

  11. Site Transition Framework | Department of Energy

    Energy Savers [EERE]

    Framework Site Transition Framework Site Transition Framework (April 2004) PDF icon Site Transition Framework More Documents & Publications Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance Long-Term Stewardship Study Recommendation 218: Develop a Fact Sheet on Site Transition at On-going Mission Sites

  12. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous

    Energy Savers [EERE]

    Diffusion Plant | Department of Energy Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Full Document and Summary Versions are available for download PDF icon Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant PDF icon Summary - Environmental Management Waste Management Facility (EMWMF) at Oak Ridge, TN More Documents & Publications

  13. September 2015 Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal Site

    Office of Legacy Management (LM)

    Groundwater and Surface Water Sampling at the Shiprock, New Mexico, Disposal Site February 2016 LMS/SHP/S00915 This page intentionally left blank U.S. Department of Energy DVP-September 2015, Shiprock, New Mexico February 2016 RINs 15097348 and 15097349 Page i Contents Sampling Event Summary ...............................................................................................................1 Planned Sampling Map Shiprock, New Mexico, Disposal Site

  14. August 2015 Groundwater Sampling at the Grand Junction, Colorado, Disposal Site

    Office of Legacy Management (LM)

    Sampling at the Grand Junction, Colorado, Disposal Site October 2015 LMS/GRJ/S00815 This page intentionally left blank U.S. Department of Energy DVP-August 2015, Grand Junction, Colorado October 2015 RIN 15077245 Page i Contents Sampling Event Summary ...............................................................................................................1 Grand Junction, Colorado, Disposal Site, Sample Location Map ...................................................3 Data Assessment

  15. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    SciTech Connect (OSTI)

    Mohamed, Yasser T.

    2013-07-01

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

  16. EA-1097: Solid waste Disposal- Nevada Test Site, Nye County, Nevada

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to continue the on-site disposal of solid waste at the Area 9 and Area 23 landfills at the U.S. Department of Energy Nevada Test Site...

  17. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    SciTech Connect (OSTI)

    Rodney C. Ewing

    2004-10-07

    Spent nuclear fuel, essentially U{sub 2}, accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO{sub 2} in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term.

  18. disposal_cell.cdr

    Office of Legacy Management (LM)

    The disposal cell was constructed in the area formerly occupied by the Weldon Spring Uranium Feed Materials Plant production buildings. The cell provides long-term isolation and ...

  19. Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-09-01

    According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

  20. Lakeview, Oregon, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    ... a soilrock matrix layer on the top and rock (riprap) on the side slopes to protect against wind and water erosion. The top of the disposal cell supports native brush and grasses. ...

  1. Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

    SciTech Connect (OSTI)

    Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory

    2011-11-01

    Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.

  2. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Summary and Guide for Stakeholders

    SciTech Connect (OSTI)

    Not Available

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723). DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations: Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho; Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  3. Framework for DOE mixed low-level waste disposal: Site fact sheets

    SciTech Connect (OSTI)

    Gruebel, M.M.; Waters, R.D.; Hospelhorn, M.B.; Chu, M.S.Y.

    1994-11-01

    The Department of Energy (DOE) is required to prepare and submit Site Treatment Plans (STPS) pursuant to the Federal Facility Compliance Act (FFCAct). Although the FFCAct does not require that disposal be addressed in the STPS, the DOE and the States recognize that treatment of mixed low-level waste will result in residues that will require disposal in either low-level waste or mixed low-level waste disposal facilities. As a result, the DOE is working with the States to define and develop a process for evaluating disposal-site suitability in concert with the FFCAct and development of the STPS. Forty-nine potential disposal sites were screened; preliminary screening criteria reduced the number of sites for consideration to twenty-six. The DOE then prepared fact sheets for the remaining sites. These fact sheets provided additional site-specific information for understanding the strengths and weaknesses of the twenty-six sites as potential disposal sites. The information also provided the basis for discussion among affected States and the DOE in recommending sites for more detailed evaluation.

  4. Long Term Corrosion/Degradation Test Six Year Results

    SciTech Connect (OSTI)

    M. K. Adler Flitton; C. W. Bishop; M. E. Delwiche; T. S. Yoder

    2004-09-01

    The Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) located at the Idaho National Engineering and Environmental Laboratory (INEEL) contains neutron-activated metals from non-fuel, nuclear reactor core components. The Long-Term Corrosion/Degradation (LTCD) Test is designed to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements to the environment. The test is using two proven, industry-standard methodsdirect corrosion testing using metal coupons, and monitored corrosion testing using electrical/resistance probesto determine corrosion rates for various metal alloys generally representing the metals of interest buried at the SDA, including Type 304L stainless steel, Type 316L stainless steel, Inconel 718, Beryllium S200F, Aluminum 6061, Zircaloy-4, low-carbon steel, and Ferralium 255. In the direct testing, metal coupons are retrieved for corrosion evaluation after having been buried in SDA backfill soil and exposed to natural SDA environmental conditions for times ranging from one year to as many as 32 years, depending on research needs and funding availability. In the monitored testing, electrical/resistance probes buried in SDA backfill soil will provide corrosion data for the duration of the test or until the probes fail. This report provides an update describing the current status of the test and documents results to date. Data from the one-year and three-year results are also included, for comparison and evaluation of trends. In the six-year results, most metals being tested showed extremely low measurable rates of general corrosion. For Type 304L stainless steel, Type 316L stainless steel, Inconel 718, and Ferralium 255, corrosion rates fell in the range of no reportable to 0.0002 mils per year (MPY). Corrosion rates for Zircaloy-4 ranged from no measurable corrosion to 0.0001 MPY. These rates are two orders of magnitude lower than those specified in the performance assessment for the SDA. The corrosion on the carbon steel, beryllium, and aluminum were more evident with a clear difference in corrosion performance between the 4-ft and 10-ft levels. Notable surface corrosion products were evident as well as numerous pit initiation sites. Since the corrosion of the beryllium and aluminum is characterized by pitting, the geometrical character of the corrosion becomes more significant than the general corrosion rate. Both pitting factor and weight loss data should be used together. For six-year exposure, the maximum carbon steel corrosion rate was 0.3643 MPY while the maximum beryllium corrosion rate was 0.3282 MPY and the maximum aluminum corrosion rate was 0.0030 MPY.

  5. Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site

    Broader source: Energy.gov [DOE]

    Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site

  6. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Office of Legacy Management (LM)

    Sherwood, Washington Page 5-1 5.0 Sherwood, Washington, Disposal Site 5.1 Compliance Summary The Sherwood, Washington, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on May 20, 2015. The tailings impoundment, dam, and diversion channel were in good condition. The dam inspection and associated piezometer water level measurements verified that the tailings dam is functioning as designed. A damaged perimeter sign was replaced in July 2015. Inspectors

  7. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Salt Lake City, Utah Page 15-1 15.0 Salt Lake City, Utah, Disposal Site 15.1 Compliance Summary The Salt Lake City, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 22, 2015. The disposal cell was in good condition. Observations of rock quality monitoring plots indicated no obvious change from the previous year. Inspectors did note vegetation buildup along the access road that surrounds the cell. No waste debris or indication of windblown or

  8. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2009-01-31

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

  9. Response G-1: The decision to construct an on-site disposal...

    Office of Legacy Management (LM)

    Response G-1: The decision to construct an on-site disposal facility was reached through a public process and the affected communities in St. Charles County reached a consensus...

  10. Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) published in the Federal Register (January 24, 2006), a Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site.

  11. Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations

    SciTech Connect (OSTI)

    J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

    2009-03-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

  12. Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas

    Broader source: Energy.gov [DOE]

    PIKETON, Ohio — EM’s Portsmouth site this summer sent its first shipment of mixed low-level radioactive waste from its uranium enrichment operations to Waste Control Specialists (WCS) in Andrews, Texas for treatment and disposal.

  13. Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) announces the availability of a section 3116 determination for the disposal of separated, solidified, low-activity salt waste at the Savannah River Site (SRS) near...

  14. Titanium for long-term tritium storage

    SciTech Connect (OSTI)

    Heung, L.K.

    1994-12-01

    Due to the reduction of nuclear weapon stockpile, there will be an excess of tritium returned from the field. The excess tritium needs to be stored for future use, which might be several years away. A safe and cost effective means for long term storage of tritium is needed. Storing tritium in a solid metal tritide is preferred to storing tritium as a gas, because a metal tritide can store tritium in a compact form and the stored tritium will not be released until heat is applied to increase its temperature to several hundred degrees centigrade. Storing tritium as a tritide is safer and more cost effective than as a gas. Several candidate metal hydride materials have been evaluated for long term tritium storage. They include uranium, La-Ni-Al alloys, zirconium and titanium. The criteria used include material cost, radioactivity, stability to air, storage capacity, storage pressure, loading and unloading conditions, and helium retention. Titanium has the best combination of properties and is recommended for long term tritium storage.

  15. Los Alamos National Laboratory: Long-Term Environmental Stewardship...

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

    green? Click image to learn more Next Enduring Environmental Stewardship Long-Term Strategy for Environmental Stewardship and Sustainability Long-Term Strategy for Environmental...

  16. Los Alamos National Laboratory announces strategy for long-term...

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

    Strategy for long-term environmental sustainability Los Alamos National Laboratory announces strategy for long-term environmental sustainability Provides a blueprint for protecting ...

  17. Los Alamos National Laboratory: Long-Term Environmental Stewardship...

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

    Long-Term Strategy for Environmental Stewardship and Sustainability Long-Term Strategy for Environmental Stewardship and Sustainability (pdf) From today for years to come Over the ...

  18. Hydrogen Storage Technologies: Long-Term Commercialization Approach...

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

    Technologies: Long-Term Commercialization Approach with First Products First Hydrogen Storage Technologies: Long-Term Commercialization Approach with First Products First Presented ...

  19. Building America Case Study: Initial and Long Term Movement of...

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

    Initial and Long-Term Movement of Cladding Installed Over Exterior Rigid Insulation PROJECT INFORMATION Project Name: Initial and Long-Term Movement of Cladding Installed Over ...

  20. Transition of Long-Term Response Action Management Requirements...

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

    Transition of Long-Term Response Action Management Requirements Transition of Long-Term Response Action Management Requirements The purpose of this memorandum is to provide you ...

  1. Salt Waste Disposal at the Savannah River Site | Department of Energy

    Energy Savers [EERE]

    Salt Waste Disposal at the Savannah River Site Salt Waste Disposal at the Savannah River Site Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Currently, DOE SRS has prepared one final (salt waste) and is

  2. 2003 Long-Term Surveillance and Maintenance Program Report

    SciTech Connect (OSTI)

    2004-07-01

    Radioactive waste was created by the Federal Government and private industry at locations around the country in support of national defense, research, and civilian power-generation programs. If not controlled, much of this legacy waste would remain hazardous to human health and the environment indefinitely. Current technology does not allow us to render this waste harmless, so the available methods to control risk rely on consolidation, isolation, and long-term management of the waste. The U.S. Department of Energy (DOE) has an obligation to safely control the radioactive waste and to inform and train future generations to maintain and, perhaps, improve established protections. DOE is custodian for much of the radioactive and other hazardous waste under control of the Federal Government. DOE established the Formerly Utilized Sites Remedial Action Program (FUSRAP) in 1974 and the Defense Decontamination and Decommissioning (D&D) Program and the Surplus Facilities Management Program in the 1980s. Congress passed the Uranium Mill Tailings Radiation Control Act (UMTRCA) in 1978. These federal programs and legislation were established to identify, remediate, and manage legacy waste. Remedial action is considered complete at a radioactive waste site when the identified hazardous material is isolated and the selected remedial action remedy is in place and functioning. Radioactive or other hazardous materials remain in place as part of the remedy at many DOE sites. Long-term management of radioactive waste sites incorporates a set of actions necessary to maintain protection of human health and the environment. These actions include maintaining physical impoundment structures in good repair to ensure that they perform as designed, preventing exposure to the wastes by maintaining access restrictions and warnings, and recording site conditions and activities for future custodians. Any actions, therefore, that will prevent exposure to the radioactive waste now or in the future are part of long-term site management. In response to post-closure care requirements set forth in UMTRCA, DOE Headquarters established the Long-Term Surveillance and Maintenance (LTS&M) Program in 1988 at the DOE office in Grand Junction, Colorado. The program assumed long-term management responsibility for sites remediated under UMTRCA and other programs. Since its inception, the LTS&M Program has evolved in response to changing stakeholder needs, improvements in technology, and the addition of more DOE sites as remediation is completed. The mission of the LTS&M Program was to fulfill DOE’s responsibility to implement all activities necessary to ensure regulatory compliance and to protect the public and the environment from long-lived wastes associated with the nation’s nuclear energy, weapons, and research activities. Key components of the LTS&M Program included stakeholder participation, site monitoring and maintenance, records and information management, and research and technology transfer. This report presents summaries of activities conducted in 2003 in fulfillment of the LTS&M Program mission. On December 15, 2003, DOE established the Office of Legacy Management (LM) to allow for optimum management of DOE’s legacy responsibilities. Offices are located in Washington, DC, Grand Junction, Colorado, Morgantown, West Virginia, and Pittsburgh, Pennsylvania, to perform long-term site management, land management, site transition support, records management, and other related tasks. All activities formerly conducted under the LTS&M Program have been incorporated into the Office of Land and Site Management (LM–50), as well as management of remedies involving ground water and surface water contaminated by former processing activities.

  3. Siting Study for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

    2010-10-01

    The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

  4. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Naturita, Colorado Page 13-1 13.0 Naturita, Colorado, Disposal Site 13.1 Compliance Summary The Naturita, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on May 12, 2015. The site was in excellent condition. A section of the perimeter fence had been trampled down and several loose fence strands were identified. The fence sections were repaired 2 weeks after the inspection. Inspectors identified no other needs or cause for a follow-up or

  5. Long-Term Wind Power Variability

    SciTech Connect (OSTI)

    Wan, Y. H.

    2012-01-01

    The National Renewable Energy Laboratory started collecting wind power data from large commercial wind power plants (WPPs) in southwest Minnesota with dedicated dataloggers and communication links in the spring of 2000. Over the years, additional WPPs in other areas were added to and removed from the data collection effort. The longest data stream of actual wind plant output is more than 10 years. The resulting data have been used to analyze wind power fluctuations, frequency distribution of changes, the effects of spatial diversity, and wind power ancillary services. This report uses the multi-year wind power data to examine long-term wind power variability.

  6. DOE - Office of Legacy Management -- Maryland Disposal Site ...

    Office of Legacy Management (LM)

    under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Baltimore - Vicinity , Maryland MD.05-1 Evaluation Year: 1989 MD.05-1 Site Operations:...

  7. Salt Lake City, Utah, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    soils in place because they pose no unacceptable risk to human health or the environment. Past processing operations at the site have resulted in contamination in a shallow...

  8. A data base for low-level radioactive waste disposal sites

    SciTech Connect (OSTI)

    Daum, M.L.; Moskowitz, P.D.

    1989-07-01

    A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs.

  9. Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant

    Office of Environmental Management (EM)

    Paducah, KY EM Project: On-Site Disposal Facility ETR Report Date: August 2008 ETR-16 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Disposal Facility(OSDF) at the Paducah Gaseous Diffusion Plant Why DOE-EM Did This Review The Paducah Gaseous Diffusion Plant (PGDP) is an active uranium enrichment facility that was placed on the National Priorities List. DOE is required to remediate the PGDP in accordance with the

  10. Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2013-01-31

    The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health and the environment. The waste stream is recommended for disposal without conditions.

  11. Numerical simulation experiments on the long-term evolution of...

    Office of Scientific and Technical Information (OSTI)

    the long-term evolution of a CO2 plume under a sloping caprock Citation Details In-Document Search Title: Numerical simulation experiments on the long-term evolution of a CO2 plume ...

  12. Long-term Contract Information and Registrations | Department...

    Energy Savers [EERE]

    Long-Term Contract Information and Registrations at U.S. LNG Export Facilities DOEFE ... contract information with DOEFE for LNG exports and long-term natural gas supply. ...

  13. Why is a long-term strategy important?

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

    Why is a long-term strategy important? Why is a long-term strategy important? Because we protect the environment. That is our practice today, and it is our commitment to a...

  14. LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT...

    Office of Scientific and Technical Information (OSTI)

    LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT OF RADIONUCLIDES IN A SEMI-ARID VADOSE ZONE Citation Details In-Document Search Title: LONG-TERM COLLOID ...

  15. Long-Term Surveillance Operations and Maintenance Fiscal Year...

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

    3 Year-End Summary Report Long-Term Surveillance Operations and Maintenance Fiscal Year ... PDF icon Long-Term Surveillance Operations and Maintenance Fiscal Year 2013 Year-End ...

  16. Long-term risk stabilization of the Rocky Flats Plant residues

    SciTech Connect (OSTI)

    Melberg, T.A.

    1994-12-31

    The liquid and solid residues continue to be a concern at Rocky Flats, primarily due to safety aspects of long-term storage and of the need for processing them into a form for ultimate disposal. Currently, Rocky Flats is processing the low-level solutions from bottles and tanks by direct cementation for storage and disposal. Plans for actinide precipitation of the high-level solutions are being finalized with an anticipated completion date of 2 to 3 yr. The solid residues present a more difficult challenge because of the numerous forms that these exist. Rocky Flats is developing several strategies to handle these materials for safe long-term storage and eventual disposal.

  17. Long-term corrosion testing pan.

    SciTech Connect (OSTI)

    Wall, Frederick Douglas; Brown, Neil R. (Los Alamos National Laboratory, Los Alamos, NM)

    2008-08-01

    This document describes the testing and facility requirements to support the Yucca Mountain Project long-term corrosion testing needs. The purpose of this document is to describe a corrosion testing program that will (a) reduce model uncertainty and variability, (b) reduce the reliance upon overly conservative assumptions, and (c) improve model defensibility. Test matrices were developed for 17 topical areas (tasks): each matrix corresponds to a specific test activity that is a subset of the total work performed in a task. A future document will identify which of these activities are considered to be performance confirmation activities. Detailed matrices are provided for FY08, FY09 and FY10 and rough order estimates are provided for FY11-17. Criteria for the selection of appropriate test facilities were developed through a meeting of Lead Lab and DOE personnel on October 16-17, 2007. These criteria were applied to the testing activities and recommendations were made for the facility types appropriate to carry out each activity. The facility requirements for each activity were assessed and activities were identified that can not be performed with currently available facilities. Based on this assessment, a total of approximately 10,000 square feet of facility space is recommended to meet all future testing needs, given that all testing is consolidated to a single location. This report is a revision to SAND2007-7027 to address DOE comments and add a series of tests to address NWTRB recommendations.

  18. Long-term corrosion testing plan.

    SciTech Connect (OSTI)

    Wall, Frederick Douglas; Brown, Neil R. (Los Alamos National Laboratory, Los Alamos, NM)

    2009-02-01

    This document describes the testing and facility requirements to support the Yucca Mountain Project long-term corrosion testing program. The purpose of this document is to describe a corrosion testing program that will (a) reduce model uncertainty and variability, (b) reduce the reliance upon overly conservative assumptions, and (c) improve model defensibility. Test matrices were developed for 17 topical areas (tasks): each matrix corresponds to a specific test activity that is a subset of the total work performed in a task. A future document will identify which of these activities are considered to be performance confirmation activities. Detailed matrices are provided for FY08, FY09 and FY10 and rough order estimates are provided for FY11-17. Criteria for the selection of appropriate test facilities were developed through a meeting of Lead Lab and DOE personnel on October 16-17, 2007. These criteria were applied to the testing activities and recommendations were made for the facility types appropriate to carry out each activity. The facility requirements for each activity were assessed and activities were identified that can not be performed with currently available facilities. Based on this assessment, a total of approximately 10,000 square feet of facility space is recommended to accommodate all future testing, given that all testing is consolidated to a single location. This report is a revision to SAND2008-4922 to address DOE comments.

  19. Adapting Advances in Remediation Science to Long-Term Surveillance |

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

    Department of Energy Adapting Advances in Remediation Science to Long-Term Surveillance Adapting Advances in Remediation Science to Long-Term Surveillance Paper and presentation presented at the Waste Managent 2006 Conference. February 26 through March 2, 2006, Tucson, Arizona. David Peterson PDF icon Adapting Advances in Remediation Science to Long-Term Surveillance More Documents & Publications Applied Science and Technology Task Order Fiscal Year 2009 Year-End Summary Report Long-Term

  20. Long-Term Grout Performance | Department of Energy

    Office of Environmental Management (EM)

    Grout Performance Long-Term Grout Performance Summary Notes from 5 March 2008 Generic Technical Issue Discussion on Long-Term Grout Performance PDF icon Summary Notes from 5 March 2008 Generic Technical Issue Discussion on Long-Term Grout Performance More Documents & Publications Long-Term Engineered Cap Performance Estimating Waste Inventory and Waste Tank Characterization DOE EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013)

  1. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings

    Office of Scientific and Technical Information (OSTI)

    Radiation Control Act Title I Disposal Sites (Technical Report) | SciTech Connect Technical Report: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites This report, in fulfillment of a license requirement, presents the results of long-term surveillance and

  2. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings

    Office of Scientific and Technical Information (OSTI)

    Radiation Control Act Title II Disposal Sites (Technical Report) | SciTech Connect Technical Report: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites This report, in fulfillment of a license requirement, presents the results of long-term surveillance and

  3. Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

    SciTech Connect (OSTI)

    Croff, A.G.

    2001-01-11

    The purpose of this report is to review and document the capability of potential products of depleted UF{sub 6} conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report.

  4. The application of compressed sensing to long-term acoustic emission-based

    Office of Scientific and Technical Information (OSTI)

    structural health monitoring (Conference) | SciTech Connect Conference: The application of compressed sensing to long-term acoustic emission-based structural health monitoring Citation Details In-Document Search Title: The application of compressed sensing to long-term acoustic emission-based structural health monitoring × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI)

  5. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    SciTech Connect (OSTI)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D.

    2013-07-01

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

  6. Closure Report for Corrective Action Unit 399: Area 18 Disposal Site

    SciTech Connect (OSTI)

    Navarro Nevada Environmental Services

    2010-08-10

    The closure report for CAU 399 is just a one page summary listing the coordinates of the disposal site which were given at the time (1995) in Nevada State Plan Coordinates - North American Datum of 1983. The drawing of the use restricted site also listed the coordinates in Nevada State Plan Coordinates - North American Datum of 1983. In the ensuing years the reporting of coordinates has been standardized so that all coordinates are reported in the same manner, which is: NAD 27 UTM Zone 11 N, meters. This Errata Sheet updates the coordinate reporting to the currently accepted method and includes an aerial photo showing the disposal site with the coordinates listed showing the use restricted area.

  7. Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...

    Office of Environmental Management (EM)

    Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of Long-Term Performance Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of...

  8. Classified Component Disposal at the Nevada National Security Site (NNSS) - 13454

    SciTech Connect (OSTI)

    Poling, Jeanne; Arnold, Pat; Saad, Max; DiSanza, Frank; Cabble, Kevin

    2013-07-01

    The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012. (authors)

  9. Application of pathways analyses for site performance prediction for the Gas Centrifuge Enrichment Plant and Oak Ridge Central Waste Disposal Facility

    SciTech Connect (OSTI)

    Pin, F.G.; Oblow, E.M.

    1984-01-01

    The suitability of the Gas Centrifuge Enrichment Plant and the Oak Ridge Central Waste Disposal Facility for shallow-land burial of low-level radioactive waste is evaluated using pathways analyses. The analyses rely on conservative scenarios to describe the generation and migration of contamination and the potential human exposure to the waste. Conceptual and numerical models are developed using data from comprehensive laboratory and field investigations and are used to simulate the long-term transport of contamination to man. Conservatism is built into the analyses when assumptions concerning future events have to be made or when uncertainties concerning site or waste characteristics exist. Maximum potential doses to man are calculated and compared to the appropriate standards. The sites are found to provide adequate buffer to persons outside the DOE reservations. Conclusions concerning site capacity and site acceptability are drawn. In reaching these conclusions, some consideration is given to the uncertainties and conservatisms involved in the analyses. Analytical methods to quantitatively assess the probability of future events to occur and the sensitivity of the results to data uncertainty may prove useful in relaxing some of the conservatism built into the analyses. The applicability of such methods to pathways analyses is briefly discussed. 18 refs., 9 figs.

  10. Long-Term Surveillance and Maintenance Program

    Office of Legacy Management (LM)

    ... mild. The wind at the Shiprock site blows most frequently from the southeast in summer and from the west in winter. On an annual basis, the most frequent wind direction is ...

  11. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    SciTech Connect (OSTI)

    Smith, Frank G.; Phifer, Mark A.

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory constraints based on the intruder analysis are well above conservative estimates of the OSWDF inventory and, based on intruder disposal limits; about 7% of the disposal capacity is reached with the estimated OSWDF inventory.

  12. The Long-Term Inflow and Structural Test Program

    SciTech Connect (OSTI)

    SUTHERLAND,HERBERT J; JONES,PERRY L.; NEAL,BYRON A.

    2000-10-17

    The Long-term Inflow and Structural Test (LIST) program is collecting long-term, continuous inflow and structural response data to characterize the extreme loads on wind turbines. A heavily instrumented Micon 65/13M turbine with SERI 8-m blades is being used as the first test turbine for this test program. This turbine and its two sister turbines are located in Bushland, TX a test site that exposes the turbines to a wind regime that is representative of a Great Plains commercial site. The turbines and their inflow are being characterized with 60 measurements: 34 to characterize the inflow, 19 to characterize structural response, and 7 to characterize the time-varying state of the turbine. The primary characterization of the inflow into the LIST turbine relies upon an array of five sonic anemometers. These three-axis anemometers are placed approximately 2-diameters upstream of the turbine in a pattern designed to describe the inflow. Primary characterization of the structural response of the turbine uses several sets of strain gauges to measure bending loads on the blades and the tower and two accelerometers to measure the motion of the nacelle. Data from the various instruments are sampled at a rate of 30 Hz using a newly developed data acquisition system that features a time-synchronized continuous data stream that is telemetered from the turbine rotor. The data, taken continuously, are automatically divided into 10-minute segments and archived for analysis. Preliminary data are presented to illustrate the operation of the turbine and the data acquisition and analysis system.

  13. Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

    SciTech Connect (OSTI)

    Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

    1983-12-01

    The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals.

  14. The Changing Adventures of Mixed Low-Level Waste Disposal at the Nevada Test Site

    SciTech Connect (OSTI)

    DOE /Navarro/NSTec

    2007-02-01

    After a 15-year hiatus, the United States Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO) began accepting DOE off-site generated mixed low-level radioactive waste (MLLW) for disposal at the Nevada Test Site (NTS) in December 2005. This action was predicated on the acceptance by the Nevada Division of Environmental Protection (NDEP) of a waste analysis plan (WAP). The NNSA/NSO agreed to limit mixed waste disposal to 20,000 cubic meters (approximately 706,000 cubic feet) and close the facility by December 2010 or sooner, if the volume limit is reached. The WAP and implementing procedures were developed based on Hanford’s system of verification to the extent possible so the two regional disposal sites could have similar processes. Since the NNSA/NSO does not have a breaching facility to allow the opening of boxes at the site, verification of the waste occurs by visual inspection at the generator/treatment facility or by Real-Time-Radiography (RTR) at the NTS. This system allows the NTS to effectively, efficiently, and compliantly accept MLLW for disposal. The WAP, NTS Waste Acceptance Criteria, and procedures have been revised based on learning experiences. These changes include: RTR expectations; visual inspection techniques; tamper-indicating device selection; void space requirements; and chemical screening concerns. The NNSA/NSO, NDEP, and the generators have been working together throughout the debugging of the verification processes. Additionally, the NNSA/NSO will continue to refine the MLLW acceptance processes and strive for continual improvement of the program.

  15. Vehicle Technologies Office: Long-Term Lightweight Materials Research

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

    (Magnesium and Carbon Fiber) | Department of Energy Long-Term Lightweight Materials Research (Magnesium and Carbon Fiber) Vehicle Technologies Office: Long-Term Lightweight Materials Research (Magnesium and Carbon Fiber) In the long term, advanced materials such as magnesium and carbon fiber reinforced composites could reduce the weight of some components by 50-75 percent. Magnesium Even though magnesium (Mg) can reduce component weight by more than 60 percent, its use is currently limited

  16. Long Term Environment and Economic Impacts of Coal Liquefaction...

    Office of Scientific and Technical Information (OSTI)

    Long Term Environment and Economic Impacts of Coal Liquefaction in China Fletcher, Jerald 01 COAL, LIGNITE, AND PEAT The project currently is composed of six specific tasks - three...

  17. Long-Term Biological Monitoring of an Impaired Stream: Implications...

    Office of Scientific and Technical Information (OSTI)

    Major components of the long-term program included testing and monitoring of invertebrate and fish toxicity, bioindicators of fish health, fish contaminant accumulation, and ...

  18. Experimental apparatus and software design for dynamic long-term...

    Office of Scientific and Technical Information (OSTI)

    reliability testing of a spring-mass MEMS device. Citation Details In-Document Search Title: Experimental apparatus and software design for dynamic long-term reliability ...

  19. Long-Term Strategy for Environmental Stewardship and Sustainability

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

    Long-Term Strategy for Environmental Stewardship & Sustainability Hawks nesting Bike rider commutes to work at LANL A bobcat walking on LANL property Weather monitoring at LANL...

  20. The relationship between interannual and long-term cloud feedbacks...

    Office of Scientific and Technical Information (OSTI)

    climate models with more positive cloud feedback in response to interannual climate fluctuations also have more positive cloud feedback in response to long-term global warming. ...

  1. Strontium Isotopes Test Long-Term Zonal Isolation of Injected...

    Office of Scientific and Technical Information (OSTI)

    Water after Hydraulic Fracturing Citation Details In-Document Search Title: Strontium Isotopes Test Long-Term Zonal Isolation of Injected and Marcellus Formation Water after ...

  2. Long-Term Strategy for Environmental Stewardship and Sustainability

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

    Long-Term Strategy for Environmental Stewardship & Sustainability Hawks nesting Bike rider commutes to work at LANL A bobcat walking on LANL property Weather monitoring at LANL ...

  3. An Analytical Framework for Long Term Policy for Commercial Deployment...

    Open Energy Info (EERE)

    Analytical Framework for Long Term Policy for Commercial Deployment and Innovation in Carbon Capture and Sequestration Technology in the United States Jump to: navigation, search...

  4. Site Transition Summary: Cleanup Completion to Long-Term Stewardship...

    Office of Environmental Management (EM)

    non-radiological dose assessment; air surveillance; groundwater, surface water, and sediment monitoring and analysis; soil monitoring; and foodstuffs and biota monitoring. The...

  5. Site Transition Framework for Long-Term Surveillance and Maintenance

    Office of Environmental Management (EM)

  6. Recommended Procedures for Measuring Radon Fluxes from Disposal Sites of Residual Radioactive Materials

    SciTech Connect (OSTI)

    Young,, J. A.; Thomas, V. W.; Jackson, P. 0.

    1983-03-01

    This report recornmenrls instrumentation and methods suitable for measuring radon fluxes emanating from covered disposal sites of residual radioactive materials such as uranium mill tailings. Problems of spatial and temporal variations in radon flux are discussed and the advantages and disadvantages of several instruments are examined. A year-long measurement program and a two rnonth measurement rnethodology are then presented based on the inherent difficulties of measuring average radon flux over a cover using the recommended instrumentation.

  7. Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll

    SciTech Connect (OSTI)

    Robison, W.L.; Noshkin, V.E.

    1981-02-18

    Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu and /sup 241/Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island radioecology and dose assessment work.

  8. Assessment of microbial processes on gas production at radioactive low-level waste disposal sites

    SciTech Connect (OSTI)

    Weiss, A.J.; Tate, R.L. III; Colombo, P.

    1982-05-01

    Factors controlling gaseous emanations from low level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide, and possible hydrogen from the site, stems from the inclusion of tritium and/or carbon-14 into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste material, primary emphasis of the study involved an examination of the biochemical pathways producing methane, carbon dioxide, and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Initial examination of the data indicates that the ecosystem is anaerobic. As the result of the complexity of the pathway leading to methane production, factors such as substrate availability, which limit the initial reaction in the sequence, greatly affect the overall rate of methane evolution. Biochemical transformations of methane, hydrogen and carbon dioxide as they pass through the soil profile above the trench are discussed. Results of gas studies performed at three commercial low level radioactive waste disposal sites are reviewed. Methods used to obtain trench and soil gas samples are discussed. Estimates of rates of gas production and amounts released into the atmosphere (by the GASFLOW model) are evaluated. Tritium and carbon-14 gaseous compounds have been measured in these studies; tritiated methane is the major radionuclide species in all disposal trenches studied. The concentration of methane in a typical trench increases with the age of the trench, whereas the concentration of carbon dioxide is similar in all trenches.

  9. 2015-01 "Identification and Preparation of Interim Disposition Site(s) to Enable LANL Transuranic Disposal Operations and Nation’s Other Sites’ Waste Disposal Operations to Remain Continually Operational"

    Broader source: Energy.gov [DOE]

    Approved March 11, 2015 It is the intent of the NNMCAB to assure that operations at DOE and LANL regarding the safe handling, transport, and disposal of transuranic waste from LANL, as well as other generator sites to WIPP, accelerate and make more transparent, any activities in motion or planned, that will re-establish nuclear disposal pathways and destinations.

  10. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-10-04

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.

  11. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

    Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

    2000-06-01

    The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

  12. The relationship between interannual and long-term cloud feedbacks

    SciTech Connect (OSTI)

    Zhou, Chen; Zelinka, Mark D.; Dessler, Andrew E.; Klein, Stephen A.

    2015-12-11

    The analyses of Coupled Model Intercomparison Project phase 5 simulations suggest that climate models with more positive cloud feedback in response to interannual climate fluctuations also have more positive cloud feedback in response to long-term global warming. Ensemble mean vertical profiles of cloud change in response to interannual and long-term surface warming are similar, and the ensemble mean cloud feedback is positive on both timescales. However, the average long-term cloud feedback is smaller than the interannual cloud feedback, likely due to differences in surface warming pattern on the two timescales. Low cloud cover (LCC) change in response to interannual and long-term global surface warming is found to be well correlated across models and explains over half of the covariance between interannual and long-term cloud feedback. In conclusion, the intermodel correlation of LCC across timescales likely results from model-specific sensitivities of LCC to sea surface warming.

  13. Fuzzy multicriteria disposal method and site selection for municipal solid waste

    SciTech Connect (OSTI)

    Ekmekcioglu, Mehmet; Kaya, Tolga; Kahraman, Cengiz

    2010-08-15

    The use of fuzzy multiple criteria analysis (MCA) in solid waste management has the advantage of rendering subjective and implicit decision making more objective and analytical, with its ability to accommodate both quantitative and qualitative data. In this paper a modified fuzzy TOPSIS methodology is proposed for the selection of appropriate disposal method and site for municipal solid waste (MSW). Our method is superior to existing methods since it has capability of representing vague qualitative data and presenting all possible results with different degrees of membership. In the first stage of the proposed methodology, a set of criteria of cost, reliability, feasibility, pollution and emission levels, waste and energy recovery is optimized to determine the best MSW disposal method. Landfilling, composting, conventional incineration, and refuse-derived fuel (RDF) combustion are the alternatives considered. The weights of the selection criteria are determined by fuzzy pairwise comparison matrices of Analytic Hierarchy Process (AHP). It is found that RDF combustion is the best disposal method alternative for Istanbul. In the second stage, the same methodology is used to determine the optimum RDF combustion plant location using adjacent land use, climate, road access and cost as the criteria. The results of this study illustrate the importance of the weights on the various factors in deciding the optimized location, with the best site located in Catalca. A sensitivity analysis is also conducted to monitor how sensitive our model is to changes in the various criteria weights.

  14. Gas Generation Rates as an Indicator for the Long Term Stability of Radioactive Waste Products

    SciTech Connect (OSTI)

    Steyer, S.; Brennecke, P.; Bandt, G.; Kroger, H.

    2007-07-01

    Pursuant to the 'Act on the Peaceful Utilization of Atomic Energy and the Protection against its Hazards' (Atomic Energy Act) the Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz, BfS) is legally responsible for the construction and operation of federal facilities for the disposal of radioactive waste. Within the scope of this responsibility, particular due to par. 74(1) Ordinance on Radiation Protection, BfS defines all safety-related requirements on waste packages envisaged for disposal, establishes guidelines for the conditioning of radioactive waste and approves the fulfillment of the waste acceptance requirements within the radioactive waste quality control system. BfS also provides criteria to enable the assessment of methods for the treatment and packaging of radioactive waste to produce waste packages suitable for disposal according to par. 74(2) Ordinance on Radiation Protection. Due to the present non-availability of a repository in Germany, quality control measures for all types of radioactive waste products are carried out prior to interim storage with respect to the future disposal. As a result BfS approves the demonstrated properties of the radioactive waste packages and confirms the fulfillment of the respective requirements. After several years of storage the properties of waste packages might have changed. By proving, that such changes have no significant impact on the quality of the waste product, the effort of requalification could be minimized. Therefore, data on the long-term behavior of radioactive waste products need to be acquired and indicators to prove the long-term stability have to be quantified. Preferably, such indicators can be determined easily with non-destructive methods, even for legacy waste packages. A promising parameter is the gas generation rate. The relationship between gas generation rate and long term stability is presented as first result of an ongoing study on behalf of BfS. Permissible gas generation rates that ensure adequate product stability with respect to future disposal are to be identified. (authors)

  15. Example of a Risk-Based Disposal Approval: Solidification of Hanford Site Transuranic Waste

    SciTech Connect (OSTI)

    Barnes, B.M.; Hyatt, J.E.; Martin, P.W.; Prignano, A.L.

    2008-07-01

    The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26, 2005 to June 9, 2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP. (authors)

  16. EXAMPLE OF A RISK BASED DISPOSAL APPROVAL SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

    SciTech Connect (OSTI)

    PRIGNANO AL

    2007-11-14

    The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26,2005 to June 9,2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP.

  17. EIS-0113: Disposal of Hanford Defense High-Level, Transuranic and Tank Waste, Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this EIS to examine the potential environmental impacts of final disposal options for legacy and future radioactive defense wastes stored at the Hanford Site.

  18. Site A/Plot M Disposal Site, Chicago, Illinois, Fact Sheet

    Office of Legacy Management (LM)

    Art Kleinrath (970) 248-6037 Audrey Berry, Public Affairs (970) 248-7727 or visit the Internet site at StabilizationIsolation Approach LTSM Program Activities Contacts , LTSM...

  19. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)

    SciTech Connect (OSTI)

    1996-11-01

    During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

  20. Long-Term Stewardship Study | Department of Energy

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

    Long-Term Stewardship Study Long-Term Stewardship Study The Department of Energy (DOE) has prepared this Long-term Stewardship Study ("Study" or "Final Study") to comply with the terms of a settlement agreement between DOE, the Natural Resources Defense Council, and 38 other plaintiffs [Natural Resources Defense Council, et al. v. Richardson, et al., Civ. No. 97-936 (SS) (D.D.C. Dec. 12, 1998)]. The Study describes and analyzes several issues and a variety of information

  1. Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Dorries, Alison M

    2010-11-09

    Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

  2. Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-01-01

    This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

  3. RACORO long-term, systematic aircraft observations of boundary...

    Office of Scientific and Technical Information (OSTI)

    22 January and 30 June 2009. This was the first time that a long-term aircraft campaign ... set of instrumentsmore to measure solar and thermal radiation, cloud microphysics, ...

  4. Experimental apparatus and software design for dynamic long-term

    Office of Scientific and Technical Information (OSTI)

    reliability testing of a spring-mass MEMS device. (Conference) | SciTech Connect Experimental apparatus and software design for dynamic long-term reliability testing of a spring-mass MEMS device. Citation Details In-Document Search Title: Experimental apparatus and software design for dynamic long-term reliability testing of a spring-mass MEMS device. No abstract prepared. Authors: Parson, Ted Blair ; Reu, Phillip L. ; Tanner, Danelle Mary ; Boyce, Brad Lee ; Epp, David S. Publication Date:

  5. Long-term inverter operation demonstration at Sandia National Laboratories.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Long-term inverter operation demonstration at Sandia National Laboratories. Citation Details In-Document Search Title: Long-term inverter operation demonstration at Sandia National Laboratories. No abstract prepared. Authors: Ellis, Abraham ; Kuszmaul, Scott S. ; Gonzalez, Sigifredo Publication Date: 2009-06-01 OSTI Identifier: 966623 Report Number(s): SAND2009-3488C TRN: US200921%%513 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource

  6. Operational Simulation Tools and Long Term Strategic Planning for High

    Energy Savers [EERE]

    Penetrations of PV in the Southeastern U.S. | Department of Energy Operational Simulation Tools and Long Term Strategic Planning for High Penetrations of PV in the Southeastern U.S. Operational Simulation Tools and Long Term Strategic Planning for High Penetrations of PV in the Southeastern U.S. EPRI logo.jpg In collaboration with the Tennessee Valley Authority Southern Company, the Sacramento Municipal Utility District, the California Independent System Operator, and other partners,

  7. Los Alamos National Laboratory announces strategy for long-term

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

    environmental sustainability Strategy for long-term environmental sustainability Los Alamos National Laboratory announces strategy for long-term environmental sustainability Provides a blueprint for protecting the environment while accomplishing the Lab's national security missions. March 1, 2013 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience,

  8. Evaluating Transport and Attenuation of Inorganic Contaminants in the Vadose Zone for Aqueous Waste Disposal Sites

    SciTech Connect (OSTI)

    Truex, Michael J.; Oostrom, Martinus; Tartakovsky, Guzel D.

    2015-09-01

    An approach was developed for evaluating vadose zone transport and attenuation of aqueous wastes containing inorganic (non-volatile) contaminants that were disposed of at the land surface (i.e., directly to the ground in cribs, trenches, tile fields, etc.) and their effect on the underlying groundwater. The approach provides a structured method for estimating transport of contaminants through the vadose zone and the resulting temporal profile of groundwater contaminant concentrations. The intent of the approach is also to provide a means for presenting and explaining the results of the transport analysis in the context of the site-specific waste disposal conditions and site properties, including heterogeneities and other complexities. The document includes considerations related to identifying appropriate monitoring to verify the estimated contaminant transport and associated predictions of groundwater contaminant concentrations. While primarily intended for evaluating contaminant transport under natural attenuation conditions, the approach can also be applied to identify types of, and targets for, mitigation approaches in the vadose zone that would reduce the temporal profile of contaminant concentrations in groundwater, if needed.

  9. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Reneau, S.L.; Raymond, R. Jr.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

  10. Slope and bank erosional stability of the Canonsburg, Pennsylvania, UMTRA disposal site

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This report was prepared in response to US Nuclear Regulatory Commission (NRC) comments received in a letter of 8 March 1994. This letter included discussions of the US Department of Energy (DOE) 21 May 1993 geomorphic report for the Canonsburg, Pennsylvania, site. To clarify the NRC`s position, a DOE/NRC conference call was held on 12 April 1994. The NRC clarified that it did not require a preliminary erosion protection design for the Canonsburg site, but directed the DOE to address a ``one-bad-year`` scenario. The NRC wants confirmation that one bad year of stream flooding and landsliding will not release residual radioactive material (RRM) from the Canonsburg site into the creek. The NRC is concerned that a bad year theoretically could occur between postcell-closure inspections. These annual inspections are conducted in September or October. The NRC suggested that the following procedures should be conducted in this analysis: a flooding analysis, including the maximum saturation levels (flood water elevations) anticipated during a 100-year flood; a stream bank erosion analysis to determine how much of the bank adjacent to the site may be removed in a bad year; a slope stability analysis to determine how far back the site would be disturbed by slope instability that could be triggered by a bad year of stream bank erosion; and a ``critical cross section`` study to show the relationship of the RRM located outside the disposal cell to the maximum computer estimated erosion/landslide activity.

  11. Innovative Strategy For Long Term Monitoring Of Metal And Radionuclide Plumes

    SciTech Connect (OSTI)

    Eddy-Dilek, Carol; Millings, Margaret R.; Looney, Brian B.; Denham, Miles E.

    2014-01-08

    Many government and private industry sites that were once contaminated with radioactive and chemical wastes cannot be cleaned up enough to permit unrestricted human access. The sites will require long term management, in some cases indefinitely, leaving site owners with the challenge of protecting human health and environmental quality at these "legacy" sites. Long-term monitoring of groundwater contamination is one of the largest projected costs in the life cycle of environmental management at the Savannah River Site, the larger DOE complex, and many large federal and private sites. There is a need to optimize the performance and manage the cost of long term surveillance and monitoring at their sites. Currently, SRNL is initiating a pilot field test using alternative protocols for long term monitoring of metals and radionuclides. A key component of the approach is that monitoring efforts are focused on measurement of low cost metrics related to hydrologic and chemical conditions that control contaminant migration. The strategy combines careful monitoring of hydrologic boundary conditions with measurement of master variables such as chemical surrogates along with a smaller number of standard well analyses. In plumes contaminated with metals, master variables control the chemistry of the groundwater system, and include redox variables (ORP, DO, chemicals), pH, specific conductivity, biological community (breakdown/decay products), and temperature. Significant changes in these variables will result in conditions whereby the plume may not be stable and therefore can be used to predict possible plume migration. Conversely, concentration measurements for all types of contaminants in groundwater are a lagging indicator plume movement - major changes contaminant concentrations indicate that contamination has migrated. An approach based on measurement of master variables and explicit monitoring of hydrologic boundary conditions combined with traditional metrics should lead to improved monitoring while simultaneously reducing costs. This paradigm is being tested at the SRS F-Area where an innovative passive remedial system is being monitored and evaluated over the long term prior to traditional regulatory closure. Contaminants being addressed at this site are uranium, strontium-90, iodine-129, and tritium. We believe that the proposed strategies will be more effective in early identification of potential risks; these strategies will also be cost effective because controlling variables are relatively simple to measure. These variables also directly reflect the evolution of the plume through time, so that the monitoring strategy can be modified as the plume 'ages'. This transformational long-term monitoring paradigm will generate large cost savings to DOE, other federal agencies and industry and will provide improved performance and leading indicators of environmental management performance.

  12. The relationship between interannual and long-term cloud feedbacks

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhou, Chen; Zelinka, Mark D.; Dessler, Andrew E.; Klein, Stephen A.

    2015-12-11

    The analyses of Coupled Model Intercomparison Project phase 5 simulations suggest that climate models with more positive cloud feedback in response to interannual climate fluctuations also have more positive cloud feedback in response to long-term global warming. Ensemble mean vertical profiles of cloud change in response to interannual and long-term surface warming are similar, and the ensemble mean cloud feedback is positive on both timescales. However, the average long-term cloud feedback is smaller than the interannual cloud feedback, likely due to differences in surface warming pattern on the two timescales. Low cloud cover (LCC) change in response to interannual andmore » long-term global surface warming is found to be well correlated across models and explains over half of the covariance between interannual and long-term cloud feedback. In conclusion, the intermodel correlation of LCC across timescales likely results from model-specific sensitivities of LCC to sea surface warming.« less

  13. Long-term decontamination engineering study. Volume 1

    SciTech Connect (OSTI)

    Geuther, W.J.

    1995-04-03

    This report was prepared by Westinghouse Hanford Company (WHC) with technical and cost estimating support from Pacific Northwest Laboratories (PNL) and Parsons Environmental Services, Inc. (Parsons). This engineering study evaluates the requirements and alternatives for decontamination/treatment of contaminated equipment at the Hanford Site. The purpose of this study is to determine the decontamination/treatment strategy that best supports the Hanford Site environmental restoration mission. It describes the potential waste streams requiring treatment or decontamination, develops the alternatives under consideration establishes the criteria for comparison, evaluates the alternatives, and draws conclusions (i.e., the optimum strategy for decontamination). Although two primary alternatives are discussed, this study does identify other alternatives that may warrant additional study. hanford Site solid waste management program activities include storage, special processing, decontamination/treatment, and disposal facilities. This study focuses on the decontamination/treatment processes (e.g., waste decontamination, size reduction, immobilization, and packaging) that support the environmental restoration mission at the Hanford Site.

  14. Regulatory Framework for Salt Waste Disposal and Tank Closure at the Savannah River Site - 13663

    SciTech Connect (OSTI)

    Thomas, Steve; Dickert, Ginger

    2013-07-01

    The end of the Cold War has left a legacy of approximately 37 million gallons of radioactive waste in the aging waste tanks at the Department of Energy's Savannah River Site (SRS). A robust program is in place to remove waste from these tanks, treat the waste to separate into a relatively small volume of high-level waste and a large volume of low-level waste, and to actively dispose of the low-level waste on-site and close the waste tanks and associated ancillary structures. To support performance-based, risk-informed decision making and to ensure compliance with all regulatory requirements, the U.S. Department of Energy (DOE) and its current and past contractors have worked closely with the South Carolina Department of Health and Environmental Control (SCDHEC), the U.S. Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC) to develop and implement a framework for on-site low-level waste disposal and closure of the SRS waste tanks. The Atomic Energy Act of 1954, as amended, provides DOE the authority to manage defense-related radioactive waste. DOE Order 435.1 and its associated manual and guidance documents detail this radioactive waste management process. The DOE also has a requirement to consult with the NRC in determining that waste that formerly was classified as high-level waste can be safely managed as either low-level waste or transuranic waste. Once DOE makes a determination, NRC then has a responsibility to monitor DOE's actions in coordination with SCDHEC to ensure compliance with the Title 10 Code of Federal Regulations Part 61 (10CFR61), Subpart C performance objectives. The management of hazardous waste substances or components at SRS is regulated by SCDHEC and the EPA. The foundation for the interactions between DOE, SCDHEC and EPA is the SRS Federal Facility Agreement (FFA). Managing this array of requirements and successfully interacting with regulators, consultants and stakeholders is a challenging task but ensures thorough and thoughtful processes for disposing of the SRS low-level waste and the closure of the tank farm facilities. (authors)

  15. 1997 Hanford site report on land disposal restrictions for mixed waste

    SciTech Connect (OSTI)

    Black, D.G.

    1997-04-07

    The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

  16. Long-term protection of uranium mill tailings

    SciTech Connect (OSTI)

    Beedlow, P.A.; Hartley, J.N.

    1984-04-01

    US Environmental Protection Agency standards for the cleanup and disposal of inactive tailings sites require that control measures for disposal of tailings be designed to be effective for up to 1000 years if reasonably achievable, and, in any case, for 200 years at least. To control the escape of contaminants over such long periods, containment systems must be capable of adjusting to changing environmental conditions. Elements of a containment system include surface covers, biotic barriers, radon barriers, and, in some cases, liners. Each element of the system affects the others, and the whole system responds to the surrounding environment. Interaction is facilitated primarily by soil moisture. Consequently, the control of soil moisture is critical to the effectiveness of containment systems. Protective covers are necessary to prevent disruption of the containment system by physical or biological factors, to provide for the effective functioning of the radon barrier, and to prevent infiltration of excess water that could cause leaching. In order to design protective covers, a working knowledge of the factors and processes impacting tailings piles is required. This report characterizes the major factors and processes, and presents generic solutions based on current research. 65 references, 9 figures, 6 tables.

  17. Tribal Renewable Energy Webinar: Project Development for Long Term Tribal

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

    Energy | Department of Energy Development for Long Term Tribal Energy Tribal Renewable Energy Webinar: Project Development for Long Term Tribal Energy July 27, 2016 11:00AM to 12:30PM MDT Get details about the DOE Office of Indian Energy's five-step process for developing renewable energy projects on tribal lands and how they are important to the success of any energy project. The webinar will cover how to determine project savings and production potential estimates, define project options,

  18. Summary, Long-Term Nuclear Technology Research and Development Plan |

    Energy Savers [EERE]

    Department of Energy Summary, Long-Term Nuclear Technology Research and Development Plan Summary, Long-Term Nuclear Technology Research and Development Plan In 1998, DOE established the Nuclear Energy Research Advisory Committee (NERAC) to provide advice to the Secretary and to the Director, Office of Nuclear Energy, Science, and Technology (NE), on the broad range of non-defense DOE nuclear technology programs. The NERAC recommended development of a long-range R&D program. This R&D

  19. ARM - Field Campaign - Long-Term Microwave Radiometer Intercomparison

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

    govCampaignsLong-Term Microwave Radiometer Intercomparison ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : Long-Term Microwave Radiometer Intercomparison 2001.04.01 - 2001.09.30 Lead Scientist : Richard Cederwall For data sets, see below. Summary Make the spare MWR operational. Ingest data from the spare MWR. Input the output data of the spare MWR and ingest to VAP. Provide data to IOP participants.

  20. Technical Scope and Approach for the 2004 Composite Analysis of Low Level Waste Disposal at the Hanford Site

    SciTech Connect (OSTI)

    Kincaid, Charles T.; Bryce, Robert W.; Buck, John W.

    2004-07-09

    A composite analysis is required by U.S. Department of Energy (DOE) Manual 435.1-1 to ensure public safety through the management of active and planned low-level radioactive waste disposal facilities associated with the Hanford Site (DOE/HQ-Manual 435.1-1). A Composite Analysis is defined as ''a reasonably conservative assessment of the cumulative impact from active and planned low-level waste disposal facilities, and all other sources from radioactive contamination that could interact with the low-level waste disposal facility to affect the dose to future members of the public''. At the Hanford Site, a composite analysis is required for continued disposal authorization for the immobilized low-activity waste, tank waste vitrification plant melters, low level waste in the 200 East and 200 West Solid Waste Burial Grounds, and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) waste in the Environmental Restoration Disposal Facility. The 2004 Composite Analysis will be a site-wide analysis, considering final remedial actions for the Columbia River corridor and the Central Plateau at the Hanford Site. The river corridor includes waste sites and facilities in each of the 100 Areas as well as the 300, 400, and 600 Areas. The remedial actions for the river corridor are being conducted to meet residential land use standards with the vision of the river corridor being devoted to a combination of recreation and preservation. The ''Central Plateau'' describes the region associated with operations and waste sites of the 200 Areas. DOE is developing a strategy for closure of the Central Plateau area by 2035. At the time of closure, waste management activities will shrink to a Core Zone within the Central Plateau. The Core Zone will contain the majority of Hanford's permanently disposed waste

  1. DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

    SciTech Connect (OSTI)

    SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

    2011-01-13

    Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

  2. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2007-06-01

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

  3. Uranium Mill Tailings Radiation Control Act Sites Fact Sheet

    Energy Savers [EERE]

    This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act Title I and II disposal and processing sites. The sites are managed by the U.S. Department of Energy Office of Legacy Management. Introduction The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604) is a federal law that provides for the safe and environmentally sound disposal, long-term stabilization, and control of uranium mill tailings in a manner that minimizes or

  4. Systems Long Term Exposure Program: Analysis of the First Year of

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

    Systems Engineering and Integration Systems Engineering and Integration Systems Engineering and Integration The fuel cycle in use today in the United States faces challenges in achieving the goals of sustainability. While used fuel is safely stored at reactor sites, the development of a system to manage all of the waste now and in the future has proven to be a persistently difficult task. Uncertainties about long-term resource availability make it difficult to properly value reusable material in

  5. Long-Term Hydrologic Monitoring Program Sampling and Analysis Results for 2009

    SciTech Connect (OSTI)

    2010-01-21

    The U.S. Department of Energy (DOE) Office of Legacy Management conducted annual sampling at the Rulison, Colorado, Site for the Long-Term Hydrologic Monitoring Program (LTHMP) on May 11 and 12, 2009. Samples were analyzed by the U.S. Environmental Protection Agency (EPA) Radiation&Indoor Environments National Laboratory in Las Vegas, Nevada. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectroscopy and for tritium using the conventional and enriched methods.

  6. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.

    1996-03-01

    A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

  7. Evapotranspiration Dynamics and Effects on Groundwater Recharge and Discharge at the Tuba City, Arizona, Disposal Site: Final Report

    Office of Scientific and Technical Information (OSTI)

    Evapotranspiration Dynamics and Effects on Groundwater Recharge and Discharge at the Tuba City, Arizona, Disposal Site February 2016 LMS/TUB/S13751 ESL-RPT-2016-02 Prepared for U.S. DEPARTMENT OF ENERGY Legacy Management This page intentionally left blank Contents Abbreviations.................................................................................................................................................... iii Executive

  8. DOE Issues RFI and Industry Day Announcement on Optimal Design of Saltstone Disposal Units at the Savannah River Site

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. (January 11, 2016) – DOE has announced release of a Request for Information (RFI) on the optimal design of Saltstone Disposal Units (SDU) in support of the Savannah River Site (SRS) liquid waste program mission, along with plans to hold an Industry Day to provide additional information on the SDU project.

  9. EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE’s Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012.

  10. Ocean FUSRAP: feasibility of ocean disposal of materials from the Formerly Utilized Sites Remedial Action Progam (FUSRAP)

    SciTech Connect (OSTI)

    Kupferman, S.L.; Anderson, D.R.; Brush, L.H.; Gomez, L.S.; Laul, J.C.; Shephard, L.E.

    1982-01-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) of the Department of Energy is designed to identify and evaluate the radiological conditions at sites formerly used by the Corps of Engineers Manhattan Engineer District and the US Atomic Energy Commission. Where required, remedial action will be instituted to remove potential restrictions on the use of the sites due to residual low-level radioactive contamination. A total of 31 sites that may require remedial action has been identified. The purpose of the Ocean FUSRAP Program, which began in March 1981, is to assess the technical, environmental, and institutional feasibility of disposing, in the ocean and on the ocean floor, of FUSRAP soil and rubble which contains traces of natural radioactive materials. The initial focus has been on the Middlesex, New Jersey, Sampling Plant site and surrounding properties, which contain on the order of 100,000 metric tons of material. The Belgian Congo uranium ore and other uranium ores used by the United States were handled at the sampling plant site. In studying the feasibility of ocean disposal of FUSRAP material from Middlesex, New Jersey, we have begun to examine institutional requirements to be met, the composition of the source material with regard to its inventory of toxic chemical and radiochemical components and the impact of the source material in the marine environment. To date we have found nothing that would preclude safe and inexpensive disposal of this material in the ocean.

  11. China-Medium and Long Term Energy Conservation Plan | Open Energy...

    Open Energy Info (EERE)

    Medium and Long Term Energy Conservation Plan Jump to: navigation, search Name China-Medium and Long Term Energy Conservation Plan AgencyCompany Organization Government of China...

  12. PORTSMOUTH ON-SITE DISPOSAL CELL HIGH DENSITY POLYETHYLENE GEOMEMBRANE LONGEVITY

    SciTech Connect (OSTI)

    Phifer, M.

    2012-01-31

    It is anticipated that high density polyethylene (HDPE) geomembranes will be utilized within the liner and closure cap of the proposed On-Site Disposal Cell (OSDC) at the Portsmouth Gaseous Diffusion Plant. The likely longevity (i.e. service life) of HDPE geomembranes in OSDC service is evaluated within the following sections of this report: (1) Section 2.0 provides an overview of HDPE geomembranes, (2) Section 3.0 outlines potential HDPE geomembranes degradation mechanisms, (3) Section 4.0 evaluates the applicability of HDPE geomembrane degradation mechanisms to the Portsmouth OSDC, (4) Section 5.0 provides a discussion of the current state of knowledge relative to the longevity (service life) of HDPE geomembranes, including the relation of this knowledge to the Portsmouth OSDC, and (5) Section 6.0 provides summary and conclusions relative to the anticipated service life of HDPE geomembranes in OSDC service. Based upon this evaluation it is anticipated that the service life of HDPE geomembranes in OSDC service would be significantly greater than the 200 year service life assumed for the OSDC closure cap and liner HDPE geomembranes. That is, a 200 year OSDC HDPE geomembrane service life is considered a conservative assumption.

  13. Geologic processes in the RWMC area, Idaho National Engineering Laboratory: Implications for long term stability and soil erosion at the radioactive waste management complex

    SciTech Connect (OSTI)

    Hackett, W.R.; Tullis, J.A.; Smith, R.P.

    1995-09-01

    The Radioactive Waste Management Complex (RWMC) is the disposal and storage facility for low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). Transuranic waste and mixed wastes were also disposed at the RWMC until 1970. It is located in the southwestern part of the INEL about 80 km west of Idaho Falls, Idaho. The INEL occupies a portion of the Eastern Snake River Plain (ESRP), a low-relief, basalt, and sediment-floored basin within the northern Rocky Mountains and northeastern Basin and Range Province. It is a cool and semiarid, sagebrush steppe desert characterized by irregular, rolling terrain. The RWMC began disposal of INEL-generated wastes in 1952, and since 1954, wastes have been accepted from other Federal facilities. Much of the waste is buried in shallow trenches, pits, and soil vaults. Until about 1970, trenches and pits were excavated to the basalt surface, leaving no sediments between the waste and the top of the basalt. Since 1970, a layer of sediment (about 1 m) has been left between the waste and the basalt. The United States Department of Energy (DOE) has developed regulations specific to radioactive-waste disposal, including environmental standards and performance objectives. The regulation applicable to all DOE facilities is DOE Order 5820.2A (Radioactive Waste Management). An important consideration for the performance assessment of the RWMC is the long-term geomorphic stability of the site. Several investigators have identified geologic processes and events that could disrupt a radioactive waste disposal facility. Examples of these {open_quotes}geomorphic hazards{close_quotes} include changes in stream discharge, sediment load, and base level, which may result from climate change, tectonic processes, or magmatic processes. In the performance assessment, these hazards are incorporated into scenarios that may affect the future performance of the RWMC.

  14. 9975 SHIPPING PACKAGE PERFORMANCE OF ALTERNATE MATERIALS FOR LONG-TERM STORAGE APPLICATION

    SciTech Connect (OSTI)

    Skidmore, E.; Hoffman, E.; Daugherty, W.

    2010-02-24

    The Model 9975 shipping package specifies the materials of construction for its various components. With the loss of availability of material for two components (cane fiberboard overpack and Viton{reg_sign} GLT O-rings), alternate materials of construction were identified and approved for use for transport (softwood fiberboard and Viton{reg_sign} GLT-S O-rings). As these shipping packages are part of a long-term storage configuration at the Savannah River Site, additional testing is in progress to verify satisfactory long-term performance of the alternate materials under storage conditions. The test results to date can be compared to comparable results on the original materials of construction to draw preliminary conclusions on the performance of the replacement materials.

  15. Summary of the engineering analysis report for the long-term management of depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Dubrin, J.W., Rahm-Crites, L.

    1997-09-01

    The Department of Energy (DOE) is reviewing ideas for the long-term management and use of its depleted uranium hexafluoride. DOE owns about 560,000 metric tons (over a billion pounds) of depleted uranium hexafluoride. This material is contained in steel cylinders located in storage yards near Paducah, Kentucky; Portsmouth, Ohio; and at the East Tennessee Technology Park (formerly the K-25 Site) in Oak Ridge, Tennessee. On November 10, 1994, DOE announced its new Depleted Uranium Hexafluoride Management Program by issuing a Request for Recommendations and an Advance Notice of Intent in the Federal Register (59 FR 56324 and 56325). The first part of this program consists of engineering, costs and environmental impact studies. Part one will conclude with the selection of a long-term management plan or strategy. Part two will carry out the selected strategy.

  16. Long-Term Spatial Data Preservation and Archiving: What Are the Issues?

    SciTech Connect (OSTI)

    BLEAKLY, DENISE R.

    2002-01-01

    The Department of Energy (DOE) is moving towards Long-Term Stewardship (LTS) of many environmental restoration sites that cannot be released for unrestricted use. One aspect of information management for LTS is geospatial data archiving. This report discusses the challenges facing the DOE LTS program concerning the data management and archiving of geospatial data. It discusses challenges in using electronic media for archiving, overcoming technological obsolescence, data refreshing, data migration, and emulation. It gives an overview of existing guidance and policy and discusses what the United States Geological Service (USGS), National Oceanic and Atmospheric Administration (NOAA) and the Federal Emergency Management Agency (FEMA) are doing to archive the geospatial data that their agencies are responsible for. In the conclusion, this report provides issues for further discussion around long-term spatial data archiving.

  17. Analyses of soils at commercial radioactive-waste-disposal sites. [Barnwell, SC; Richland, WA

    SciTech Connect (OSTI)

    Piciulo, P.L.; Shea, C.E.; Barletta, R.E.

    1982-01-01

    Brookhaven National Laboratory, in order to provide technical assistance to the NRC, has measured a number of physical and chemical characteristics of soils from two currently operating commercial radioactive waste disposal sites; one at Barnwell, SC, and the other near Richland, WA. Soil samples believed to be representative of the soil that will contact the buried waste were collected and analyzed. Earth resistivities (field measurements), from both sites, supply information to identify variations in subsurface material. Barnwell soil resistivities (laboratory measurements) range from 3.6 x 10/sup 5/ ohm-cm to 8.9 x 10/sup 4/ ohm-cm. Soil resistivities of the Hanford sample vary from 3.0 x 10/sup 5/ ohm-cm to 6.6 x 10/sup 3/ ohm-cm. The Barnwell and Hanford soil pH ranges from 4.8 to 5.4 and from 4.0 to 7.2 respectively. The pH of a 1:2 mixture of soil to 0.01 M CaCl/sub 2/ resulted in a pH for the Barnwell samples of 3.9 +- 0.1 and for the Hanford samples of 7.4 +- 0.2. These values are comparable to the pH measurements of the water extract of the soils used for the analyses of soluble ion content of the soils. The exchange acidity of the soils was found to be approximately 7 mg-eq per 100 g of dry soil for clay material from Barnwell, whereas the Hanford soils showed an alkaline reaction. Aqueous extracts of saturated pastes were used to determine the concentrations of the following ions: Ca/sup 2 +/, Mg/sup 2 +/, K/sup +/, Na/sup +/, HCO/sub 3//sup -/, SO/sub 4//sup =/, and Cl/sup -/. The sulfide content of each of the soils was measured in a 1:2.5 mixture of soil to an antioxidant buffer solution. The concentrations of soluble ions found in the soils from both sites are consistent with the high resistivities.

  18. Long term prediction and the SSC (Superconducting Super Collider)

    SciTech Connect (OSTI)

    Talman, R.

    1990-09-01

    Successful operation of the Superconducting Supercollider (SSC) will depend on the stable circulation of particles for tens of millions of turns around the rings, in the presence of small nonlinear deflecting fields. One design challenge is to set specifications for the maximum allowable field imperfections of this sort, consistent with the required. stability. Another challenge is to plan for the inclusion of field compensating elements that will ameliorate the effects of errors. The tools'' available for projecting the long term stability are theoretical, both analytic and numerical, and experimental. These aspects are reviewed. 19 refs.

  19. Interactive long-term simulation for power system restoration planning

    SciTech Connect (OSTI)

    Fountas, N.A.; Hatziargyriou, N.D. [National Technical Univ., Athens (Greece)] [National Technical Univ., Athens (Greece); Orfanogiannis, C.; Tasoulis, A. [Public Power Corp., Athens (Greece)] [Public Power Corp., Athens (Greece)

    1997-02-01

    The problem of restoring a power system following a complete blackout is complex and multi-faceted. Many control actions have to be performed on time, while constraints such as power balance and system stability have to be carefully respected. In this paper, the application of long-term dynamic analysis in studying frequency and voltage responses due to load and generation mismatches in isolated systems or during extension of the existing system in the restoration phase is presented. Simulation results covering the main steps of the Hellenic power system restoration process following a recent total blackout are presented and discussed.

  20. Regulating for the long term: SMCRA and acid mine drainage

    SciTech Connect (OSTI)

    Shea, C.W.

    1995-12-31

    With the passage of the Surface Mining Control and Reclamation Act of 1977 (SMCRA), regulators and industry representatives expected to solve the problem of pollution of the Nation`s waterways caused by acidic discharges from coal mines. Eighteen years after the passage of SMCRA, hard issues of predicting, regulating and treating acid mine drainage remain. Acid mine drainage is most common in the coal seams of the Midwest and Appalachia: Pennsylvania, West Virginia, Maryland, Ohio, Illinois, and Tennessee. This article discusses regulation of coal mines and acid mine drainage for the long term.

  1. Long-term global nuclear energy and fuel cycle strategies

    SciTech Connect (OSTI)

    Krakowski, R.A.

    1997-09-24

    The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E{sup 3} (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E{sup 3} model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E{sup 3} model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues.

  2. Disposal in Crystalline Rocks: FY’15 Progress Report

    Broader source: Energy.gov [DOE]

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and...

  3. ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY

    SciTech Connect (OSTI)

    Smith, F.; Phifer, M.

    2014-04-10

    A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the Berea sandstone aquiver over time and does not conform to standard private water well construction practices. The bottom-line is that all predicted doses from the base case and five sensitivity cases fall well below the DOE all-pathways 25 mrem/yr Performance Objective.

  4. Composite analysis for low-level waste disposal in the 200 area plateau of the Hanford Site

    SciTech Connect (OSTI)

    Kincaid, C.T.; Bergeron, M.P.; Cole, C.R.

    1998-03-01

    This report presents the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis) prepared in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or planned low-level waste disposal actions: the solid waste burial grounds in the 200 West Area, the solid waste burial grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for immobilized low-activity waste. A single Composite Analysis was prepared for the Hanford Site considering only sources on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the {open_quotes}as low as reasonably achievable{close_quotes} concept is followed. The 100 mrem in a year limit was the maximum allowable all-pathways dose for 1000 years following Hanford Site closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment defined as the area between a buffer zone surrounding an exclusive waste management area on the 200 Area Plateau, and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was a multistep process involving the estimation or simulation of inventories; waste release to the environment; migration through the vadose zone, groundwater, and atmospheric pathways; and exposure and dose. Doses were estimated for scenarios based on agriculture, residential, industrial, and recreational land use. The radionuclides included in the vadose zone and groundwater pathway analyses of future releases were carbon-14, chlorine-36, selenium-79, technetium-99, iodine-129, and uranium isotopes.

  5. Remote Sensing Analysis of the Sierra Blanca (Faskin Ranch) Low-Level Radioactive Waste Disposal Site, Hudspeth County, Texas

    SciTech Connect (OSTI)

    LeMone, D. V.; Dodge, R.; Xie, H.; Langford, R. P.; Keller, G. R.

    2002-02-26

    Remote sensing images provide useful physical information, revealing such features as geological structure, vegetation, drainage patterns, and variations in consolidated and unconsolidated lithologies. That technology has been applied to the failed Sierra Blanca (Faskin Ranch) shallow burial low-level radioactive waste disposal site selected by the Texas Low-Level Radioactive Waste Disposal Authority. It has been re-examined using data from LANDSAT satellite series. The comparison of the earlier LANDSAT V (5/20/86) (30-m resolution) with the later new, higher resolution ETM imagery (10/23/99) LANDSAT VII data (15-m resolution) clearly shows the superiority of the LANDSAT VII data. The search for surficial indications of evidence of fatal flaws at the Sierra Blanca site utilizing was not successful, as it had been in the case of the earlier remote sensing analysis of the failed Fort Hancock site utilizing LANDSAT V data. The authors conclude that the tectonic activity at the Sierra Blanca site is much less recent and active than in the previously studied Fort Hancock site. The Sierra Blanca site failed primarily on the further needed documentation concerning a subsurface fault underneath the site and environmental justice issues. The presence of this fault was not revealed using the newer LANDSAT VII data. Despite this fact, it must be remembered that remote sensing provides baseline documentation for determining future physical and financial remediation responsibilities. On the basis of the two sites examined by LANDSAT remote sensing imaging, it is concluded that it is an essential, cost-effective tool that should be utilized not only in site examination but also in all nuclear-related facilities.

  6. Assessing Long-Term Wind Conditions by Combining Different Measure-Correlate-Predict Algorithms: Preprint

    SciTech Connect (OSTI)

    Zhang, J.; Chowdhury, S.; Messac, A.; Hodge, B. M.

    2013-08-01

    This paper significantly advances the hybrid measure-correlate-predict (MCP) methodology, enabling it to account for variations of both wind speed and direction. The advanced hybrid MCP method uses the recorded data of multiple reference stations to estimate the long-term wind condition at a target wind plant site. The results show that the accuracy of the hybrid MCP method is highly sensitive to the combination of the individual MCP algorithms and reference stations. It was also found that the best combination of MCP algorithms varies based on the length of the correlation period.

  7. Revegetation/rock cover for stabilization of inactive uranium mill tailings disposal sites

    SciTech Connect (OSTI)

    Beedlow, P.A.; McShane, M.C.; Cadwell, L.L.

    1982-07-01

    Pacific Northwest Laboratory is developing design and performance guidelines for surface stabilization of inactive uranium mill tailings. In this work, vegetation and rock covers are being evaluated for maintaining long-term integrity of impoundment systems. Methods are being developed to estimate erosion rates associated with rock and/or vegetation covers, and to determine the effects of surface treatments on soil moisture. Interactions between surface treatments and barriers (radon and biological) are being studied as well. The product will be a set of guidelines to aid in designing surface covers. This report presents the status of this program and a discussion of considerations pertinent to the application of surface covers to tailings. Test plots located in Grand Junction, Colorado and Waterflow, New Mexico are being used to study: (1) the interactions between vegetation and radon and biological barriers, (2) the effects of surface covers on soil moisture, and (3) the effects of rock covers on vegetation.

  8. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Office of Environmental Management (EM)

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  9. Long term nuclear criticality potential in waste packages

    SciTech Connect (OSTI)

    Thomas, D.A.; Doering, T.W.

    1994-12-31

    Title 10 CFR 60.131.(b).(7) requires that the radioactive waste disposed of in the Mined Geologic Disposal System (MGDS) remain subcritical during the period of isolation. The period of waste isolation, approximately 10,000 years, represents a time period greater than any previously examined for criticality control of spent fuel. Change in the criticality potential over long time periods for the Multi-Purpose Canister (MPC) waste package conceptual design has been examined and methods of criticality control over this time have been investigated.

  10. Over 150 years of long-term fertilization alters spatial scaling of microbial biodiversity

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Liang, Yuting; Wu, Liyou; Clark, Ian M.; Xue, Kai; Yang, Yunfeng; Van Nostrand, Joy D.; Deng, Ye; He, Zhili; McGrath, Steve; Storkey, Jonathan; et al

    2015-04-07

    Spatial scaling is a critical issue in ecology, but how anthropogenic activities like fertilization affect spatial scaling is poorly understood, especially for microbial communities. Here, we determined the effects of long-term fertilization on the spatial scaling of microbial functional diversity and its relationships to plant diversity in the 150-year-old Park Grass Experiment, the oldest continuous grassland experiment in the world. Nested samples were taken from plots with contrasting inorganic fertilization regimes, and community DNAs were analyzed using the GeoChip-based functional gene array. The slopes of microbial gene-area relationships (GARs) and plant species-area relationships (SARs) were estimated in a plot receivingmore » nitrogen (N), phosphorus (P), and potassium (K) and a control plot without fertilization. Our results indicated that long-term inorganic fertilization significantly increased both microbial GARs and plant SARs. Microbial spatial turnover rates (i.e., z values) were less than 0.1 and were significantly higher in the fertilized plot (0.0583) than in the control plot (0.0449) (P < 0.0001). The z values also varied significantly with different functional genes involved in carbon (C), N, P, and sulfur (S) cycling and with various phylogenetic groups (archaea, bacteria, and fungi). Similarly, the plant SARs increased significantly (P < 0.0001), from 0.225 in the control plot to 0.419 in the fertilized plot. Soil fertilization, plant diversity, and spatial distance had roughly equal contributions in shaping the microbial functional community structure, while soil geochemical variables contributed less. Results indicated that long-term agricultural practice could alter the spatial scaling of microbial biodiversity. Determining the spatial scaling of microbial biodiversity and its response to human activities is important but challenging in microbial ecology. Most studies to date are based on different sites that may not be truly comparable or on short-term perturbations, and hence, the results observed could represent transient responses. This study examined the spatial patterns of microbial communities in response to different fertilization regimes at the Rothamsted Research Experimental Station, which has become an invaluable resource for ecologists, environmentalists, and soil scientists. The current study is the first showing that long-term fertilization has dramatic impacts on the spatial scaling of microbial communities. In addition, by identifying the spatial patterns in response to long-term fertilization and their underlying mechanisms, the study makes fundamental contributions to predictive understanding of microbial biogeography.« less

  11. Over 150 years of long-term fertilization alters spatial scaling of microbial biodiversity

    SciTech Connect (OSTI)

    Liang, Yuting; Wu, Liyou; Clark, Ian M.; Xue, Kai; Yang, Yunfeng; Van Nostrand, Joy D.; Deng, Ye; He, Zhili; McGrath, Steve; Storkey, Jonathan; Hirsch, Penny R.; Sun, Bo; Zhou, Jizhong

    2015-04-07

    Spatial scaling is a critical issue in ecology, but how anthropogenic activities like fertilization affect spatial scaling is poorly understood, especially for microbial communities. Here, we determined the effects of long-term fertilization on the spatial scaling of microbial functional diversity and its relationships to plant diversity in the 150-year-old Park Grass Experiment, the oldest continuous grassland experiment in the world. Nested samples were taken from plots with contrasting inorganic fertilization regimes, and community DNAs were analyzed using the GeoChip-based functional gene array. The slopes of microbial gene-area relationships (GARs) and plant species-area relationships (SARs) were estimated in a plot receiving nitrogen (N), phosphorus (P), and potassium (K) and a control plot without fertilization. Our results indicated that long-term inorganic fertilization significantly increased both microbial GARs and plant SARs. Microbial spatial turnover rates (i.e., z values) were less than 0.1 and were significantly higher in the fertilized plot (0.0583) than in the control plot (0.0449) (P < 0.0001). The z values also varied significantly with different functional genes involved in carbon (C), N, P, and sulfur (S) cycling and with various phylogenetic groups (archaea, bacteria, and fungi). Similarly, the plant SARs increased significantly (P < 0.0001), from 0.225 in the control plot to 0.419 in the fertilized plot. Soil fertilization, plant diversity, and spatial distance had roughly equal contributions in shaping the microbial functional community structure, while soil geochemical variables contributed less. Results indicated that long-term agricultural practice could alter the spatial scaling of microbial biodiversity. Determining the spatial scaling of microbial biodiversity and its response to human activities is important but challenging in microbial ecology. Most studies to date are based on different sites that may not be truly comparable or on short-term perturbations, and hence, the results observed could represent transient responses. This study examined the spatial patterns of microbial communities in response to different fertilization regimes at the Rothamsted Research Experimental Station, which has become an invaluable resource for ecologists, environmentalists, and soil scientists. The current study is the first showing that long-term fertilization has dramatic impacts on the spatial scaling of microbial communities. In addition, by identifying the spatial patterns in response to long-term fertilization and their underlying mechanisms, the study makes fundamental contributions to predictive understanding of microbial biogeography.

  12. Distribution of radionuclides and water in Bandelier Tuff beneath a former Los Alamos liquid waste disposal site after 33 years

    SciTech Connect (OSTI)

    Nyhan, J.W.; Drennon, B.J.; Abeele, W.V.; Trujillo, G.; Herrera, W.J.; Wheeler, M.L.; Booth, J.W.; Purtymun, W.D.

    1984-07-01

    The distribution of radionuclides and water in Bandelier Tuff beneath a former liquid waste disposal site at Los Alamos was investigated. The waste use history of the site was described, as well as several pertinent laboratory and field studies of water and radionuclide migration in Bandelier Tuff. The distribution of plutonium, /sup 241/Am, and water was determined in a set of about 800 tuff samples collected to sampling depths of 30 m beneath two absorption beds. These data were then related to site geohydrologic data. Water and radionuclide concentrations found after 33 years were compared with the results of similar studies previously performed at this site, and the implications of these comparisons are discussed relative to nuclear waste management. 19 references, 6 figures, 4 tables.

  13. Site: Contract Name: Contractor: Contract Number: Contract Type:

    Office of Environmental Management (EM)

    Department of Energy Framework for Long-Term Surveillance and Maintenance Site Transition Framework for Long-Term Surveillance and Maintenance Site Transition Framework for Long-Term Surveillance and Maintenance PDF icon Site Transition Framework for Long-Term Surveillance and Maintenance More Documents & Publications Site Transition Framework for Long-Term Surveillance and Maintenance Site Transition Process Upon Cleanup Completion Long-Term Stewardship Study

    Framework Site

  14. 1999 Report on Hanford Site land disposal restriction for mixed waste

    SciTech Connect (OSTI)

    BLACK, D.G.

    1999-03-25

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

  15. Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

    SciTech Connect (OSTI)

    Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

  16. Long-term desorption behavior of uranium and neptunium in heterogeneous volcanic tuff materials /

    SciTech Connect (OSTI)

    Dean, Cynthia A.

    2010-05-01

    Uranium and neptunium desorption were studied in long-term laboratory experiments using four well-characterized volcanic tuff cores collected from southeast of Yucca Mountain, Nevada. The objectives of the experiments were to 1. Demonstrate a methodology aimed at characterizing distributions of sorption parameters (attributes of multiple sorption sites) that can be applied to moderately-sorbing species in heterogeneous systems to provide more realistic reactive transport parameters and a more realistic approach to modeling transport in heterogeneous systems. 2. Focus on uranium and neptunium because of their high solubility, relatively weak sorption, and high contributions to predicted dose in Yucca Mountain performance assessments. Also, uranium is a contaminant of concern at many DOE legacy sites and uranium mining sites.

  17. EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017.

  18. Zambia : long-term generation expansion study - executive summary.

    SciTech Connect (OSTI)

    Conzelmann, G.; Koritarov, V.; Buehring, W.; Veselka, T.; Decision and Information Sciences

    2008-02-28

    The objective of this study is to analyze possible long-term development options of the Zambian electric power system in the period up to 2015. The analysis involved the hydro operations studies of the Zambezi river basin and the systems planning studies for the least-cost generation expansion planning. Two well-known and widely accepted computer models were used in the analysis: PC-VALORAGUA model for the hydro operations and optimization studies and the WASP-III Plus model for the optimization of long-term system development. The WASP-III Plus model is a part of the Argonne National Laboratory's Energy and Power Evaluation Model (ENPEP). The analysis was conducted in close collaboration with the Zambia Electricity Supply Corporation (ZESCO). On the initiative from The World Bank, the sponsor of the study, ZESCO formed a team of experts that participated in the analysis and were trained in the use of computer models. Both models were transferred to ZESCO free of charge and installed on several computers in the ZESCO corporate offices in Lusaka. In September-October 1995, two members of the ZESCO National Team participated in a 4-week training course at Argonne National Laboratory near Chicago, U.S.A., focusing on the long-term system expansion planning using the WASP and VALORAGUA models. The hydropower operations studies were performed for the whole Zambezi river basin, including the full installation of the Kariba power station, and the Cahora Bassa hydro power station in Mozambique. The analysis also included possible future projects such as Itezhi-Tezhi, Kafue Gorge Lower, and Batoka Gorge power stations. As hydropower operations studies served to determine the operational characteristics of the existing and future hydro power plants, it was necessary to simulate the whole Zambezi river basin in order to take into account all interactions and mutual influences between the hydro power plants. In addition, it allowed for the optimization of reservoir management and optimization of hydro cascades, resulting in the better utilization of available hydro potential. Numerous analyses were performed for different stages of system development. These include system configurations that correspond to years 1997, 2001, 2015 and 2020. Additional simulations were performed in order to determine the operational parameters of the three existing hydro power stations Victoria Falls, Kariba, and Kafue Gorge Upper, that correspond to the situation before and after their rehabilitation. The rehabilitation works for these three major power stations, that would bring their operational parameters and availability back to the design level, are planned to be carried out in the period until 2000. The main results of the hydro operations studies are presented in Table ES-1. These results correspond to VALORAGUA simulations of system configurations in the years 2001 and 2015. The minimum, average, and maximum electricity generation is based on the simulation of monthly water inflows that correspond to the chronological series of unregulated water inflows at each hydro profile in the period from April 1961 to March 1990. The recommended hydrology dataset provided in the Hydrology Report of the SADC Energy Project AAA 3.8 was used for this study.

  19. EIS-0269: Long-Term Management of Depleted Uranium Hexaflouride

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) prepared this programmatic environmental impact statement to assess the potential impacts of alternative management strategies for depleted uranium hexafluoride currently stored at three DOE sites: Paducah site near Paducah, Kentucky; Portsmouth site near Portsmouth, Ohio; and K-25 site on the Oak Ridge Reservation in Oak Ridge, Tennessee.

  20. Scoping evaluation of the technical capabilities of DOE sites for disposal of hazardous metals in mixed low-level waste

    SciTech Connect (OSTI)

    Gruebel, M.M.; Waters, R.D.; Langkopf, B.S.

    1997-05-01

    A team of analysts designed and conducted a scoping evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of the hazardous metals in mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Eight hazardous metals were evaluated: arsenic, barium, cadmium, chromium, lead, mercury, selenium, and silver. The analysis considered transport only through the groundwater pathway. The results are reported as site-specific estimates of maximum concentrations of each hazardous metal in treated mixed low-level waste that do not exceed the performance measures established for the analysis. Also reported are site-specific estimates of travel times of each hazardous metal to the point of compliance.

  1. Coupled Environmental Processes and Long-term Performance of Landfill Covers in the northern Mojave Desert

    SciTech Connect (OSTI)

    David Shafer; Michael Young; Stephen Zitzer; Eric McDonald; Todd Caldwell

    2004-05-12

    Evapotransiration (ET) covers have gained widespread acceptance as a closure feature for waste disposal sites, particularly in the arid and semi-arid regions of the southwestern U.S. But as landforms, ET covers are subject to change over time because of processes such as pedogenesis, hydrologic processes, vegetation establishment and change, and biological processes. To better understand the effects of coupled process changes to ET covers, a series of four primary analog sites in Yucca Flat on the Nevada Test Site, along with measurements and observations from other locations in the Mojave Desert, were selected to evaluate changes in ET covers over time. The analog sites, of varying ages, were selected to address changes in the early post-institutional control period, the 1,000-year compliance period for disposal of low-level and mixed low-level waste, and the 10,000-year compliance period for transuranic waste sites.

  2. Long-term impacts of aerosols on the vertical development of...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Long-term impacts of aerosols on the vertical development of clouds and precipitation Citation Details In-Document Search Title: Long-term impacts of aerosols on ...

  3. Long-term management of high-level radioactive waste (HLW) and...

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

    Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) ...

  4. MODELING OF LONG-TERM FATE OF MOBILIZED FINES DUE TO DAM-EMBANKMENT...

    Office of Scientific and Technical Information (OSTI)

    Conference: MODELING OF LONG-TERM FATE OF MOBILIZED FINES DUE TO DAM-EMBANKMENT INTERFACIAL DISLOCATIONS Citation Details In-Document Search Title: MODELING OF LONG-TERM FATE OF ...

  5. Delamination Failures in Long-Term Field Aged PV Modules from...

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

    Delamination Failures in Long-Term Field Aged PV Modules from Point of View of Encapsulant Delamination Failures in Long-Term Field Aged PV Modules from Point of View of ...

  6. Building America Case Study: Long-Term Monitoring of Mini-Split...

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

    Long-Term Monitoring of Mini-Split Ductless Heat Pumps in the Northeast Devens and ... (BSC) evaluated the long-term performance of MSHPs in 8 homes during a period of 3 years. ...

  7. Missouri Entices With Rebates, Lends for the Long-Term | Department...

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

    Missouri Entices With Rebates, Lends for the Long-Term Missouri Entices With Rebates, Lends for the Long-Term When the Missouri Agricultural Energy Savings Team-A Revolutionary ...

  8. Complete Fiber/Copper Cable Solution for Long-Term Temperature...

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

    Complete FiberCopper Cable Solution for Long-Term Temperature and Pressure Measurement in Supercritical Reservoirs and EGS Wells Complete FiberCopper Cable Solution for Long-Term ...

  9. The economics of long-term global climate change

    SciTech Connect (OSTI)

    Not Available

    1990-09-01

    This report is intended to provide an overview of economic issues and research relevant to possible, long-term global climate change. It is primarily a critical survey, not a statement of Administration or Department policy. This report should serve to indicate that economic analysis of global change is in its infancy few assertions about costs or benefits can be made with confidence. The state of the literature precludes any attempt to produce anything like a comprehensive benefit-cost analysis. Moreover, almost all the quantitative estimates regarding physical and economic effects in this report, as well as many of the qualitative assertions, are controversial. Section I provides background on greenhouse gas emissions and their likely climatic effects and on available policy instruments. Section II considers the costs of living with global change, assuming no substantial efforts to reduce greenhouse gas emissions. Section III considers costs of reducing these emissions, though the available literature does not contain estimates of the costs of policies that would, on the assumptions of current climate models, prevent climate change altogether. The individual sections are not entirely compartmentalized, but can be read independently if necessary.

  10. LONG-TERM PERIODICITY VARIATIONS OF THE SOLAR RADIUS

    SciTech Connect (OSTI)

    Qu, Z. N.; Xie, J. L.

    2013-01-01

    In order to study the long-term periodicity variations of the solar radius, daily solar radius data from 1978 February to 2000 September at the Calern Observatory are used. Continuous observations of the solar radius are difficult due to the weather, seasonal effects, and instrument characteristics. Thus, to analyze these data, we first use the Dixon criterion to reject suspect values, then we measure the cross-correlation between the solar radius and sunspot numbers. The result indicates that the solar radius is in complete antiphase with the sunspot numbers and shows lead times of 74 months relative to the sunspot numbers. The Lomb-Scargle and date compensated discrete Fourier transform methods are also used to investigate the periodicity of the solar radius. Both methods yield similar significance periodicities around {approx}1 yr, {approx}2.6 yr, {approx}3.6 yr, and {approx}11 yr. Possible mechanisms for these periods are discussed. The possible physical cause of the {approx}11 yr period is the cyclic variation of the magnetic pressure of the concentrated flux tubes at the bottom of the solar convection zone.

  11. Long-term proliferation and safeguards issues in future technologies

    SciTech Connect (OSTI)

    Keisch, B.; Auerbach, C.; Fainberg, A.; Fiarman, S.; Fishbone, L.G.; Higinbotham, W.A.; Lemley, J.R.; O'Brien, J.

    1986-02-01

    The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for which safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification.

  12. Global recycling services for short and long term risk reduction

    SciTech Connect (OSTI)

    Arslan, M.; Grygiel, J.M.; Drevon, C.; Lelievre, F.; Lesage, M.; Vincent, O.

    2013-07-01

    New schemes are being developed by AREVA in order to provide global solutions for safe and non-proliferating management of used fuels, thereby significantly contributing to overall risks reduction and sustainable nuclear development. Utilities are thereby provided with a service through which they will be able to send their used fuels and only get returned vitrified and compacted waste, the only waste remaining after reprocessing. This waste is stable, standard and has demonstrated capability for very long term interim storage. They are provided as well with associated facilities and all necessary services for storage in a demonstrated safely manner. Recycled fuels, in particular MOX, would be used either in existing LWRs or in a very limited number of full MOX reactors (like the EPR reactor), located in selected countries, that will recycle MOX so as to downgrade the isotopic quality of the Pu inventories in a significant manner. Reprocessed uranium also can be recycled. These schemes, on top of offering demonstrated operational advantages and a responsible approach, result into optimized economics for all shareholders of the scheme, as part of reactor financing (under Opex or Capex form) will be secured thanks to the value of the recycled flows. It also increases fuel cost predictability as recycled fuel is not subject to market fluctuations as much and allows, in a limited span of time, for clear risk mitigation. (authors)

  13. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 333: U-3auS DISPOSAL SITE, NEVADA TEST SITE, NEVADA FOR THE PERIOD JULY 2005-JUNE 2006

    SciTech Connect (OSTI)

    2006-08-01

    Corrective Action Unit (CAU) 333, U-3auS Disposal Site, is a closed construction landfill located in Area 3 of the Nevada Test Site (NTS). The closure of this site was approved by the Nevada Division of Environmental Protection (NDEP) in a letter to the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV) dated June 27, 2001. Post-closure requirements are described in a letter from NNSA/NV to NDEP dated October 9, 2001, and were approved by the NDEP in a letter dated November 5, 2001. This report covers the period July 2005 through June 2006 and consists of copies of the inspection checklist and field notes, repair records (if any), photographs, and recommendations and conclusions.

  14. Recent progress in siting low-level waste disposal facilities in the Southwestern Compact and the Central Interstate Compact

    SciTech Connect (OSTI)

    DeOld, J.H.; Shaffner, J.A.

    1995-11-01

    US Ecology is the private contractor selected to develop and operate low-level waste disposal facilities in the Southwestern and the Central Interstate Compacts. These initiatives have been proceeding for almost a decade in somewhat different regulatory and political climates. This paper chronicles recent events in both projects. In both cases there is reason for continued optimism that low-level waste facilities to serve the needs of waste generators in these two compacts will soon be a reality. When the California Department of Health Services issued a license for the proposed Ward Valley LLRW disposal facility on September 16, 1993, it represented a significant step in implementation of a new generation of regional LLRW disposal facilities. While limited scope land transfer hearings were on the horizon, project beneficiaries were confident that the disposal site would be operational by 1995. Since then, however, political initiatives championed by Senator Barbara Boxer (D-CA) have clouded the federal land transfer process and left the commencement date of operations indeterminant. Since 1993, the biomedical community, waste generators most affected by delays, have been petitioning the current administration to emphasize the need for a timely solution. These efforts are aimed at Clinton administration officials responsible for current delays, who apparently have not recognized the importance of the Ward Valley facility to California`s economy, nor the national ramifications of their delaying actions. The current status of challenges to the Ward Valley license and California Environmental Quality Act (CEQA) documentation is also provided. The presentation also discusses the recently completed National Academy of Science evaluation of reports critical of the Ward Valley development process.

  15. Is Current Hydrogeologic Research Addressing Long-TermPredictions...

    Office of Scientific and Technical Information (OSTI)

    and BiosciencesDivision Country of Publication: United States Language: English Subject: 58 GEOSCIENCES; EDUCATION; FORECASTING; SIMULATION; SITE CHARACTERIZATION; TESTING

  16. Portsmouth Waste Disposal | Department of Energy

    Office of Environmental Management (EM)

    Environmental Cleanup Portsmouth Waste Disposal Portsmouth Waste Disposal Preliminary design cross section of Planned On-site Disposal Cell Preliminary design cross section of ...

  17. Movement of tagged dredged sand at thalweg disposal sites in the Upper Mississippi River. Volume 3. Additional results at Gordon's Ferry and Whitney Island sites

    SciTech Connect (OSTI)

    McCown, D.L.; Paddock, R.A.

    1985-04-01

    During routine channel maintenance, hydraulically dredged sand was tagged with sand coated with fluorescent dye before being deposited as a pile in the thalweg at three sites on the Upper Mississippi River. As discussed in the first two volumes of this report, bathymetry was measured and surface sediments were sampled to study changes in the topography of the disposal pile and the downstream movement of the tagged sand. At all three sites, topographic evidence of the pile disappeared after the first period of high river flow, which was followed by redevelopment of dunes in the disposal area. The tagged sand did not migrate into nearby border areas, backwaters, or sloughs, remaining in the main channel as it moved downstream. This volume presents the results of additional surveys at the Gordon's Ferry and Whitney Island sites. At Gordon's Ferry, 25 bottom cores were taken to examine the three-dimensional distribution of tagged sand in the bottom sediments. The core analyses indicated that much of the tagged sand had been incorporated into the dune structure and that it resided primarily in the crests of the dunes.

  18. Alternative Site Technology Deployment-Monitoring System for the U-3ax/bl Disposal Unit at the Nevada Test Site

    SciTech Connect (OSTI)

    Dixon, J.M.; Levitt, D.G.; Rawlinson, S.E.

    2001-02-01

    In December 2000, a performance monitoring facility was constructed adjacent to the U-3ax/bl mixed waste disposal unit at the Nevada Test Site (NTS). Recent studies conducted in the arid southwestern United States suggest that a vegetated monolayer evapotranspiration (ET) closure cover may be more effective at isolating waste than traditional Resource Conservation and Recovery Act (RCRA) multi-layered designs. The monitoring system deployed next to the U-3ax/bl disposal unit consists of eight drainage lysimeters with three surface treatments: two are left bare; two are revegetated with native species; two are being allowed to revegetate with invader species; and two are reserved for future studies. Soil used in each lysimeter is native alluvium taken from the same location as the soil used for the cover material on U-3ax/bl. The lysimeters were constructed so that any drainage to the bottom can be collected and measured. To provide a detailed evaluation of the cover performance, an ar ray of 16 sensors was installed in each lysimeter to measure soil water content, soil water potential, and soil temperature. Revegetation of the U-3ax/bl closure cover establishes a stable plant community that maximizes water loss through transpiration while at the same time, reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment.

  19. Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites

    SciTech Connect (OSTI)

    A. Jeff Sondrup; Annette L. Schafter

    2010-09-01

    Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratorys proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts are required to meet the Department of Energys Low-Level Waste requirements (DOE-O 435.1), its natural phenomena hazards assessment criteria (DOE-STD-1023-95), and the Radioactive Waste Management Manual (DOE M 435.1-1) guidance in addition to being required by the National Environmental Policy Act (NEPA) environmental assessment (EA). Potential sources of water evaluated include those arising from (1) local precipitation events, (2) precipitation events occurring off of the INL (off-site precipitation), and (3) increased flows in the Big Lost River in the event of a Mackay Dam failure. On-site precipitation events include potential snow-melt and rainfall. Extreme rainfall events were evaluated for the potential to create local erosion, particularly of the barrier placed over the disposal facility. Off-site precipitation carried onto the INL by the Big Lost River channel was evaluated for overland migration of water away from the river channel. Off-site precipitation sources evaluated were those occurring in the drainage basin above Mackay Reservoir. In the worst-case scenarios, precipitation occurring above Mackay Dam could exceed the dams capacity, leading to overtopping, and eventually complete dam failure. Mackay Dam could also fail during a seismic event or as a result of mechanical piping. Some of the water released during dam failure, and contributing precipitation, has the potential of being carried onto the INL in the Big Lost River channel. Resulting overland flows from these flood sources were evaluated for their erosion potential, ability to overflow the proposed disposal facility, and for their ability to increase migration of contaminants from the facility. The assessment of available literature suggests that the likelihood of detrimental flood water impacting the proposed RH-LLW facility is extremely low. The annual exceedance probability associated with uncontrolled flows in the Big Lost River impacting either of the proposed sites is 1x10-5, with return interval (RI) of 10,000yrs. The most probable dam failure scenario has an annual exceedance probability of 6.3x10-6 (1.6x105 yr RI). In any of the scenarios generating possible on-site water, the duration is expected to be quite short, water depths are not expected to exceed 0.5 m, and the erosion potential can easily be mitigated by emplacement of a berm (operational period), and an engineered cover (post closure period). Subsurface mobilization of radionuclides was evaluated for a very conservative flooding scenario resulting in 50 cm deep, 30.5 day on-site water. The annual exceedance probability for which is much smaller than 3.6x10-7 (2.8x106 yr RI). For the purposes of illustration, the facility was assumed to flood every 500 years. The periodically recurring flood waters were predicted to marginally increase peak radionuclide fluxes into the aquifer by at most by a factor of three for non-sorbing radionuclides, and to have limited impact on peak radionuclide fluxes into the aquifer for contaminants that do sorb.

  20. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2016 - QUARTER ONE

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

    ONE DISPOSAL VOLUME REPORT DOE/NV/25946--2729 FY16 - Quarter 1 FY16 Cumulative FY16 - Quarter 1 FY16 Cumulative DOE APPROVED Waste Volume Volume DOE APPROVED Waste Volume Volume GENERATORS Type (Ft 3 ) (Ft 3 ) GENERATORS Type (Ft 3 ) (Ft 3 ) ABERDEEN PROVING GROUNDS (MD) LLW 1,122 1,122 NATIONAL SECURITY TECHNOLOGIES (NV) LLW 173 173 LLW 810 810 MIXED 6,447 6,447 CONSOLIDATED NUCLEAR SECURITY, LLC / Y-12 (TN) LLW 23,066 23,066 OAK RIDGE RESERVATION / UCOR (TN) LLW 12,681 12,681 DURATEK / ENERGY

  1. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2016 - QUARTER TWO

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

    TWO DISPOSAL VOLUME REPORT DOE/NV/25946--2779 FY16 - Quarter 2 FY16 Cumulative FY16 - Quarter 2 FY16 Cumulative DOE APPROVED Waste Volume Volume DOE APPROVED Waste Volume Volume GENERATORS Type (Ft 3 ) (Ft 3 ) GENERATORS Type (Ft 3 ) (Ft 3 ) ABERDEEN PROVING GROUNDS (MD) LLW 0 1,122 LLW 604 776 LLW 7,328 8,138 CNR 2,560 2,560 MIXED 6,344 12,791 CNRH 328 328 ARGONNE NATIONAL LAB (IL) LLW 1,063 1,063 NAVARRO (NV) LLW 224 224 BATTELLE ENERGY ALLIANCE (ID) LLW 8,465 8,465 NUCLEAR FUEL SERVICES (TN)

  2. Long-Term Surveillance and Maintenance at Rocky Flats: Early Experiences and Lessons Learned

    SciTech Connect (OSTI)

    Surovchak, S.; Kaiser, L.; DiSalvo, R.; Boylan, J.; Squibb, G.; Nelson, J.; Darr, B.; Hanson, M.

    2008-07-01

    The U.S. Department of Energy's (DOE's) Rocky Flats Site was established in 1951 as part of the United States' nationwide nuclear weapons complex to manufacture nuclear weapons components. In 1992 weapons production halted, and the Rocky Flats mission changed to include environmental investigations, cleanup, and site closure. In October 2005, DOE and its contractor completed an accelerated 10-year, $7 billion cleanup of chemical and radiological contamination left from nearly 50 years of production. The cleanup required the decommissioning, decontamination, demolition, and removal of more than 800 structures; removal of more than 500,000 cubic meters of low-level radioactive waste; and remediation of more than 360 potentially contaminated environmental sites. The final remedy for the site was selected in September 2006 and included institutional controls, physical controls, and continued monitoring for the former industrial portion of the site. The remainder of the site, which served as a buffer zone surrounding the former industrial area, was transferred to the U.S. Fish and Wildlife Service in July 2007 for a national wildlife refuge. DOE's Office of Legacy Management is responsible for the long-term surveillance and maintenance of Rocky Flats, which includes remedy implementation activities and general site maintenance. Several factors have complicated the transition from closure to post-closure at Rocky Flats. The early experiences associated with the two years since the physical cleanup and closure work were completed have led to several valuable lessons learned. (authors)

  3. CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY

    SciTech Connect (OSTI)

    Jordan, J.; Flach, G.

    2012-03-29

    As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

  4. 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

    2003-06-01

    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.

  5. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2014 - Qtr 2

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

    2 DISPOSAL VOLUME REPORT Run Date and Time: 4/1/2014 8:57 AM DOE APPROVED Disposal Volume Volume Volume Volume Volume Volume GENERATORS Location (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 1,226.65 34.73 3,353.72 94.97 92,888 2,630 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0.00 159,977 4,530 Area 5 6,359.61 180.08 110,139.17 3,118.79 1,150,051 32,566 Mixed 0.00 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 0 0

  6. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2014 - Qtr3

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

    Qtr3 DISPOSAL VOLUME REPORT Run Date and Time: 7/7/2014 7:33 AM DOE APPROVED Disposal Volume Volume Volume Volume Volume Volume GENERATORS Location (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 5,253.37 148.76 94,787 2,684 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0.00 159,977 4,530 Area 5 1,702.17 48.20 151,483.69 4,289.54 1,191,395 33,737 Mixed 0.00 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 0 0

  7. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2014 - Qtr4

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

    Qtr4 DISPOSAL VOLUME REPORT Run Date and Time: 10/22/2014 5:53 AM DOE APPROVED Disposal Volume Volume Volume Volume Volume Volume GENERATORS Location (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 8,799.98 249.19 98,334 2,785 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0.00 159,977 4,530 Area 5 0.00 0.00 175,346.52 4,965.26 1,215,258 34,412 Mixed 0.00 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 0 0 Mixed

  8. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2015 - Qtr 1

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

    1 DISPOSAL VOLUME REPORT Run Date and Time: 1/20/2015 7:59 AM DOE APPROVED Disposal Volume Volume Volume Volume Volume Volume GENERATORS Location (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 98,334 2,785 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0.00 159,977 4,530 Area 5 0.00 0.00 22,116.86 626.28 1,237,375 35,039 Mixed 0.00 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 0 0 Mixed 0.00 0.00

  9. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2015 - Qtr 2

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

    2 DISPOSAL VOLUME REPORT DOE APPROVED Disposal Volume Volume Volume Volume Volume Volume GENERATORS Location (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 1,204.55 34.11 99,539 2,819 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0.00 159,977 4,530 Area 5 1,014.59 28.73 72,977.39 2,066.49 1,288,235 36,479 Mixed 0.00 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0.00 0 0 Mixed 0.00 0.00 0.00 0.00 0 0 Area 3 0.00

  10. Preliminary identification of potentially disruptive scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site

    SciTech Connect (OSTI)

    Guzowski, R.V.; Newman, G.

    1993-12-01

    The Greater Confinement Disposal location is being evaluated to determine whether defense-generated transuranic waste buried at this location complies with the Containment Requirements established by the US Environmental Protection Agency. One step in determining compliance is to identify those combinations of events and processes (scenarios) that define possible future states of the disposal system for which performance assessments must be performed. An established scenario-development procedure was used to identify a comprehensive set of mutually exclusive scenarios. To assure completeness, 761 features, events, processes, and other listings (FEPS) were compiled from 11 references. This number was reduced to 205 primarily through the elimination of duplications. The 205 FEPs were screened based on site-specific, goal-specific, and regulatory criteria. Four events survived screening and were used in preliminary scenario development: (1) exploratory drilling penetrates a GCD borehole, (2) drilling of a withdrawal/injection well penetrates a GCD borehole, (3) subsidence occurs at the RWMS, and (4) irrigation occurs at the RWMS. A logic diagram was used to develop 16 scenarios from the four events. No screening of these scenarios was attempted at this time. Additional screening of the currently retained events and processes will be based on additional data and information from site-characterization activities. When screening of the events and processes is completed, a final set of scenarios will be developed and screened based on consequence and probability of occurrence.

  11. COMPOSITE ANALYSIS OF LLW DISPOSAL FACILITIES AT THE U.S. DEPARTMENT OF ENERGY'S SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Hiergesell, R; Mark Phifer, M; Frank02 Smith, F

    2009-01-08

    Composite Analyses (CA's) are required per DOE Order 435.1 [1], in order to provide a reasonable expectation that DOE low-level waste (LLW) disposal, high-level waste tank closure, and transuranic (TRU) waste disposal in combination with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), Resource Conservation and Recovery Act (RCRA), and deactivation and decommissioning (D&D) actions, will not result in the need for future remedial actions in order to ensure radiological protection of the public and environment. This Order requires that an accounting of all sources of DOE man-made radionuclides and DOE enhanced natural radionuclides that are projected to remain on the site after all DOE site operations have ceased. This CA updates the previous CA that was developed in 1997. As part of this CA, an inventory of expected radionuclide residuals was conducted, exposure pathways were screened and a model was developed such that a dose to the MOP at the selected points of exposure might be evaluated.

  12. Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling

    SciTech Connect (OSTI)

    Phifer, Mark A.; Smith, Frank G. III

    2013-06-21

    A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

  13. Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah...

    Office of Environmental Management (EM)

    of the existing RCRA Subtitle D landfill, (2) site considerations such as seismic and brown versus green field, (3) the public communication plan, (4) future public use options,...

  14. Geological aspects of the nuclear waste disposal problem

    SciTech Connect (OSTI)

    Laverov, N.P.; Omelianenko, B.L.; Velichkin, V.I.

    1994-06-01

    For the successful solution of the high-level waste (HLW) problem in Russia one must take into account such factors as the existence of the great volume of accumulated HLW, the large size and variety of geological conditions in the country, and the difficult economic conditions. The most efficient method of HLW disposal consists in the maximum use of protective capacities of the geological environment and in using inexpensive natural minerals for engineered barrier construction. In this paper, the principal trends of geological investigation directed toward the solution of HLW disposal are considered. One urgent practical aim is the selection of sites in deep wells in regions where the HLW is now held in temporary storage. The aim of long-term investigations into HLW disposal is to evaluate geological prerequisites for regional HLW repositories.

  15. Long-Term Stewardship of Mixed Wastes: Passive Reactive Barriers...

    Office of Scientific and Technical Information (OSTI)

    of Energy sites using a group of common soil bacteria of the genus Cellulomonas. ... Sponsoring Org: USDOE - Office of Science (SC) Country of Publication: United States ...

  16. Is Current Hydrogeologic Research Addressing Long-TermPredictions...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 58 GEOSCIENCES; EDUCATION; FORECASTING; SIMULATION; SITE CHARACTERIZATION; TESTING Word Cloud More Like This Full ...

  17. Record of Decision - ROD - Long-Term Regional Dialogue - July...

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

    and Conservation Council CSE Customer Service Engineers CY Calendar Year DOE Richland United States Department of Energy, Hanford, Washington site DSIs Direct-Service...

  18. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2015 - QUARTER FOUR

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

    QUARTER FOUR DISPOSAL VOLUME REPORT FY15 - Quarter 4 FY15 Cumulative FY15 - Quarter 4 FY15 Cumulative DOE APPROVED Waste Volume Volume DOE APPROVED Waste Volume Volume GENERATORS Type (Ft 3 ) (Ft 3 ) GENERATORS Type (Ft 3 ) (Ft 3 ) ABERDEEN PROVING GROUNDS (MD)LLW 4,926 7,642 LLW 111 1,491 LLW 6,430 27,485 MIXED 19 347 MIXED 16,197 76,337 CNR 1,383 2,870 ARGONNE NATIONAL LAB (IL) LLW 0 3,346 CNRH 493 821 LLW 14,761 27,732 NAVARRO LLW 16 7,837 CNR 1,271 3,814 BROOKHAVEN NATIONAL LAB (NY) LLW

  19. 1998 report on Hanford Site land disposal restrictions for mixed waste

    SciTech Connect (OSTI)

    Black, D.G.

    1998-04-10

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities stored, generation rates, location and method of storage, an assessment of storage-unit compliance status, storage capacity, and the bases and assumptions used in making the estimates.

  20. Alternative Evaluation Study: Methods to Mitigate/Accommodate Subsidence for the Radioactive Waste Management Sites at the Nevada Test Site, Nye County Nevada, with Special Focus on Disposal Cell U-3ax/bl

    SciTech Connect (OSTI)

    Barker, L.

    1997-09-01

    An Alternative Evaluation Study is a type of systematic approach to problem identification and solution. An Alternative Evaluation Study was convened August 12-15, 1997, for the purpose of making recommendations concerning closure of Disposal Cell U-3ax/bl and other disposal cells and mitigation/accommodation of waste subsidence at the Radioactive Waste Management Sites at the Nevada Test Site. This report includes results of the Alternative Evaluation Study and specific recommendations.

  1. Geophysical methods for fracture characterization in and around potential sites for nuclear waste disposal

    SciTech Connect (OSTI)

    Majer, E.L.; Lee, K.H. ); Morrison, H.F. )

    1992-08-01

    Historically, geophysical methods have been used extensively to successfully explore the subsurface for petroleum, gas, mineral, and geothermal resources. Their application, however, for site characterization, and monitoring the performance of near surface waste sites or repositories has been somewhat limited. Presented here is an overview of the geophysical methods that could contribute to defining the subsurface heterogeneity and extrapolating point measurements at the surface and in boreholes to volumetric descriptions in a fractured rock. In addition to site characterization a significant application of geophysical methods may be in performance assessment and in monitoring the repository to determine if the performance is as expected.

  2. DOE issues Finding of No Significant Impact on Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low Level Radioactive Waste Generated at Idaho Site

    Broader source: Energy.gov [DOE]

    Idaho Falls, ID – After completing a careful assessment, the U.S. Department of Energy has determined that building a new facility at its Idaho National Laboratory site for continued disposal of remote-handled low level radioactive waste generated by operations at the site will not have a significant impact on the environment.

  3. Los Alamos Lab Completes Excavation of Waste Disposal Site Used in the

    Energy Savers [EERE]

    Department of Energy Demolition Work Progresses Toward Goal of Completing Cleanup Los Alamos Demolition Work Progresses Toward Goal of Completing Cleanup January 14, 2016 - 12:20pm Addthis The sewage treatment facility before demolition. The sewage treatment facility before demolition. Debris from the sewage treatment facility. Debris from the sewage treatment facility. Site of the demolished sewage treatment facility. Site of the demolished sewage treatment facility. The sewage treatment

  4. Ancient Lava Flows Trap CO2 for Long-Term Storage in Big Sky Injection

    Broader source: Energy.gov [DOE]

    How can a prehistoric volcanic eruption help us reduce the amount of CO2 released into the atmosphere today? The answer is found in the basalt formations created by the lava – formations that can be used as sites for injecting carbon dioxide (CO2) captured from industrial sources in a process called carbon capture and storage. The Big Sky Carbon Sequestration Partnership recently injected 1,000 metric tons of CO2 into the Grande Ronde Basalt Formation in eastern Washington. This first-of-its kind injection is part of research meant to determine if basalt formations could provide a long-term solution for storing CO2, a potent greenhouse gas.

  5. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect (OSTI)

    Cook, J.R.; Hunt, P.D.

    1994-04-15

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

  6. Impact of a coastal disposal site for inert wastes on the physical marine environment, Barcola-Bovedo, Trieste, Italy

    SciTech Connect (OSTI)

    Colizza, E.; Fontolan, G.; Brambati, A.

    1996-06-01

    Sediments in the marine area surrounding the Barcola-Bovedo coastal disposal site for inert wastes show a textural adjustment as a response to the new morphology due to construction of a 150-m-wide x 350-m-long landfill. Relatively coarse-sized deposits were found along the nearshore area facing the central landfill face, while pelitic sediments transported in suspension settle deeper, mainly in the northwestern sector of the study area, according to the cyclonic circulation scheme. Geochemical comparison between disposed material and sea-bottom sediments, normalized taking in account the regional variability of the element contents, shows: (1) Cr concentrations in the coastal samples twice as high as in the offshore ones, with the former characterizing the whole coastal and port area of Trieste, and (2) {open_quotes}anomalous{close_quotes} enrichments of Zn, Cu, and Pb, located mainly in the southern stretch of the investigated area, where dumping work is in progress in order to connect the landfill with the port area. Although the new morphology of the sea bottom is reflected in the grain-size redistribution, the sediments were not altered as far as their geochemical properieties are concerned. In contrast, the recent discharge of material in the southern area is easily discernible because of its high heavy-metal content. 30 refs., 10 figs., 6 tabs.

  7. NEVADA NATIONAL SECURITY SITE WASTE DISPOSAL OPERATIONS FY 2015 - Qtr 3

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

    3 DISPOSAL VOLUME REPORT Volume Volume Volume Volume Volume Volume (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) (Ft 3 ) (M 3 ) Area 3 0.00 0.00 0.00 0.00 0 0 Area 5 2,141.45 60.64 3,346.01 94.75 101,680 2,879 Mixed 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 159,977 4,530 Area 5 25,981.00 735.70 98,958.39 2,802.19 1,314,216 37,214 Mixed 0.00 0.00 0.00 3,940 112 Area 3 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 0 0 Mixed 0.00 0.00 0.00 0 0 Area 3 0.00 0.00 0.00 0 0 Area 5 0.00 0.00 0.00 96,558 2,734 Mixed 0.00 0.00

  8. Low level tank waste disposal study

    SciTech Connect (OSTI)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  9. Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0

    SciTech Connect (OSTI)

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

    2004-05-03

    The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

  10. Modeling long-term CO2 storage, sequestration and cycling

    SciTech Connect (OSTI)

    Bacon, Diana H.

    2013-11-11

    The application of numerical and analytical models to the problem of storage, sequestration and migration of carbon dioxide in geologic formations is discussed. A review of numerical and analytical models that have been applied to CO2 sequestration are presented, as well as a description of frameworks for risk analysis. Application of models to various issues related to carbon sequestration are discussed, including trapping mechanisms, density convection mixing, impurities in the CO2 stream, changes in formation porosity and permeability, the risk of vertical leakage, and the impacts on groundwater resources if leakage does occur. A discussion of the development and application of site-specific models first addresses the estimation of model parameters and the use of natural analogues to inform the development of CO2 sequestration models, and then surveys modeling that has been done at two commercial-scale CO2 sequestration sites, Sleipner and In Salah, along with a pilot-scale injection sites used to study CO2 sequestration in saline aquifers (Frio) and an experimental site designed to test monitoring of CO2 leakage in the vadose zone (ZERT Release Facility).

  11. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect (OSTI)

    D. Wieland, V. Yucel, L. Desotell, G. Shott, J. Wrapp

    2008-04-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators.

  12. LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT OF

    Office of Scientific and Technical Information (OSTI)

    RADIONUCLIDES IN A SEMI-ARID VADOSE ZONE (Technical Report) | SciTech Connect LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT OF RADIONUCLIDES IN A SEMI-ARID VADOSE ZONE Citation Details In-Document Search Title: LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT OF RADIONUCLIDES IN A SEMI-ARID VADOSE ZONE The main purpose of this project was to improve the fundamental mechanistic understanding and quantification of long-term colloid mobilization and

  13. Long-Term Biological Monitoring of an Impaired Stream: Implications for

    Office of Scientific and Technical Information (OSTI)

    Environmental Management [Special Issue] (Journal Article) | SciTech Connect Long-Term Biological Monitoring of an Impaired Stream: Implications for Environmental Management [Special Issue] Citation Details In-Document Search Title: Long-Term Biological Monitoring of an Impaired Stream: Implications for Environmental Management [Special Issue] The long-term ecological recovery of an impaired stream in response to an industrial facility's pollution abatement actions and the implications of

  14. Long-term measurements of submicrometer aerosol chemistry at the Southern

    Office of Scientific and Technical Information (OSTI)

    Great Plains (SGP) using an Aerosol Chemical Speciation Monitor (ACSM) (Journal Article) | SciTech Connect Long-term measurements of submicrometer aerosol chemistry at the Southern Great Plains (SGP) using an Aerosol Chemical Speciation Monitor (ACSM) Citation Details In-Document Search Title: Long-term measurements of submicrometer aerosol chemistry at the Southern Great Plains (SGP) using an Aerosol Chemical Speciation Monitor (ACSM) In this study the long-term trends of non-refractory

  15. Using Social Media for Long-Term Branding | Department of Energy

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

    Social Media for Long-Term Branding Using Social Media for Long-Term Branding Better Buildings Residential Network Marketing and Outreach Peer Exchange Call Series: Using Social Media for Long-Term Branding, Call Slides and Discussion Summary, February 27, 2014. PDF icon Call Slides and Discussion Summary More Documents & Publications Effective Strategies for Participating in Utility Planning Marketing & Driving Demand Collaborative - Social Media Tools & Strategies Leveraging

  16. Algal Biofuels: Long-Term Energy Benefits Drive U.S. Research | Department

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

    of Energy Biofuels: Long-Term Energy Benefits Drive U.S. Research Algal Biofuels: Long-Term Energy Benefits Drive U.S. Research Algal Biofuels: Long-Term Energy Benefits Drive U.S. Research PDF icon algal_biofuels_factsheet.pdf More Documents & Publications 2015 Peer Review Presentations-Algal Feedstocks Algae Biofuels Technology Bioenergy Technologies Office Fiscal Year 2014 Annual Report

  17. Microsoft PowerPoint - DETL_long_term_inverter_testing_wcomments.ppt

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

    Administration under contract DE-AC04-94AL85000. LONG-TERM INVERTER OPERATION DEMONSTRATION SANDIA NATIONAL LABORATORIES Department 6335 Solar Systems Sigifredo Gonzalez, Scott Kuszmaul, Abraham Ellis 34th IEEE PV Specialists Conference Philadelphia, PA 12 June, 2009 LONG-TERM INVERTER OPERATION RE-CHARACTERIZATION REQUIREMENTS Purpose Analyze the effects of long term operation and exposure on the performance of the utility interconnected PV inverter Parameters Identify the influential

  18. Summary Final Long-Term Management and Storage of Elemental Mercury Supplemental Environmental Impact Statement

    Office of Environmental Management (EM)

    Environmental Impact Statement Final LONG-TERM MANAGEMENT AND STORAGE OF ELEMENTAL MERCURY Final Supplemental Environmental Impact Statement LONG-TERM MANAGEMENT AND STORAGE OF ELEMENTAL MERCURY DOE/EIS-0423-S1 September 2013 SUMMARY AND GUIDE FOR STAKEHOLDERS U.S. Department of Energy Office of Environmental Management Washington, DC AVAILABILITY OF THIS FINAL LONG-TERM MANAGEMENT AND STORAGE OF ELEMENTAL MERCURY SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT For additional information on this

  19. Evaluation of proposed designs for streamflow monitoring structures at waste disposal sites

    SciTech Connect (OSTI)

    Clapp, R.B.; Borders, D.M.; Tardiff, M.F.; Huff, D.D.

    1991-01-01

    Design of small surface water monitoring stations associated with waste sites requires an approach that balances several problems. The monitoring site must have a capacity for a wide range of flows, allow accurate measurements over the full performance range, minimize effects from accumulation of contaminated sediments, and minimize costs of construction and operation. Selecting a station design that takes these factors into consideration can be done systematically through use of formal decision analysis. The paper discusses the effectiveness of various hydraulic structures as flumes and weirs to monitor stream flow and drainage. The process has produced the most viable alternative designs and yielded fully documented guidelines for designing new stations as they are needed. 7 refs., 6 figs., 3 tabs.

  20. Impacts of Long-term Drought on Power Systems in the U.S. Southwest...

    Energy Savers [EERE]

    ... Long-Term Reliability Assessment, North American Electric Reliability Corporation, Atlanta GA (www.nerc.com,) November 2011. NERC 2012, Summer Reliability Assessment 20102, North ...

  1. Long-Term Demonstration of Hydrogen Production from Coal at Elevated...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Long-Term Demonstration of Hydrogen Production from Coal at Elevated Temperatures Year 6 - Activity 1.12 - Development of a National Center for Hydrogen ...

  2. Using Social Media for Long-Term Branding | Department of Energy

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

    Using Social Media for Long-Term Branding Better Buildings Residential Network Marketing ... Effective Strategies for Participating in Utility Planning Marketing & Driving Demand ...

  3. Finding Long-Term Solutions for Nuclear Waste | Department of Energy

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

    Long-Term Solutions for Nuclear Waste Finding Long-Term Solutions for Nuclear Waste December 21, 2015 - 1:00pm Addthis The Department of Energy is working toward long-term solutions for nuclear waste storage. | Photo by <a href="https://www.flickr.com/photos/mandj98/">James Marvin Phelps</a>. The Department of Energy is working toward long-term solutions for nuclear waste storage. | Photo by James Marvin Phelps. Franklin (Lynn) Orr Franklin (Lynn) Orr Under Secretary for

  4. Over 150 years of long-term fertilization alters spatial scaling...

    Office of Scientific and Technical Information (OSTI)

    Prev Next Title: Over 150 years of long-term fertilization alters spatial scaling of microbial biodiversity You are accessing a document from the Department of Energy's...

  5. Design of the Long-term Waste Management Facility for Historic LLRW Port Hope Project - 13322

    SciTech Connect (OSTI)

    Campbell, Don; Barton, David; Case, Glenn

    2013-07-01

    The Municipality of Port Hope is located on the northern shores of Lake Ontario approximately 100 km east of Toronto, Ontario, Canada. Starting in the 1930's, radium and later uranium processing by Eldorado Gold Mines Limited (subsequently Eldorado Nuclear Limited) (Eldorado) at their refinery in Port Hope resulted in the generation of process residues and wastes that were disposed of indiscriminately throughout the Municipality until about the mid-1950's. These process residues contained radium (Ra- 226), uranium, arsenic and other contaminants. Between 1944 and 1988, Eldorado was a Federal Crown Corporation, and as such, the Canadian Federal Government has assumed responsibility for the clean-up and long-term management of the historic waste produced by Eldorado during this period. The Port Hope Project involves the construction and development of a new long-term waste management facility (LTWMF), and the remediation and transfer of the historic wastes located within the Municipality of Port Hope to the new LTWMF. The new LTWMF will consist of an engineered above-ground containment mound designed to contain and isolate the wastes from the surrounding environment for the next several hundred years. The design of the engineered containment mound consists of a primary and secondary composite base liner system and composite final cover system, made up of both natural materials (e.g., compacted clay, granular materials) and synthetic materials (e.g., geo-synthetic clay liner, geo-membrane, geo-textiles). The engineered containment mound will cover an area of approximately 13 hectares and will contain the estimated 1.2 million cubic metres of waste that will be generated from the remedial activities within Port Hope. The LTWMF will also include infrastructure and support facilities such as access roads, administrative offices, laboratory, equipment and personnel decontamination facilities, waste water treatment plant and other ancillary facilities. Preliminary construction activities for the Port Hope LTWMF commenced in 2012 and are scheduled to continue over the next few years. The first cell of the engineered containment mound is scheduled to be constructed in 2015 with waste placement into the Port Hope LTWMF anticipated over the following seven year period. (authors)

  6. Transition of Long-Term Response Action Management Requirements

    Office of Environmental Management (EM)

    Facility | Department of Energy Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility October 30, 2014 - 12:00pm Addthis Savannah River Remediation (SRR) Salt Waste Processing Facility (SWPF) Integration Manager Keith Harp (front right) points to the spot where the Savannah River Site’s liquid waste facilities transfer lines will connect to lines from the SWPF, which

  7. DOE - Office of Legacy Management -- Cheney Disposal Cell - 008

    Office of Legacy Management (LM)

    Cheney Disposal Cell - 008 FUSRAP Considered Sites Site: Cheney Disposal Cell (008) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: ...

  8. DOE - Office of Legacy Management -- Clive Disposal Cell - 036

    Office of Legacy Management (LM)

    Clive Disposal Cell - 036 FUSRAP Considered Sites Site: Clive Disposal Cell (036 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: ...

  9. DOE - Office of Legacy Management -- Estes Gulch Disposal Cell...

    Office of Legacy Management (LM)

    Estes Gulch Disposal Cell - 010 FUSRAP Considered Sites Site: Estes Gulch Disposal Cell (010) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  10. DOE - Office of Legacy Management -- 11 E (2) Disposal Cell ...

    Office of Legacy Management (LM)

    11 E (2) Disposal Cell - 037 FUSRAP Considered Sites Site: 11 E. (2) Disposal Cell (037) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  11. DOE - Office of Legacy Management -- Burro Canyon Disposal Cell...

    Office of Legacy Management (LM)

    Burro Canyon Disposal Cell - 007 FUSRAP Considered Sites Site: Burro Canyon Disposal Cell (007) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  12. Dispersal Limitations on Fish Community Recovery Following Long-term Water Quality Remediation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    McManamay, Ryan A.; Jett, Robert T.; Ryon, Michael G.; Gregory, Scott M.; Stratton, Sally H.; Peterson, Mark J.

    2016-02-22

    Holistic restoration approaches, such as water quality remediation, are likely to meet conservation objectives because they are typically implemented at watershed scales, as opposed to individual stream reaches. However, habitat fragmentation may impose constraints on the ecological effectiveness of holistic restoration strategies by limiting colonization following remediation. We questioned the importance of dispersal limitations to fish community recovery following long-term water quality remediation and species reintroductions across the White Oak Creek (WOC) watershed near Oak Ridge, Tennessee (USA). Long-term (26 years) responses in fish species richness and biomass to water quality remediation were evaluated in light of habitat fragmentation andmore » population isolation from instream barriers, which varied in their passage potential. In addition, ordination techniques were used to determine the relative importance of habitat connectivity and water quality, in explaining variation fish communities relative to environmental fluctuations, i.e. streamflow. Ecological recovery (changes in richness) at each site was negatively related to barrier index, a measure of community isolation by barriers relative to stream distance. Following species reintroductions, dispersal by fish species was consistently in the downstream direction and upstream passage above barriers was non-existent. The importance of barrier index in explaining variation in fish communities was stronger during higher flow conditions, but decreased over time an indication of increasing community stability and loss of seasonal migrants. Compared to habitat fragmentation, existing water quality concerns (i.e., outfalls, point source discharges) were unrelated to ecological recovery, but explained relatively high variation in community dynamics. Our results suggest that habitat fragmentation limited the ecological effectiveness of intensive water quality remediation efforts and fish reintroduction efforts by impeding recolonization at isolated stream reaches.« less

  13. Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

    SciTech Connect (OSTI)

    Rutqvist, Jonny; Liu, Hui-Hai; Steefel, Carl I.; Serrano de Caro, M. A.; Caporuscio, Florie Andre; Birkholzer, Jens T.; Blink, James A.; Sutton, Mark A.; Xu, Hongwu; Buscheck, Thomas A.; Levy, Schon S.; Tsang, Chin-Fu; Sonnenthal, Eric; Halsey, William G.; Jove-Colon, Carlos F.; Wolery, Thomas J.

    2011-01-01

    Key components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate long-term repository performance. The focus of this report is the following: (1) Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept; (2) Evaluation of key parameters in the characterization of EBS performance; (3) Identification of key knowledge gaps and uncertainties; and (4) Evaluation of tools and modeling approaches for EBS processes and performance. The above topics will be evaluated through the analysis of the following: (1) Overview of EBS concepts for various NW disposal systems; (2) Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments; (3) Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS; and (4) Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

  14. SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Knowledge Advancement.

    SciTech Connect (OSTI)

    Gauntt, Randall O.; Mattie, Patrick D.; Bixler, Nathan E.; Ross, Kyle; Cardoni, Jeffrey N; Kalinich, Donald A.; Osborn, Douglas M.; Sallaberry, Cedric Jean-Marie; Ghosh, S. Tina

    2014-02-01

    This paper describes the knowledge advancements from the uncertainty analysis for the State-of- the-Art Reactor Consequence Analyses (SOARCA) unmitigated long-term station blackout accident scenario at the Peach Bottom Atomic Power Station. This work assessed key MELCOR and MELCOR Accident Consequence Code System, Version 2 (MACCS2) modeling uncertainties in an integrated fashion to quantify the relative importance of each uncertain input on potential accident progression, radiological releases, and off-site consequences. This quantitative uncertainty analysis provides measures of the effects on consequences, of each of the selected uncertain parameters both individually and in interaction with other parameters. The results measure the model response (e.g., variance in the output) to uncertainty in the selected input. Investigation into the important uncertain parameters in turn yields insights into important phenomena for accident progression and off-site consequences. This uncertainty analysis confirmed the known importance of some parameters, such as failure rate of the Safety Relief Valve in accident progression modeling and the dry deposition velocity in off-site consequence modeling. The analysis also revealed some new insights, such as dependent effect of cesium chemical form for different accident progressions. (auth)

  15. Analysis of the technical capabilities of DOE sites for disposal of residuals from the treatment of mixed low-level waste

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.; Langkopf, B.S.; Kuehne, P.B.

    1997-04-01

    The US Department of Energy (DOE) has stored or expects to generate over the next five years more than 130,000 m{sup 3} of mixed low-level waste (MLLW). Before disposal, MLLW is usually treated to comply with the land disposal restrictions of the Resource Conservation and Recovery Act. Depending on the type of treatment, the original volume of MLLW and the radionuclide concentrations in the waste streams may change. These changes must be taken into account in determining the necessary disposal capacity at a site. Treatment may remove the characteristic in some waste that caused it to be classified as mixed. Treatment of some waste may, by reduction of the mass, increase the concentrations of some transuranic radionuclides sufficiently so that it becomes transuranic waste. In this report, the DOE MLLW streams were analyzed to determine after-treatment volumes and radionuclide concentrations. The waste streams were reclassified as residual MLLW or low-level or transuranic waste resulting from treatment. The volume analysis indicated that about 89,000 m{sup 3} of waste will require disposal as residual MLLW. Fifteen DOE sites were then evaluated to determine their capabilities for hosting disposal facilities for some or all of the residual MLLW. Waste streams associated with about 90% of the total residual MLLW volume are likely to present no significant issues for disposal and require little additional analysis. Future studies should focus on the remaining waste streams that are potentially problematic by examining site-specific waste acceptance criteria, alternative treatment processes, alternative waste forms for disposal, and pending changes in regulatory requirements.

  16. Long-term energy generation planning under uncertainty

    SciTech Connect (OSTI)

    Escudero, L.F.; Paradinas, I.; Salmeron, J.; Sanchez, M.

    1998-07-01

    In this work the authors deal with the hydro-thermal coordination problem under uncertainty in generators availability, fuel costs, exogenous water inflow and energy demand. The objective is to minimize the system operating cost. The decision variables are the fuel procurement for each thermal generation site, the energy generated by each thermal and hydro-generator and the release and spilled water from reservoirs. Control variables are the stored water in reservoirs and the stored fuel in thermal plants at the end of each time period. The main contribution on the proposed topic focus in the simultaneous inclusion of the hydro-network and the thermal generation related constraints, as well as the stochastic aspect of the aforementioned parameters. The authors report their computational experience on real problems drawn from the Spanish hydro-thermal generation system. A case tested includes 85 generators (42 thermal plants with a global 27084MW capacity) and 57 reservoirs.

  17. Evaluation of mid-to-long term basic research for environmental restoration: Preliminary analysis to characterize DOE waste problems in a 5- to 20-year timeframe and to identify research needs

    SciTech Connect (OSTI)

    Not Available

    1989-09-01

    This document describes a long-term basic research program for the US Department of Energy (DOE) that complements departmental initiatives in waste management and site cleanup. The most important problems faced by DOE are environmental restoration of waste sites and cleanup of inactive facilities. Environmental restoration is defined in this report as characterization, assessment, remediation, and post-closure verification within the waste/environmental system at DOE sites. Remediation of inactive, contaminated waste-disposal sites is the largest and most expensive task facing DOE. Immobilization, isolation, separation, and destruction of waste, either aboveground or in situ, are difficult and costly tasks. Technologies for these tasks are primitive or do not exist. Departmental problems in the long term are being analyzed scientifically and research needs are being identified. When completed, the Office of Energy Research's (OER's) basis research plan will describe potential scientific research needs for universities, national laboratories, and others as a basis for research proposals to DOE. Extensive interaction with the scientific community is planned to further refine and prioritize research needs. Basic research within DOE is directed toward fundamental knowledge leading to the discovery of new scientific or engineering concepts and principles that may or may not have immediate specific technological applications. However, because DOE is a mission-oriented agency, basic research in DOE is strongly influenced by national energy and environmental policy and may be multidisciplinary in nature. Basic research will provide innovative concepts and the fundamental knowledge base that facilitates the development and application of new and emerging technologies. 41 refs., 5 figs., 9 tabs.

  18. EIS-0356: Retrieval, Treatment and Disposal of Tank Wastes and Closure of Single-Shell Tanks at the Hanford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposed retrieval, treatment, and disposal of the waste being managed in the high-level waste (HLW) tank farms at the Hanford Site near Richland, Washington, and closure of the 149 single-shell tanks (SSTs) and associated facilities in the HLW tank farms.

  19. Ocean-current measurements at the Farallon Islands Low-Level Radioactive Waste Disposal Site, 1977-1978. Includes appendix. Final report

    SciTech Connect (OSTI)

    Not Available

    1991-06-01

    The report discusses the results of ocean bottom current measurements obtain from the Farallon Islands Low-Level Waste Disposal Site off the California coast, near San Francisco. The report includes a discussion of the velocity of the currents over the time period and area measured relative to large-scale currents off the California coast, and the possibility for shoreward transport of LLW Materials from the Farallon Islands Site.

  20. Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Dubrin, J.W.; Rosen, R.S.; Zoller, J.N.; Harri, J.W.; Schwertz, N.L.

    1995-12-01

    The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered, is presented. The long-term management strategy alternatives fall into three broad categories: use, storage, or disposal. Conversion of the depleted UF6 to another form such as oxide or metal is needed to implement most of these alternatives. Likewise, transportation of materials is an integral part of constructing the complete pathway between the current storage condition and ultimate disposition. The analysis of options includes development of pre-conceptual designs; estimates of effluents, wastes, and emissions; specification of resource requirements; and preliminary hazards assessments. The results of this analysis will assist DOE in selecting a strategy by providing the engineering information necessary to evaluate the environmental impacts and costs of implementing the management strategy alternatives.

  1. Waste Disposal | Department of Energy

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

    Disposal Waste Disposal Trucks transport debris from Oak Ridge’s cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. Trucks transport debris from Oak Ridge's cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. The low-level radiological and hazardous wastes generated from Oak Ridge's cleanup projects are disposed in the Environmental Management Waste Management Facility (EMWMF). The

  2. Long-Term Surveillance Operations and Maintenance Fiscal Year 2013 Year-End

    Energy Savers [EERE]

    Summary Report | Department of Energy 3 Year-End Summary Report Long-Term Surveillance Operations and Maintenance Fiscal Year 2013 Year-End Summary Report LTS-O&M is at the core of LM efforts to fulfill a strategy that includes objectives published in the 2011-2020 Strategic Plan (DOE 2011). PDF icon Long-Term Surveillance Operations and Maintenance Fiscal Year 2013 Year-End Summary Report More Documents & Publications Long-Term Surveillance Operations and Maintenance Fiscal Year

  3. Long-Term Surveillance Operations and Maintenance Fiscal Year 2014 Year-End

    Energy Savers [EERE]

    Summary Report | Department of Energy 4 Year-End Summary Report Long-Term Surveillance Operations and Maintenance Fiscal Year 2014 Year-End Summary Report The Long-Term Surveillance Operations and Maintenance (LTS-O&M) subtask has a critical long-term surveillance and maintenance (LTS&M) role for the U.S. Department of Energy (DOE) Office of Legacy Management (LM). LM needs knowledge and tools to ensure that implementation of LTS&M will be informed, efficient, and cost-effective.

  4. Assessing the Role of Iron Sulfides in the Long Term Sequestration of

    Office of Scientific and Technical Information (OSTI)

    Uranium by Sulfate-Reducing Bacteria (Technical Report) | SciTech Connect Assessing the Role of Iron Sulfides in the Long Term Sequestration of Uranium by Sulfate-Reducing Bacteria Citation Details In-Document Search Title: Assessing the Role of Iron Sulfides in the Long Term Sequestration of Uranium by Sulfate-Reducing Bacteria This overarching aim of this project was to identify the role of biogenic and synthetic iron-sulfide minerals in the long-term sequestration of reduced U(IV) formed

  5. Long-Term Management and Storage of Elemental Mercury | Department of

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

    Energy Long-Term Management and Storage of Elemental Mercury Long-Term Management and Storage of Elemental Mercury In addition to banning the export of elemental mercury from the United States as of January 1, 2013, the Mercury Export Ban Act of 2008 (MEBA) (Public Law No. 110-414) requires the Department of Energy (DOE) to establish a facility for the long-term management and storage of elemental mercury (generated with the U.S.). DOE used the National Environmental Policy Act (NEPA)

  6. Long-term management of high-level radioactive waste (HLW) and spent

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

    nuclear fuel (SNF) | Department of Energy Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor to generate nuclear energy but that has been removed from the reactor as no

  7. Assessing the Role of Iron Sulfides in the Long Term Sequestration of

    Office of Scientific and Technical Information (OSTI)

    Uranium by Sulfate-Reducing Bacteria (Technical Report) | SciTech Connect Technical Report: Assessing the Role of Iron Sulfides in the Long Term Sequestration of Uranium by Sulfate-Reducing Bacteria Citation Details In-Document Search Title: Assessing the Role of Iron Sulfides in the Long Term Sequestration of Uranium by Sulfate-Reducing Bacteria This overarching aim of this project was to identify the role of biogenic and synthetic iron-sulfide minerals in the long-term sequestration of

  8. Assessing the Role of Iron Sulfides in the Long Term Sequestration of U by

    Office of Scientific and Technical Information (OSTI)

    Sulfate Reducing Bacteria (Technical Report) | SciTech Connect SciTech Connect Search Results Technical Report: Assessing the Role of Iron Sulfides in the Long Term Sequestration of U by Sulfate Reducing Bacteria Citation Details In-Document Search Title: Assessing the Role of Iron Sulfides in the Long Term Sequestration of U by Sulfate Reducing Bacteria This four-year project's overarching aim was to identify the role of biogenic and synthetic iron-sulfide minerals in the long-term

  9. Radiation Dose and Subsequent Risk for Stomach Cancer in Long-term Survivors of Cervical Cancer

    SciTech Connect (OSTI)

    Kleinerman, Ruth A.; Smith, Susan A.; Holowaty, Eric; Hall, Per; Pukkala, Eero; Vaalavirta, Leila; Stovall, Marilyn; Weathers, Rita; Gilbert, Ethel; Aleman, Berthe M.P.; Kaijser, Magnus; Andersson, Michael; Storm, Hans; Joensuu, Heikki; Lynch, Charles F.; and others

    2013-08-01

    Purpose: To assess the doseresponse relationship for stomach cancer after radiation therapy for cervical cancer. Methods and Materials: We conducted a nested, matched casecontrol study of 201 cases and 378 controls among 53,547 5-year survivors of cervical cancer diagnosed from 1943 to 1995, from 5 international, population-based cancer registries. We estimated individual radiation doses to the site of the stomach cancer for all cases and to corresponding sites for the matched controls (overall mean stomach tumor dose, 2.56 Gy, range 0.03-46.1 and after parallel opposed pelvic fields, 1.63 Gy, range 0.12-6.3). Results: More than 90% of women received radiation therapy, mostly with external beam therapy in combination with brachytherapy. Stomach cancer risk was nonsignificantly increased (odds ratio 1.27-2.28) for women receiving between 0.5 and 4.9 Gy to the stomach cancer site and significantly increased at doses ?5 Gy (odds ratio 4.20, 95% confidence interval 1.41-13.4, P{sub trend}=.047) compared with nonirradiated women. A highly significant radiation doseresponse relationship was evident when analyses were restricted to the 131 cases (251 controls) whose stomach cancer was located in the middle and lower portions of the stomach (P{sub trend}=.003), whereas there was no indication of increasing risk with increasing dose for 30 cases (57 controls) whose cancer was located in the upper stomach (P{sub trend}=.23). Conclusions: Our findings show for the first time a significant linear doseresponse relationship for risk of stomach cancer in long-term survivors of cervical cancer.

  10. Spatial distribution of HTO activity in unsaturated soil depth in the vicinity of long-term release source

    SciTech Connect (OSTI)

    Golubev, A.; Golubeva, V.; Mavrin, S.

    2015-03-15

    Previous studies reported about a correlation between HTO activity distribution in unsaturated soil layer and atmospheric long-term releases of HTO in the vicinity of Savannah River Site. The Tritium Working Group of BIOMASS Programme has performed a model-model intercomparison study of HTO transport from atmosphere to unsaturated soil and has evaluated HTO activity distribution in the unsaturated soil layer in the vicinity of permanent atmospheric sources. The Tritium Working Group has also reported about such a correlation, however the conclusion was that experimental data sets are needed to confirm this conclusion and also to validate appropriate computer models. (authors)

  11. Long-Term Surveillance and Maintenance Records: Maintaining Access to the Knowledge - 13122

    SciTech Connect (OSTI)

    Montgomery, John; Gueretta, Jeanie; McKinney, Ruth; Anglim, Cliff

    2013-07-01

    The U.S. Department of Energy (DOE) Office of Legacy Management (LM) is an integral part of DOE's strategy to ensure that legacy liabilities of former nuclear weapons production sites are properly managed following the completion of environmental cleanup activities. In the area of environmental legacy management, records management is crucial to the protection of health, environmental, and legal interests of the Department and the public. LM is responsible for maintaining long-term surveillance and maintenance (LTS and M) records in performance of its mission. Maintaining access to the knowledge contained in these record collections is one of LM's primary responsibilities. To fulfill this responsibility, LM established a consolidated records management facility, the LM Business Center (LMBC), to house physical media records and electronic records. A new electronic record keeping system (ERKS) was needed to replace an obsolete system while helping to ensure LM is able to meet ongoing responsibilities to maintain access to knowledge and control the life cycle management of records. (authors)

  12. A Perspective on Long-Term Recovery Following the Fukushima Nuclear Accident - 12075

    SciTech Connect (OSTI)

    Chen, S.Y.

    2012-07-01

    The tragic events at the Fukushima Daiichi Nuclear Power Station began occurring on March 11, 2011, following Japan's unprecedented earthquake and tsunami. The subsequent loss of external power and on-site cooling capacity severely compromised the plant's safety systems, and subsequently, led to core melt in the affected reactors and damage to spent nuclear fuel in the storage pools. Together with hydrogen explosions, this resulted in a substantial release of radioactive material to the environment (mostly Iodine-131 and Cesium- 137), prompting an extensive evacuation effort. The latest release estimate places the event at the highest severity level (Level 7) on the International Nuclear Event Scale, the same as the Chernobyl accident of 1986. As the utility owner endeavored to stabilize the damaged facility, environmental contamination continued to propagate and affect every aspect of daily life in the affected region of Japan. Elevated levels of radioactivity (mostly dominated by Cs-137 with the passage of time) were found in soil, drinking water, vegetation, produce, seafood, and other foodstuffs. An estimated 80,000 to 90,000 people were evacuated; more evacuations are being contemplated months after the accident, and a vast amount of land has become contaminated. Early actions were taken to ban the shipment and sale of contaminated food and drinking water, followed by later actions to ban the shipment and sale of contaminated beef, mushrooms, and seafood. As the event continues to evolve toward stabilization, the long-term recovery effort needs to commence - a process that doubtless will involve rather complex decision-making interactions between various stakeholders. Key issues that may be encountered and considered in such a process include (1) socio-political factors, (2) local economic considerations, (3) land use options, (4) remediation approaches, (5) decontamination methods, (6) radioactive waste management, (7) cleanup levels and options, and (8) government policies, among others. This paper offers a perspective on this likely long and arduous journey toward establishing a 'new normal' that will ultimately take shape. Toward this end, it is important to evaluate the 'optimization' process advocated by the international community in achieving long-term recovery from this particularly fateful event in Fukushima. In the process, experience and lessons learned from past events will be fully evaluated and considered. (author)

  13. Final EIS for Decommissioning and/or Long-Term Stewardship at the WVDP and Western New York Nuclear Service Center

    Energy Savers [EERE]

    DOE/EIS-0226 January 2010 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center A Summary and Guide for Stakeholders The West Valley Site Availability of the Final EIS for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center For further information on this Final EIS, or to request a copy of the EIS or

  14. Development and Update of Long-Term Energy and GHG Emission Macroecono...

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

    Approach: Create a Long Term Base Case Major Inputs 9 Light Vehicles (Car and Light Truck) Heavy Vehicles (GVW Class 3-8) Medium: Class 3-6 Truck Heavy:...

  15. EIS-0480: Long-Term Experimental and Management Plan for the...

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

    Bureau of Reclamation and National Park Service, are jointly preparing a Long-Term Experimental and Management Plan for the Glen Canyon Dam and an EIS for adoption of the Plan. ...

  16. Evaluation of Long-Term Cloud-Resolving Modeling with ARM Data

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

    Evaluation of Long-Term Cloud-Resolving Modeling with ARM Data Zeng, Xiping NASAGSFC Tao, Wei-Kuo NASAGoddard Space Flight Center Zhang, Minghua State University of New York at ...

  17. Long-Term Testing of Geothermal Wells in the Coso Hot Springs...

    Open Energy Info (EERE)

    Testing of Geothermal Wells in the Coso Hot Springs KGRA Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Proceedings: Long-Term Testing of Geothermal...

  18. Algal Biofuels: Long-Term Energy Benefits Drive U.S. Research

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

    Algal Biofuels Algal Biofuels: Long-Term Energy Benefits Driv e U.S. Research Algal biofuels can help build U.S. energy security as part of a broad national strategy to cultivate ...

  19. Long-Term Changes in Gas- and Particle-Phase Emissions from On...

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

    Changes in Gas- and Particle-Phase Emissions from On-Road Diesel and Gasoline Vehicles Long-Term Changes in Gas- and Particle-Phase Emissions from On-Road Diesel and Gasoline ...

  20. Long-term Decline of Aggregate Fuel Use per Cargo-ton-mile of...

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

    Long-term Decline of Aggregate Fuel Use per Cargo-ton-mile of Commercial Trucking; A Key Enabler of Expanded U.S. Trade and Economic Growth Poster presentation at the 2007 Diesel ...

  1. Long-Term Flow Test No. 1, Roosevelt Hot Springs, Utah | Open...

    Open Energy Info (EERE)

    Flow Test No. 1, Roosevelt Hot Springs, Utah Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Long-Term Flow Test No. 1, Roosevelt Hot Springs,...

  2. Hydrogen Delivery Infrastructure Analysis, Options and Trade-offs, Transition and Long-term

    Broader source: Energy.gov [DOE]

    Presentation on Hydrogen Delivery Infrastructure Analysis, Options and Trade-offs, Transition and Long-term for the DOE Hydrogen Delivery High-Pressure Tanks and Analysis Project Review Meeting held February 8-9, 2005 at Argonne National Laboratory

  3. Evalution of long-term surface-retrieved cloud-droplet number concentration

    Office of Scientific and Technical Information (OSTI)

    with in situ aircraft observations (Journal Article) | SciTech Connect Evalution of long-term surface-retrieved cloud-droplet number concentration with in situ aircraft observations Citation Details In-Document Search Title: Evalution of long-term surface-retrieved cloud-droplet number concentration with in situ aircraft observations A new cloud-droplet number concentration (NDROP) value added product (VAP) has been produced at the Atmospheric Radiation Measurement (ARM) Southern Great

  4. Long Term Environment and Economic Impacts of Coal Liquefaction in China

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Long Term Environment and Economic Impacts of Coal Liquefaction in China Citation Details In-Document Search Title: Long Term Environment and Economic Impacts of Coal Liquefaction in China The project currently is composed of six specific tasks - three research tasks, two outreach and training tasks, and one project management and communications task. Task 1 addresses project management and communication. Research activities focused on Task 2 (Describe

  5. Long-Term Demonstration of Hydrogen Production from Coal at Elevated

    Office of Scientific and Technical Information (OSTI)

    Temperatures Year 6 - Activity 1.12 - Development of a National Center for Hydrogen Technology (Technical Report) | SciTech Connect Technical Report: Long-Term Demonstration of Hydrogen Production from Coal at Elevated Temperatures Year 6 - Activity 1.12 - Development of a National Center for Hydrogen Technology Citation Details In-Document Search Title: Long-Term Demonstration of Hydrogen Production from Coal at Elevated Temperatures Year 6 - Activity 1.12 - Development of a National Center

  6. Long-Term Stewardship of Mixed Wastes: Passive Reactive Barriers for

    Office of Scientific and Technical Information (OSTI)

    Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal, and Radionuclide Contaminants (Technical Report) | SciTech Connect Long-Term Stewardship of Mixed Wastes: Passive Reactive Barriers for Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal, and Radionuclide Contaminants Citation Details In-Document Search Title: Long-Term Stewardship of Mixed Wastes: Passive Reactive Barriers for Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal, and

  7. Long-term Stewardship of Mixed Wastes: Passive Reactive Barriers for

    Office of Scientific and Technical Information (OSTI)

    Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal and Radioactive (Technical Report) | SciTech Connect Long-term Stewardship of Mixed Wastes: Passive Reactive Barriers for Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal and Radioactive Citation Details In-Document Search Title: Long-term Stewardship of Mixed Wastes: Passive Reactive Barriers for Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal and Radioactive This project report

  8. Missouri Entices With Rebates, Lends for the Long-Term | Department of

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

    Energy Missouri Entices With Rebates, Lends for the Long-Term Missouri Entices With Rebates, Lends for the Long-Term When the Missouri Agricultural Energy Savings Team-A Revolutionary Opportunity (MAESTRO) first reached out to farmers to offer loans for efficiency upgrades, they were surprised to find the farmers often declined this offer. What MAESTRO soon realized was that they needed to find another way to generate initial interest. MAESTRO decided to offer rebates for three levels of

  9. 2015 - LNG Export, Compressed Natural Gas (CNG), Re-Exports & Long Term

    Energy Savers [EERE]

    Natural Gas Applications | Department of Energy 5 - LNG Export, Compressed Natural Gas (CNG), Re-Exports & Long Term Natural Gas Applications 2015 - LNG Export, Compressed Natural Gas (CNG), Re-Exports & Long Term Natural Gas Applications Please note: To view the complete docket listing, please click the 'Docket Index' link pertaining to a particular docket. Docket Indexes and Service Lists that are not listed can be obtained by contacting the Docket Room Manager at 202-586-9478 or

  10. Long-Term Water Projections and Climate Change | U.S. DOE Office of Science

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

    Temperatures Year 6 - Activity 1.12 - Development of a National Center for Hydrogen Technology (Technical Report) | SciTech Connect Technical Report: Long-Term Demonstration of Hydrogen Production from Coal at Elevated Temperatures Year 6 - Activity 1.12 - Development of a National Center for Hydrogen Technology Citation Details In-Document Search Title: Long-Term Demonstration of Hydrogen Production from Coal at Elevated Temperatures Year 6 - Activity 1.12 - Development of a National Center

  11. DOE Fuel Cell Pre-Solicitation Workshop - Breakout Group 5: Long-Term

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

    Innovative Technologies | Department of Energy 5: Long-Term Innovative Technologies DOE Fuel Cell Pre-Solicitation Workshop - Breakout Group 5: Long-Term Innovative Technologies Report from Breakout Group 5 of the DOE Fuel Cell Pre-Solicitation Workshop, March 16-17, 2010 PDF icon fuelcell_pre-solicitation_wkshop_innovative_tech.pdf More Documents & Publications DOE Fuel Cell Pre-Solicitation Workshop - Breakout Group 4: Low Temperature Fuel Cell System BOP & FUEL Processors For

  12. The application of compressed sensing to long-term acoustic emission-based

    Office of Scientific and Technical Information (OSTI)

    structural health monitoring (Conference) | SciTech Connect Conference: The application of compressed sensing to long-term acoustic emission-based structural health monitoring Citation Details In-Document Search Title: The application of compressed sensing to long-term acoustic emission-based structural health monitoring Authors: Park, Gyuhae [1] ; Farrar, Chuck R [1] ; Mascarenas, David L [1] ; Cattaneo, Alessandro [2] + Show Author Affiliations Los Alamos National Laboratory POLITEENICO DI

  13. The relationship between interannual and long-term cloud feedbacks (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect The relationship between interannual and long-term cloud feedbacks Citation Details In-Document Search This content will become publicly available on December 11, 2016 Title: The relationship between interannual and long-term cloud feedbacks The analyses of Coupled Model Intercomparison Project phase 5 simulations suggest that climate models with more positive cloud feedback in response to interannual climate fluctuations also have more positive cloud feedback in

  14. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

    1996-03-01

    A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

  15. Root Diseases and Exotic Ecosystems: Implications for Long-Term Site Productivity

    SciTech Connect (OSTI)

    Otrosina, W. J.; Garbelotto, M.

    1997-09-01

    Management activities and various land uses have taken place recently that have dramatically altered edaphic and environmental conditions under which forest tree species and ecosystems have evolved. Sequoia giganteum stands, fire suppression in this fire dependent ecosystem has resulted in increased mortality due to Heterobasidion annosum. On hypothesis is that fire suppression results in increased encroachment of true firs, easily infected by S-group Heterobasidion annosum, thereby transferring the disease via root contacts with S. giganteum. Existence of a hybrid with S and P ISG's of H. annosum may be evidence for anthropogenic influences on evolutionary pathways in this pathogen.

  16. Long-Term Surveillance and Maintenance at the Rocky Flats Site...

    Energy Savers [EERE]

    as a buffer zone surrounding the former industrial area, was transferred to the U.S. Fish and Wildlife Service in July 2007 for a national wildlife refuge. DOE's Office of...

  17. Oil field waste disposal costs at commercial disposal facilities

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

  18. Monitoring of the Airport Calibration Pads at Walker Field, Grand Junction, Colorado, for Long-Term Radiation Variations (August 1978)

    Broader source: Energy.gov [DOE]

    Monitoring of the Airport Calibration Pads at Walker Field, Grand Junction, Colorado, for Long-Term Radiation Variations (August 1978)

  19. Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax/bl at the Nevada Test Site

    SciTech Connect (OSTI)

    Levitt, D.G.; Fitzmaurice, T.M.

    2001-02-01

    In October 2000, final closure was initiated of U-3ax/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to the disposal unit initiated closure. This closure is unique in that it required the involvement of several U.S. Department of Energy (DOE) Environmental Management (EM) groups: Waste Management (WM), Environmental Restoration (ER), and Technology Development (TD). Initial site characterization of the disposal unit was conducted by WM. Regulatory approval for closure of the disposal unit was obtained by ER, closure of the disposal unit was conducted by ER, and deployment of the drainage lysimeter facility was conducted by WM and ER, with funding provided by the Accelerated Site Technology Deployment ( ASTD) program, administered under TD. In addition, this closure is unique in that a monolayer closure cover, also known as an evapotranspiration (ET) cover, consisting of native alluvium, received regulatory approval instead of a traditional Resource Conservation and Recovery Act (RCRA) multi-layered cover. Recent studies indicate that in the arid southwestern United States, monolayer covers may be more effective at isolating waste than layered covers because of the tendency of clay layers to desiccate and crack, and subsequently develop preferential pathways. The lysimeter facility deployed immediately adjacent to the closure cover consists of eight drainage lysimeters with three surface treatments: two were left bare; two were revegetated with native species; two were allowed to revegetate with invader species; and two are reserved for future studies. The lysimeters are constructed such that any drainage through the bottoms of the lysimeters can be measured. Sensors installed in the closure cover provide soil water content data, whereas sensors installed in the lysimeters provide soil water content, soil water potential, soil temperature, and drainage data for a detailed evaluation of the cover performance. Revegetation establishes a stable plant community that maximizes water loss through transpiration and reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment.

  20. Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia

    SciTech Connect (OSTI)

    Wolff, Dietmar; Voelzke, Holger; Weber, Wolfgang; Noack, Volker; Baeuerle, Guenther

    2007-07-01

    The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of Economics and Labour (BMWi). On the Russian side the Kurchatov Institute holds the project management of the long-term interim storage facility in Sayda Bay, whilst the Nerpa Shipyard, which is about 25 km away from the storage facility, is dismantling the submarines and preparing the reactor compartments for long-term interim storage. The technical monitoring of the German part of this project, being implemented by BMWi, is the responsibility of the Federal Institute for Materials Research and Testing (BAM). This paper gives an overview of the German-Russian project and a brief description of solutions for nuclear submarine disposal in other countries. At Nerpa shipyard, being refurbished with logistic and technical support from Germany, the reactor compartments are sealed by welding, provided with biological shielding, subjected to surface treatment and conservation measures. Using floating docks, a tugboat tows the reactor compartments from Nerpa shipyard to the interim storage facility at Sayda Bay where they will be left on the on-shore concrete storage space to allow the radioactivity to decay. For transport of reactor compartments at the shipyard, at the dock and at the storage facility, hydraulic keel blocks, developed and supplied by German subcontractors, are used. In July 2006 the first stage of the reactor compartment storage facility was commissioned and the first seven reactor compartments have been delivered from Nerpa shipyard. Following transports of reactor compartments to the storage facility are expected in 2007. (authors)

  1. Demonstration of In-Situ Stabilization of Buried Waste at Pit G-11 at the Brookhaven National laboratory Glass Pits Disposal Site

    SciTech Connect (OSTI)

    Dwyer, B.P.; Gilbert, J.; Heiser, J.

    1999-01-01

    In 1989 BNL was added to the EPAs National Priorities List. The site is divided into seven operable units (OU). OU-I includes the former landfill area. The field task site is noted as the AOC 2C Glass Holes location. Beginning in the 1960s and continuing into the 1980s, BNL disposed of laboratory waste (glassware, chemicals and animal carcasses) in numerous shallow pits. The drivers for remediating the pits are; historical records that indicate hazardous materials may have been disposed of in the pits; ground water contamination down gradient of the pits; a test excavation of one of the glass holes that unearthed laboratory glass bottles with unidentified liquids still contained; and the fact that BNL rests atop an EPA designated sole-source aquifer. The specific site chosen for this demonstration was pit G-11. The requirements that lead to choosing this pit were; a well characterized pit and a relatively isolated pit where our construction operations would not impact on adjacent pits. The glass holes area, including pit G-11, was comprehensively surveyed using a suite of geophysical techniques (e.g., EM-31, EM-61, GPR). Prior to stabilizing the waste form a subsurface barrier was constructed to contain the entire waste pit. The pit contents were then stabilized using a cement grout applied via jet grouting. The stabilization was performed to make removal of the waste from the pit easier and safer in terms of worker exposure. The grouting process would mix and masticate the waste and grout and form a single monolithic waste form. This large monolith would then be subdivided into smaller 4 foot by 4 foot by 10-12 foot block using a demolition grout. The smaller blocks would then be easily removed from the site and disposed of in a CERCLA waste site.

  2. High Temperature Steam Electrolysis: Demonstration of Improved Long-Term Performance

    SciTech Connect (OSTI)

    J. E. O'Brien; X. Zhang; R. C. O'Brien; G. Tao

    2011-11-01

    Long-term performance is an ongoing issue for hydrogen production based on high-temperature steam electrolysis (HTSE). For commercial deployment, solid-oxide electrolysis stacks must achieve high performance with long-term degradation rates of {approx}0.5%/1000 hours or lower. Significant progress has been achieved toward this goal over the past few years. This paper will provide details of progress achieved under the Idaho National Laboratory high temperature electrolysis research program. Recent long-term stack tests have achieved high initial performance with degradation rates less than 5%/khr. These tests utilize internally manifolded stacks with electrode-supported cells. The cell material sets are optimized for the electrolysis mode of operation. Details of the cells and stacks will be provided along with details of the test apparatus, procedures, and results.

  3. LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan |

    Energy Savers [EERE]

    Department of Energy LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water

  4. LOWER BOUNDS ON MAGNETIC FIELDS IN INTERGALACTIC VOIDS FROM LONG-TERM

    Office of Scientific and Technical Information (OSTI)

    GeV-TeV LIGHT CURVES OF THE BLAZAR MRK 421 (Journal Article) | SciTech Connect MAGNETIC FIELDS IN INTERGALACTIC VOIDS FROM LONG-TERM GeV-TeV LIGHT CURVES OF THE BLAZAR MRK 421 Citation Details In-Document Search Title: LOWER BOUNDS ON MAGNETIC FIELDS IN INTERGALACTIC VOIDS FROM LONG-TERM GeV-TeV LIGHT CURVES OF THE BLAZAR MRK 421 Lower bounds are derived on the amplitude B of intergalactic magnetic fields (IGMFs) in the region between Galaxy and the blazar Mrk 421, from constraints on the

  5. MODELING OF LONG-TERM FATE OF MOBILIZED FINES DUE TO DAM-EMBANKMENT

    Office of Scientific and Technical Information (OSTI)

    INTERFACIAL DISLOCATIONS (Conference) | SciTech Connect MODELING OF LONG-TERM FATE OF MOBILIZED FINES DUE TO DAM-EMBANKMENT INTERFACIAL DISLOCATIONS Citation Details In-Document Search Title: MODELING OF LONG-TERM FATE OF MOBILIZED FINES DUE TO DAM-EMBANKMENT INTERFACIAL DISLOCATIONS Authors: Ezzedine, S ; Kanarska, Y ; Lomov, I ; Antoun, T ; Glascoe, L Publication Date: 2011-07-29 OSTI Identifier: 1093897 Report Number(s): LLNL-PROC-491853 DOE Contract Number: W-7405-ENG-48 Resource Type:

  6. Glen Canyon Dam Long-Term Experimental and Management Plan DEIS

    Energy Savers [EERE]

    A-1 1 2 3 4 5 6 7 8 9 10 11 12 APPENDIX A: 13 14 ADAPTIVE MANAGEMENT WORKING GROUP 15 DESIRED FUTURE CONDITIONS 16 17 Glen Canyon Dam Long-Term Experimental and Management Plan December 2015 Draft Environmental Impact Statement A-2 1 2 3 4 5 6 7 8 9 10 11 12 This page intentionally left blank 13 14 15 Glen Canyon Dam Long-Term Experimental and Management Plan December 2015 Draft Environmental Impact Statement A-3 APPENDIX A: 1 2 ADAPTIVE MANAGEMENT WORKING GROUP 3 DESIRED FUTURE CONDITIONS 4 5 6

  7. Glen Canyon Dam Long-Term Experimental and Management Plan DEIS

    Energy Savers [EERE]

    K-1 1 2 3 4 5 6 7 8 9 10 11 12 APPENDIX K: 13 14 HYDROPOWER SYSTEMS TECHNICAL INFORMATION AND ANALYSIS 15 16 Glen Canyon Dam Long-Term Experimental and Management Plan December 2015 Draft Environmental Impact Statement K-2 1 2 3 4 5 6 7 8 9 10 11 12 This page intentionally left blank 13 14 15 Glen Canyon Dam Long-Term Experimental and Management Plan December 2015 Draft Environmental Impact Statement K-3 APPENDIX K: 1 2 HYDROPOWER SYSTEMS TECHNICAL INFORMATION AND ANALYSIS 3 4 5 This appendix

  8. DOE Announces Up to $15.3 Million for Long-Term Hydrogen Vehicle

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

    Development | Department of Energy Up to $15.3 Million for Long-Term Hydrogen Vehicle Development DOE Announces Up to $15.3 Million for Long-Term Hydrogen Vehicle Development August 14, 2008 - 2:40pm Addthis WASHINGTON- U.S. Department of Energy (DOE) Under Secretary Clarence H. "Bud" Albright, Jr. today announced the selection of 10 cost-shared hydrogen storage research and development projects, which will receive up to $15.3 million over five years, subject to annual

  9. LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan |

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

    Department of Energy LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water

  10. Greensburg Implements High-Efficiency Building Codes to Achieve Long-Term

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

    Energy Savings | Department of Energy Greensburg Implements High-Efficiency Building Codes to Achieve Long-Term Energy Savings Greensburg Implements High-Efficiency Building Codes to Achieve Long-Term Energy Savings The LEED Platinum K-12 school in Greensburg, Kansas. <em>Photo from Joah Bussert, Greensburg GreenTown, NREL 19952</em> The LEED Platinum K-12 school in Greensburg, Kansas. Photo from Joah Bussert, Greensburg GreenTown, NREL 19952 On May 4, 2007, a massive tornado

  11. Development of long-term performance models for radioactive waste forms

    SciTech Connect (OSTI)

    Bacon, Diana H.; Pierce, Eric M.

    2011-03-22

    The long-term performance of solid radioactive waste is measured by the release rate of radionuclides into the environment, which depends on corrosion or weathering rates of the solid waste form. The reactions involved depend on the characteristics of the solid matrix containing the radioactive waste, the radionuclides of interest, and their interaction with surrounding geologic materials. This chapter describes thermo-hydro-mechanical and reactive transport models related to the long-term performance of solid radioactive waste forms, including metal, ceramic, glass, steam reformer and cement. Future trends involving Monte-Carlo simulations and coupled/multi-scale process modeling are also discussed.

  12. Formation of Interfacial Layer and Long-Term Cyclability of Li-O2 Batteries

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

    - Joint Center for Energy Storage Research July 28, 2014, Research Highlights Formation of Interfacial Layer and Long-Term Cyclability of Li-O2 Batteries Surface morphology of air electrode at discharge (a,c) and charge (b, d) conditions after first (a, b) and 10th (c, d) cycles. Scientific Achievement Identified key factors that affect the long term cycle life of Li-O2 batteries under full discharge/charge conditions. Significance and Impact The interfacial layer which in situ forms on air

  13. PROBCON-HDW: A probability and consequence system of codes for long-term analysis of Hanford defense wastes

    SciTech Connect (OSTI)

    Piepho, M.G.; Nguyen, T.H.

    1988-12-01

    The PROBCON-HDW (PROBability and CONsequence analysis for Hanford defense waste) computer code system calculates the long-term cumulative releases of radionuclides from the Hanford defense wastes (HDW) to the accessible environment and compares the releases to environmental release limits as defined in 40 CFR 191. PROBCON-HDW takes into account the variability of input parameter values used in models to calculate HDW release and transport in the vadose zone to the accessible environment (taken here as groundwater). A human intrusion scenario, which consists of drilling boreholes into the waste beneath the waste sites and bringing waste to the surface, is also included in PROBCON-HDW. PROBCON-HDW also includes the capability to combine the cumulative releases according to various long-term (10,000 year) scenarios into a composite risk curve or complementary cumulative distribution function (CCDF). The system structure of the PROBCON-HDW codes, the mathematical models in PROBCON-HDW, the input files, the input formats, the command files, and the graphical output results of several HDW release scenarios are described in the report. 3 refs., 7 figs., 9 tabs.

  14. Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Church, A.; Gordon, J.; Montrose, J. K.

    2002-02-26

    In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.

  15. Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect (OSTI)

    Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

    1993-06-01

    Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen.

  16. Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site

    SciTech Connect (OSTI)

    Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

    1995-03-01

    In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

  17. Recharge Data Package for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect (OSTI)

    Fayer, Michael J.; Szecsody, Jim E.

    2004-06-30

    Pacific Northwest National Laboratory assisted CH2M Hill Hanford Group, Inc., (CHG) by providing estimates of recharge rates for current conditions and long-term scenarios involving disposal in the Integrated Disposal Facility (IDF). The IDF will be located in the 200 East Area at the Hanford Site and will receive several types of waste including immobilized low-activity waste. The recharge estimates for each scenario were derived from lysimeter and tracer data collected by the IDF PA Project and from modeling studies conducted for the project. Recharge estimates were provided for three specific site features (the surface barrier; possible barrier side slopes; and the surrounding soil) and four specific time periods (pre-Hanford; Hanford operations; surface barrier design life; post-barrier design life). CHG plans to conduct a performance assessment of the latest IDF design and call it the IDF 2005 PA; this recharge data package supports the upcoming IDF 2005 PA.

  18. Strategy for Long-Term Stewardship and Monitoring of Amchitka Island - 12190

    SciTech Connect (OSTI)

    Kautsky, Mark; Nguyen, Jason; Darr, Paul S.; Picel, Mary

    2012-07-01

    The Long-Term Surveillance and Maintenance Plan (LTSMP) for Amchitka details how the U.S. Department of Energy (DOE) intends to fulfill its mission to maintain protection of human health and the environment at and around the sites on Amchitka Island. The LTSMP calls for monitoring to be performed every 5 years, at least in the initial phase of the project. The purpose of the monitoring is to develop a baseline of activity concentrations for selected radionuclides in biota, water, and soil, both on Amchitka and at the reference location on Adak Island, approximately 322 km (200 miles) northeast of Amchitka. Data compiled by the Consortium for Risk Evaluation with Stakeholder Participation (CRESP, 2006) are being included as part of the baseline data set. The specific biological, water, and sediment samples collected during the 2011 sampling event were developed through close coordination with the primary stakeholders, including the Alaska Department of Environmental Conservation, the Aleutian Pribilof Island Association, and the U.S. Fish and Wildlife Service (USFWS). Amchitka is managed by the USFWS as part of the Alaska Maritime National Wildlife Refuge. Two plans were developed to address specific needs of the biological- and the terrestrial-monitoring programs. Results from these monitoring programs will help determine whether the environment is being impacted by radionuclide migration and uptake, and if subsistence and commercial-catch seafood is safe for human consumption. The RESRAD-BIOTA code is being used to evaluate ecological health relative to the radionuclide levels determined from this sampling event. The samples were sent to three laboratories for analysis. With the exception of the seawater samples, most of the samples were sent to the Center for Accelerator Mass Spectrometry at the Lawrence Livermore National Laboratory. A smaller subset of rock-weed samples, Star reindeer lichen samples, and soil samples collected from beneath the lichen were sent to UAF for cesium-137 analysis. Marine sediment samples were also collected and sent to UAF for testing. The seawater samples were sent to the University of Miami Tritium Laboratory for enriched tritium analysis. Results from the seawater samples for tritium were received in September 2011. Results from the 2011 sampling are expected to be available on the LM web site in 2012. (authors)

  19. Development of weld closure stations for plutonium long-term storage containers

    SciTech Connect (OSTI)

    Fernandez, R.; Martinez, D.A.; Martinez, H.E.; Nelson, T.O.; Ortega, R.E.; Rofer, C.K.; Romero, W.; Stewart, J.; Trujillo, V.L.

    1998-12-31

    Weld closure stations for plutonium long-term storage containers have been designed, fabricated, and tested for the Advanced Recovery and Integrated Extraction System (ARIES) at the TA-55 Plutonium Facility of the Los Alamos National Laboratory. ARIES is a processing system used for the dismantlement of the plutonium pits from nuclear weapons. ARIES prepares the extracted-plutonium in a form which is compatible with long-term storage and disposition options and meets international inspection requirements. The processed plutonium is delivered to the canning module of the ARIES line, where it is packaged in a stainless steel container. This container is then packaged in a secondary container for long-term storage. Each of the containers is hermetically sealed with a full penetration weld closure that meets the requirements of the ASME Section IX Boiler and Pressure Vessel Code. Welding is performed with a gas tungsten arc process in an inert atmosphere of helium. The encapsulated helium in the nested containers allows for leak testing the weld closure and container. The storage package was designed to meet packaging requirements of DOE Standard 3013-96 for long-term storage of plutonium metal and oxides. Development of the process parameters, weld fixture, weld qualification, and the welding chambers is discussed in this paper.

  20. Mixer pump long term operations plan for Tank 241-SY-101 mitigation

    SciTech Connect (OSTI)

    Irwin, J.J.

    1994-09-07

    This document provides the general Operations Plan for performance of the mixer pump long term operations for Tank 241-SY-101 mitigation of gas retention and periodic release in Tank 101-SY. This operations plan will utilize a 112 kW (150 hp) mixing pump to agitate/suspend the particulates in the tank.

  1. Long term contracts, expansion, innovation and stability: North Dakota's lignite mines thrive

    SciTech Connect (OSTI)

    Buchsbaum, L.

    2009-08-15

    North Dakota's lignite coal industry is mainly located in three countries in the central part of the state. Its large surface lignite mines are tied through long-term (20-40 years) contracts to power plants. The article talks about operations at three of the most productive mines - the Freedom mine, Falkirk mine and Center Mine. 4 figs.

  2. Challenges for Long-Term Energy Models: Modeling Energy Use and Energy Efficiency

    U.S. Energy Information Administration (EIA) Indexed Site

    Long-Term Energy Models: Modeling Energy Use and Energy Efficiency James Sweeney Stanford University Director, Precourt Institute for Energy Efficiency Professor, Management Science and Engineering Presentation to EIA 2008 Energy Conference 34 ! Years of Energy Information and Analysis Some Modeling History * Original Federal Energy Administration Demand Models in PIES and IEES (1974) - Residential, Industrial, Commercial Sectors * Econometric models * Dynamic specification * Allowed matrix of

  3. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado: Remedial Action Selection Report. Preliminary final

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    This proposed remedial action plan incorporates the results of detailed investigation of geologic, geomorphic, and seismic conditions at the proposed disposal site. The proposed remedial action will consist of relocating the uranium mill tailings, contaminated vicinity property materials, demolition debris, and windblown/waterborne materials to a permanent repository at the proposed Burro Canyon disposal cell. The proposed disposal site will be geomorphically stable. Seismic design parameters were developed for the geotechnical analyses of the proposed cell. Cell stability was analyzed to ensure long-term performance of the disposal cell in meeting design standards, including slope stability, settlement, and liquefaction potential. The proposed cell cover and erosion protection features were also analyzed and designed to protect the RRM (residual radioactive materials) against surface water and wind erosion. The location of the proposed cell precludes the need for permanent drainage or interceptor ditches. Rock to be used on the cell top-, side-, and toeslopes was sized to withstand probable maximum precipitation events.

  4. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-07-19

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  5. Low-level radioactive waste disposal facility closure

    SciTech Connect (OSTI)

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. )

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  6. Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes

    SciTech Connect (OSTI)

    Heuze, F.E.

    1981-02-01

    This document discusses the potential of the Climax pluton, at the Nevada Test Site, as the host for a granite mechanics test facility related to the geologic disposal of high-level nuclear waste. The Climax granitic pluton has been the site of three nuclear weapons effects tests: Hard Hat, Tiny Tot, and Piledriver. Geologic exploration and mapping of the granite body were performed at the occasion of these tests. Currently, it is the site Spent Fuel Test (SFT-C) conducted in the vicinity of and at the same depth as that of the Piledriver drifts. Significant exploration, mapping, and rock mechanics work have been performed and continue at this Piledriver level - the 1400 (ft) level - in the context of SFT-C. Based on our technical discussions, and on the review of the significant geological and rock mechanics work already achieved in the Climax pluton, based also on the ongoing work and the existing access and support, it is concluded that the Climax site offers great opportunities for a rock mechanics test facility. It is not claimed, however, that Climax is the only possible site or the best possible site, since no case has been made for another granite test facility in the United States. 12 figures, 3 tables.

  7. 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

    2011-04-01

    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.

  8. IN-SITU, LONG-TERM MONITORING SYSTEM FOR RADIOACTIVE CONTAMINANTS

    SciTech Connect (OSTI)

    James S. Durham; Stephen W.S. McKeever; Mark S. Akselrod

    2002-10-01

    This report presents the results of the first phase of the project entitled ''In-situ, Long-term Monitoring System for Radioactive Contaminants.'' Phase one of this effort included four objectives, each with specific success criteria. The first objective was to produce dosimetry grade fibers and rods of aluminum oxide. The success criterion for this milestone was the production of aluminum oxide rods and fibers that have a minimum measurable dose (MMD) of 100 mrem or less. This milestone was completed and the MMD for the rods was measured to be 1.53 mrem. Based on the MMD, the ability of the sensor to measure {sup 137}Cs, {sup 90}Sr/{sup 90}Y, and {sup 99}Tc was evaluated. It was determined that the sensor can measure the release limit of these radionuclides (50 pCi/cm{sup 3}) in 150 h, 200 h, and 54,000 h, respectively. The monitor is adequate for measuring {sup 137}Cs and {sup 90}Sr/{sup 90}Y but is unsuitable for measuring {sup 99}Tc in soil. The second objective was to construct a prototype sensor (dosimeter and fiber optic channel). There were three success criteria for this milestone: (1) Perform measurements with the sensor for both gamma and beta radiation with a standard deviation of 10% or less; (2) Demonstrate the ability of the sensor to discriminate between gamma and beta radiation; and (3) Obtain similar or relatable results for differing lengths of fiber optic cable. These milestones were met. The sensor was able to measure gamma radiation repeatedly with a standard deviation of 3.15% and beta radiation with a standard deviation of 2.85%. Data is presented that demonstrates that an end cap can be used to discriminate between beta plus gamma radiation using beta radiation from a {sup 90}Sr/{sup 90}Y source, and gamma radiation alone. It is shown that some amount of attenuation occurs in longer fiber optic cables, but it is unclear if the attenuation is due to poor alignment of the dosimeter and the cable. This issue will be investigated further when more dosimeters are available so that the dosimeters can be permanently attached to the longer cables. The third objective was to identify a demonstration site. The success criterion for this milestone was to obtain a written agreement from a DOE site to host the demonstration of the monitor during the third phase. Because of uncertainties in funding of the second and third phases of this effort, a written agreement was not obtained. Instead, verbal agreements were reached with both Hanford and the Nevada Test Site. It is believed that the verbal agreements meet the intent of the objective. The final objective was to prepare the Draft Phase I Topical Report. The success criterion for this milestone was to have the report accepted by NETL. It is anticipated that this objective will be met.

  9. IN-SITU, LONG-TERM MONITORING SYSTEM FOR RADIOACTIVE CONTAMINANTS

    SciTech Connect (OSTI)

    James S. Durham; Stephen W.S. McKeever; Mark S. Akselrod

    2002-10-01

    This report presents the results of the first phase of the project entitled ''In-situ, Long-term Monitoring System for Radioactive Contaminants.'' Phase one of this effort included four objectives, each with specific success criteria. The first objective was to produce dosimetry grade fibers and rods of aluminum oxide. The success criterion for this milestone was the production of aluminum oxide rods and fibers that have a minimum measureable dose (MMD) of 100 mrem or less. This milestone was completed and the MMD for the rods was measured to be 1.53 mrem. Based on the MMD, the ability of the sensor to measure {sup 137}Cs, {sup 90}Sr/{sup 90}Y, and {sup 99}Tc was evaluated. It was determined that the sensor can measure the release limit of these radionuclides (50 pCi/cm{sup 3}) in 150 h, 200 h, and 54,000 h, respectively. The monitor is adequate for measuring {sup 137}Cs and {sup 90}Sr/{sup 90}Y but is unsuitable for measuring {sup 99}Tc in soil. The second objective was to construct a prototype sensor (dosimeter and fiber optic channel). There were three success criteria for this milestone: (1) Perform measurements with the sensor for both gamma and beta radiation with a standard deviation of 10% or less; (2) Demonstrate the ability of the sensor to discriminate between gamma and beta radiation; and (3) Obtain similar or relatable results for differing lengths of fiber optic cable. These milestones were met. The sensor was able to measure gamma radiation repeatedly with a standard deviation of 3.15% and beta radiation with a standard deviation of 2.85%. Data is presented that demonstrates that an end cap can be used to discriminate between beta plus gamma and gamma radiation. It is shown that some amount of attenuation occurs in longer fiber optic cables, but it is unclear if the attenuation is due to poor alignment of the dosimeter and the cable. This issue will be investigated further when more dosimeters are available so that the dosimeters can be permanently attached to the longer cables. The third objective was to identify a demonstration site. The success criterion for this milestone was to obtain a written agreement from a DOE site to host the demonstration of the monitor during the third phase. Because of uncertainties in funding of the second and third phases of this effort, a written agreement was not obtained. Instead, verbal agreements were reached with both Hanford and the Nevada Test Site. It is believed that the verbal agreements meet the intent of the objective. The final objective was to prepare the Draft Phase I Topical Report. The success criterion for this milestone was to have the report accepted by NETL. It is anticipated that this objective will be met.

  10. Using DRASTIC'' to improve the accuracy of a geographical information system used for solid waste disposal facility siting: A case study

    SciTech Connect (OSTI)

    Padgett, D.A. . Dept. of Geography)

    1993-01-01

    Beginning in 1989, the citizens and commissioners of Alachua County, Florida began to develop a siting plan for a new solid waste disposal facility (SWDF). Through a cooperative effort with a private consulting firm, several evaluative criteria were selected and then translated into parameters for a geographical information system (GIS). Despite efforts to avoid vulnerable hydrogeology, the preferred site selected was in close proximity to the well field supplying Gainesville, Florida, home to approximately 75 percent of the county's population. The results brought forth a wave of protests from local residents claiming that leachate from the proposed SWDF would contaminate their drinking water. In this study, DRASTIC'' was applied in order to improve the accuracy and defensibility of the aquifer protection-based GIS parameters. DRASTIC'', a method for evaluating ground water contamination potential, is an acronym which stands for Depth to Water, Net Recharge, Aquifer Media, Soil Media, Topography, Impact of Vadose Zone Media, and Conductivity (Hydraulic)''.

  11. Hazardous waste site assessment: Inactive landfill, Site 300, Lawrence Livermore National Laboratory

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    This report presents the results of an investigation of an inactive landfill (Pit 6) at Lawrence Livermore National Laboratory's (LLNL) Site 300. The primary objectives were to: collect and review background information pertaining to past waste disposal practices and previous environmental characterization studies; conduct a geophysical survey of the landfill area to locate the buried wastes; conduct a hydrogeologic investigation to provide additional data on the rate and direction of groundwater flow, the extent of any groundwater contamination, and to investigate the connection, if any, of the shallow groundwater beneath the landfill with the local drinking water supply; conduct a risk assessment to identify the degree of threat posed by the landfill to the public health and environment; compile a preliminary list of feasible long-term remedial action alternatives for the landfill; and develop a list of recommendations for any interim measures necessary at the landfill should the long-term remedial action plan be needed.

  12. Long-term management of AAR-affected structures - An international perspective

    SciTech Connect (OSTI)

    Charlwood, R.G.; Solymar, Z.V.

    1995-12-31

    The objective of the paper is to review international practice and comment on progress made in the long-term management of existing AAR-affected dams and hydroelectric plants. A updated detailed worldwide listing which now includes 104 AAR-affected structures constructed since 1900 will be presented. The listing gives summary data on the year of construction, the year that significant problems were noted, aggregate and cement types, measured expansion rates, test data, time to initial deterioration, duration of reaction, damage to the structures and effects on equipment, and repairs or replacement. A comprehensive bibliography will also be given. Analysis of the database and significant case histories will be used to identify issues affecting dam safety, plant operations, remedial measures and long-term performance of AAR-affected structures. The presentation will be illustrated by several case histories where remedial measures have been implemented.

  13. Test methods for determining short and long term VOC emissions from latex paint

    SciTech Connect (OSTI)

    Krebs, K.; Lao, H.C.; Fortmann, R.; Tichenor, B.

    1998-09-01

    The paper discusses an evaluation of latex paint (interior, water based) as a source of indoor pollution. A major objective of the research is the development of methods for predicting emissions of volatile organic compounds (VOCs) over time. Test specimens of painted gypsumboard are placed in dynamic flow-through test chambers. Samples of the outlet air are collected on Tenax sorbents and thermally desorbed for analysis by gas chromatography/flame ionization detection. These tests produce short- and long-term data for latex paint emissions of Texanol, 2-2(-butoxyethoxy)-ethanol, and glycols. Evaluation of the data shows that most of the Texanol emissions occur within the first few days, and emissions of the glycols occur over several months. This behavior may be described by an evaporative mass transfer process that dominates the short-term emissions, while long-term emissions are limited by diffusion processes within the dry paint-gypsumboard.

  14. Investigation of in-vivo skin autofluorescence lifetimes under long-term cw optical excitation

    SciTech Connect (OSTI)

    Lihachev, A; Ferulova, I; Vasiljeva, K; Spigulis, J

    2014-08-31

    The main results obtained during the last five years in the field of laser-excited in-vivo human skin photobleaching effects are presented. The main achievements and results obtained, as well as methods and experimental devices are briefly described. In addition, the impact of long-term 405-nm cw low-power laser excitation on the skin autofluorescence lifetime is experimentally investigated. (laser biophotonics)

  15. Physical Stability of Long-Term Surface Barriers-Assessment of Potentially Disruptive Natural Events

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

    ] a -" m HI BHI-00145 Rev. 00 Physical Stability of Long-Term Surface Barriers - Assessment of Potentially Disruptive Natural Events Authors N. R. Wing IT Hanford, Inc. F. M. Corpuz Bechtel Hanford, Inc. K. L. Petersen Pacific Northwest Laboratoy A. M. Tallman Westinghouse Hanford Company Date Published May 1995 HANFORD Prepared for the U.S. Department of Energy Office of Environmental Restoration and Waste Management Bechtel Hanford, Inc. Flichland, Washington Approved for Public Release .

  16. Glen Canyon Dam Long-Term Experimental and Management Plan DEIS

    Energy Savers [EERE]

    Executive Summary U.S. Department of the Interior Bureau of Reclamation, Upper Colorado Region National Park Service, Intermountain Region December 2015 Cover photo credits: Title bar: Grand Canyon National Park Grand Canyon: Grand Canyon National Park Glen Canyon Dam: T.R. Reeve High-flow experimental release: T.R. Reeve Fisherman: T. Gunn Humpback chub: Arizona Game and Fish Department Rafters: Grand Canyon National Park Glen Canyon Dam Long-Term Experimental and Management Plan December 2015

  17. Glen Canyon Dam Long-Term Experimental and Management Plan DEIS

    Energy Savers [EERE]

    Dam Long-Term Experimental and Management Plan Environmental Impact Statement PUBLIC DRAFT Volume 1-Chapters 1-8 U.S. Department of the Interior Bureau of Reclamation, Upper Colorado Region National Park Service, Intermountain Region December 2015 Cover photo credits: Title bar: Grand Canyon National Park Grand Canyon: Grand Canyon National Park Glen Canyon Dam: T.R. Reeve High-flow experimental release: T.R. Reeve Fisherman: T. Gunn Humpback chub: Arizona Game and Fish Department Rafters: Grand

  18. EIS-0480: Long-Term Experimental and Management Plan for the Operation of Glen Canyon Dam

    Broader source: Energy.gov [DOE]

    Two agencies of the Department of the Interior, Bureau of Reclamation and National Park Service, are jointly preparing a Long-Term Experimental and Management Plan for the Glen Canyon Dam and an EIS for adoption of the Plan. The Glen Canyon Dam, on the Colorado River in northern, Arizona, generates hydroelectric power that is marketed by DOE's Western Area Power Administration, a cooperating agency.

  19. NREL: Technology Deployment - NREL's Long-Term Relationship with GSA Stands

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

    the Test of Time NREL's Long-Term Relationship with GSA Stands the Test of Time News NREL Helps Federal Agencies Reach New Efficiency Targets Publications Plug-Load Control and Behavioral Change Research in GSA Office Buildings Sponsors U.S. General Services Administration Related Stories Strengthening Homeland Security through Sustainable Energy Alaska Native Village Benefits from Strategic Energy Planning Assistance U.S. Navy Yielding Valuable Results in Hawaii and Guam Fossil Fuel

  20. Assessment of Long-Term Research Needs for Coal-Liquefaction Technologies

    SciTech Connect (OSTI)

    Penner, S.S.

    1980-03-01

    The Fossil Energy Research Working Group (FERWG), at the request of J.M. Deutch (Under Secretary of DOE), E. Frieman (Director, Office of Energy Research) and G. Fumich, Jr. (Assistant Secretary for Fossil Fuels), has studied and reviewed currently funded coal-liquefaction technologies. These studies were performed in order to provide an independent assessment of critical research areas that affect the long-term development of coal-liquefaction technologies. This report summarizes the findings and research recommendations of FERWG.

  1. Assessment of Long-Term Research Needs for Shale-Oil Recovery (FERWG-III)

    SciTech Connect (OSTI)

    Penner, S.S.

    1981-03-01

    The Fossil Energy Research Working Group (FERWG), at the request of E. Frieman (Director, Office of Energy Research) and G. Fumich, Jr. (Assistant Secretary for Fossil Fuels), has reviewed and evaluated the U.S. programs on shale-oil recovery. These studies were performed in order to provide an independent assessment of critical research areas that affect the long-term prospects for shale-oil availability. This report summarizes the findings and research recommendations of FERWG.

  2. Catastrophic Incident Recovery: Long-Term Recovery from an Anthrax Event Symposium

    SciTech Connect (OSTI)

    Lesperance, Ann M.

    2008-06-30

    On March 19, 2008, policy makers, emergency managers, and medical and Public Health officials convened in Seattle, Washington, for a workshop on Catastrophic Incident Recovery: Long-Term Recovery from an Anthrax Event. The day-long symposium was aimed at generating a dialogue about restoration and recovery through a discussion of the associated challenges that impact entire communities, including people, infrastructure, and critical systems.

  3. Delamination Failures in Long-Term Field Aged PV Modules from Point of View

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

    Dehumidifiers -- v3.0 More Documents & Publications Beverage Vending Machines Metal Halide Lamp Ballasts and Fixtures Residential Dishwashers of Encapsulant | Department of Energy

    PowerPoint presentation was originally given by Tsuyoshi Shioda of Mitsui Chemicals, Inc. on Feb. 26, 2014 during the opening session of the 2013 NREL PV Module Reliability Workshop. It summarizes the study of long-term, field-aged photovoltaic modules with typical delamination failures from the point of

  4. X-ray enhancement and long-term evolution of swift J1822.31606

    SciTech Connect (OSTI)

    Benli, Onur; al??kan, ?.; Ertan, .; Alpar, M. A. [Sabanc? University, Orhanl?-Tuzla, ?stanbul 34956 (Turkey); Trmper, J. E. [Max-Planck-Institut fr extraterrestrische Physik, Geissenbachstrasse, 85740 Garching bei Mnchen (Germany); Kylafis, N. D., E-mail: onurbenli@sabanciuniv.edu [Physics Department and Institute of Theoretical and Computational Physics, University of Crete, 71003 Heraklion, Crete (Greece)

    2013-12-01

    We investigate the X-ray enhancement and the long-term evolution of the recently discovered second 'low-B magnetar' Swift J1822.3-1606 in the frame of the fallback disk model. During a soft gamma burst episode, the inner disk matter is pushed back to larger radii, forming a density gradient at the inner disk. Subsequent relaxation of the inner disk could account for the observed X-ray enhancement light curve of Swift J1822.3-1606. We obtain model fits to the X-ray data with basic disk parameters similar to those employed to explain the X-ray outburst light curves of other anomalous X-ray pulsars and soft gamma repeaters. The long period (8.4 s) of the neutron star can be reached by the effect of the disk torques in the long-term accretion phase ((1-3) 10{sup 5} yr). The currently ongoing X-ray enhancement could be due to a transient accretion epoch, or the source could still be in the accretion phase in quiescence. Considering these different possibilities, we determine the model curves that could represent the long-term rotational and the X-ray luminosity evolution of Swift J1822.3-1606, which constrain the strength of the magnetic dipole field to the range of (1-2) 10{sup 12} G on the surface of the neutron star.

  5. Long-Term Probability Distribution of Wind Turbine Planetary Bearing Loads (Poster)

    SciTech Connect (OSTI)

    Jiang, Z.; Xing, Y.; Guo, Y.; Dong, W.; Moan, T.; Gao, Z.

    2013-04-01

    Among the various causes of bearing damage and failure, metal fatigue of the rolling contact surface is the dominant failure mechanism. The fatigue life is associated with the load conditions under which wind turbines operate in the field. Therefore, it is important to understand the long-term distribution of the bearing loads under various environmental conditions. The National Renewable Energy Laboratory's 750-kW Gearbox Reliability Collaborative wind turbine is studied in this work. A decoupled analysis using several computer codes is carried out. The global aero-elastic simulations are performed using HAWC2. The time series of the drivetrain loads and motions from the global dynamic analysis are fed to a drivetrain model in SIMPACK. The time-varying internal pressure distribution along the raceway is obtained analytically. A series of probability distribution functions are then used to fit the long-term statistical distribution at different locations along raceways. The long-term distribution of the bearing raceway loads are estimated under different environmental conditions. Finally, the bearing fatigue lives are calculated.

  6. DEMONSTRATION OF LONG-TERM STORAGE CAPABILITY FOR SPENT NUCLEAR FUEL IN L BASIN

    SciTech Connect (OSTI)

    Sindelar, R.; Deible, R.

    2011-04-27

    The U.S. Department of Energy decisions for the ultimate disposition of its inventory of used nuclear fuel presently in, and to be received and stored in, the L Basin at the Savannah River Site, and schedule for project execution have not been established. A logical decision timeframe for the DOE is following the review of the overall options for fuel management and disposition by the Blue Ribbon Commission on America's Nuclear Future (BRC). The focus of the BRC review is commercial fuel; however, the BRC has included the DOE fuel inventory in their review. Even though the final report by the BRC to the U.S. Department of Energy is expected in January 2012, no timetable has been established for decisions by the U.S. Department of Energy on alternatives selection. Furthermore, with the imminent lay-up and potential closure of H-canyon, no ready path for fuel disposition would be available, and new technologies and/or facilities would need to be established. The fuel inventory in wet storage in the 3.375 million gallon L Basin is primarily aluminum-clad, aluminum-based fuel of the Materials Test Reactor equivalent design. An inventory of non-aluminum-clad fuel of various designs is also stored in L Basin. Safe storage of fuel in wet storage mandates several high-level 'safety functions' that would be provided by the Structures, Systems, and Components (SSCs) of the storage system. A large inventory of aluminum-clad, aluminum-based spent nuclear fuel, and other nonaluminum fuel owned by the U.S. Department of Energy is in wet storage in L Basin at the Savannah River Site. An evaluation of the present condition of the fuel, and the Structures, Systems, or Components (SSCs) necessary for its wet storage, and the present programs and storage practices for fuel management have been performed. Activities necessary to validate the technical bases for, and verify the condition of the fuel and the SSCs under long-term wet storage have also been identified. The overall conclusion is that the fuel can be stored in L Basin, meeting general safety functions for fuel storage, for an additional 50 years and possibly beyond contingent upon continuation of existing fuel management activities and several augmented program activities. It is concluded that the technical bases and well-founded technologies have been established to store spent nuclear fuel in the L Basin. Methodologies to evaluate the fuel condition and characteristics, and systems to prepare fuel, isolate damaged fuel, and maintain water quality storage conditions have been established. Basin structural analyses have been performed against present NPH criteria. The aluminum fuel storage experience to date, supported by the understanding of the effects of environmental variables on materials performance, demonstrates that storage systems that minimize degradation and provide full retrievability of the fuel up to and greater than 50 additional years will require maintaining the present management programs, and with the recommended augmented/additional activities in this report.

  7. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Snow, Mathew S.; Clark, Sue B.; Morrison, Samuel S.; Watrous, Matthew G.; Olson, John E.; Snyder, Darin C.

    2015-10-01

    Particulate transport represents an important mechanism for actinides and fission products at the Earth's surface; soil samples taken in the early 1970's near the Subsurface Disposal Area (SDA) at Idaho National Laboratory (INL) provide a case study for examining the mechanisms and characteristics of actinide transport under arid conditions. Transuranic waste was disposed via shallow land burial at the SDA until shortly after a flooding event that occurred in 1969. In this study we analyze soils collected in the early 1970's for ¹³⁷Cs, ²⁴¹Am, and Pu using a combination of radiometric and mass spectrometric techniques. Two distinct ²⁴⁰Pu/²³⁹Pu isotopic ratiosmore » are observed for contamination from the SDA, with values ranging from at least 0.059 to 0.069. ²⁴¹Am concentrations are observed to increase only slightly in 0-4 cm soils over the ~40 year period since soil sampling, contrary to Markham's previous hypothesis that ²⁴¹Pu is principally associated with the 0-4 cm soil fractions (Markham 1978). The lack of statistical difference in ²⁴¹Am/²³⁹⁺²⁴⁰Pu ratios with depth suggests mechanical transport and mixing discrete contaminated particles under arid conditions. Occasional samples beyond the northeastern corner are observed to contain anomalously high Pu concentrations with corresponding low ²⁴⁰Pu/²³⁹Pu atoms ratios, suggesting the occurrence of "hot particles;" application of a background Pu subtraction results in calculated Pu atom ratios for the "hot particles" which are statistically similar to those observed in the northeastern corner. Taken together, our data suggests that flooding resulted in mechanical transport of contaminated particles into the area between the SDA and the flood containment dike in the northeastern corner, following which subsequent contamination spreading resulted from wind transport of discrete particles.« less

  8. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site

    SciTech Connect (OSTI)

    Snow, Mathew S.; Clark, Sue B.; Morrison, Samuel S.; Watrous, Matthew G.; Olson, John E.; Snyder, Darin C.

    2015-10-01

    Particulate transport represents an important mechanism for actinides and fission products at the Earth's surface; soil samples taken in the early 1970's near the Subsurface Disposal Area (SDA) at Idaho National Laboratory (INL) provide a case study for examining the mechanisms and characteristics of actinide transport under arid conditions. Transuranic waste was disposed via shallow land burial at the SDA until shortly after a flooding event that occurred in 1969. In this study we analyze soils collected in the early 1970's for ¹³⁷Cs, ²⁴¹Am, and Pu using a combination of radiometric and mass spectrometric techniques. Two distinct ²⁴⁰Pu/²³⁹Pu isotopic ratios are observed for contamination from the SDA, with values ranging from at least 0.059 to 0.069. ²⁴¹Am concentrations are observed to increase only slightly in 0-4 cm soils over the ~40 year period since soil sampling, contrary to Markham's previous hypothesis that ²⁴¹Pu is principally associated with the 0-4 cm soil fractions (Markham 1978). The lack of statistical difference in ²⁴¹Am/²³⁹⁺²⁴⁰Pu ratios with depth suggests mechanical transport and mixing discrete contaminated particles under arid conditions. Occasional samples beyond the northeastern corner are observed to contain anomalously high Pu concentrations with corresponding low ²⁴⁰Pu/²³⁹Pu atoms ratios, suggesting the occurrence of "hot particles;" application of a background Pu subtraction results in calculated Pu atom ratios for the "hot particles" which are statistically similar to those observed in the northeastern corner. Taken together, our data suggests that flooding resulted in mechanical transport of contaminated particles into the area between the SDA and the flood containment dike in the northeastern corner, following which subsequent contamination spreading resulted from wind transport of discrete particles.

  9. Some considerations in the evaluation of concrete as a structural material for alternative LLW (low-level radioactive waste) disposal technologies

    SciTech Connect (OSTI)

    MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

    1987-01-01

    The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program characteristics of concrete useful in evaluating its performance and factors that can affect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, conditions for acceptance are recommended as an aid in the licensing of disposal sites which make use of alternative methods.

  10. Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units Nevada Test Site, Nevada, Rev. No.: 0 with ROTC 1 and 2

    SciTech Connect (OSTI)

    David A. Strand

    2004-05-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S Department of Defense (DoD). Corrective Action Unit 543 is located in Area 6 and Area 15 of the NTS, which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Seven corrective action sites (CASs) comprise CAU 543 and are listed below: (1) 06-07-01, Decon Pad; (2) 15-01-03, Aboveground Storage Tank; (3) 15-04-01, Septic Tank; (4) 15-05-01, Leachfield; (5) 15-08-01, Liquid Manure Tank; (6) 15-23-01, Underground Radioactive Material Area; and (7) 15-23-03, Contaminated Sump, Piping. Corrective Action Site 06-07-01, Decon Pad, is located in Area 6 and consists of the Area 6 Decontamination Facility and its components that are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency (EPA) Farm and are related to waste disposal activities at the EPA Farm. The EPA Farm was a fully-functional dairy associated with animal experiments conducted at the on-site laboratory. The corrective action investigation (CAI) will include field inspections, video-mole surveys, and sampling of media, where appropriate. Data will also be obtained to support waste management decisions. The CASs within CAU 543 are being investigated because hazardous and/or radioactive constituents may be present at concentrations that could potentially pose a threat to human health and the environment. The seven CASs in CAU 543 primarily consist of sanitary and process waste collection, storage, and distribution systems (e.g., storage tanks, sumps, and piping). Existing information on the nature and extent of potential contamination at these sites is insufficient to evaluate and recommend corrective action alternatives for the CASs. Therefore, additional information will be obtained by conducting a CAI prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS.

  11. Survey of university students` knowledge and views on nuclear waste disposal and the alternative dispute resolution process

    SciTech Connect (OSTI)

    Sheng, G.; Deffner, L.; Fiorini, S. [York Univ., North York, Ontario (Canada)

    1996-12-01

    The management of the high level radioactive waste is an issue which generates multifaceted conflicts. These conflicts are multi-determined, but are nonetheless, based on a myriad of associated concerns including but not exclusive to: effects of radiation on public health and safety, uncertainty associated with long-term assessments and effects, confidence in technology and in government and industry to protect public health and safety, and concerns regarding concurrent and intergenerational equity. These concerns are likely to be deeply felt by the many potential actors and stakeholders who will be impacted during the process of site selection for a nuclear waste disposal facility. Because this site selection is sure to be a controversial undertaking, it is in the interests of those who wish to promote the use of the high-level radioactive waste disposal concept, to understand fully the potential for conflict and consider alternative means of proactively preventing and/or resolving conflicts.

  12. Safety Assessment for the Kozloduy National Disposal Facility in Bulgaria - 13507

    SciTech Connect (OSTI)

    Biurrun, E.; Haverkamp, B.; Lazaro, A.; Miralles, A.; Stefanova, I.

    2013-07-01

    Due to the early decommissioning of four Water-Water Energy Reactors (WWER) 440-V230 reactors at the Nuclear Power Plant (NPP) near the city of Kozloduy in Bulgaria, large amounts of low and intermediate radioactive waste will arise much earlier than initially scheduled. In or-der to manage the radioactive waste from the early decommissioning, Bulgaria has intensified its efforts to provide a near surface disposal facility at Radiana with the required capacity. To this end, a project was launched and assigned in international competition to a German-Spanish consortium to provide the complete technical planning including the preparation of the Intermediate Safety Assessment Report. Preliminary results of operational and long-term safety show compliance with the Bulgarian regulatory requirements. The long-term calculations carried out for the Radiana site are also a good example of how analysis of safety assessment results can be used for iterative improvements of the assessment by pointing out uncertainties and areas of future investigations to reduce such uncertainties in regard to the potential radiological impact. The computer model used to estimate the long-term evolution of the future repository at Radiana predicted a maximum total annual dose for members of the critical group, which is carried to approximately 80 % by C-14 for a specific ingestion pathway. Based on this result and the outcome of the sensitivity analysis, existing uncertainties were evaluated and areas for reasonable future investigations to reduce these uncertainties were identified. (authors)

  13. Tritium: a model for low level long-term ionizing radiation exposure

    SciTech Connect (OSTI)

    Carsten, A.L.

    1984-01-01

    The somatic, cytogenetic and genetic effects of single and chronic tritiated water (HTO) ingestion in mice was investigated. This study serves not only as an evaluation of tritium toxicity (TRITOX) but due to its design involving long-term low concentration ingestion of HTO may serve as a model for low level long-term ionizing radiation exposure in general. Long-term studies involved animals maintained on HTO at concentrations of 0.3 ..mu..Ci/ml, 1.0 ..mu..Ci/ml, 3.0 ..mu..Ci/ml or depth dose equivalent chronic external exposures to /sup 137/Cs gamma rays. Maintenance on 3.0 ..mu..Ci/ml resulted in no effect on growth, life-time shortening or bone marrow cellularity, but did result in a reduction of bone marrow stem cells, an increase in DLM's in second generation animals maintained on this regimen and cytogenetic effects as indicated by increased sister chromatid exchanges (SCE's) in bone marrow cells, increased chromosome aberrations in the regenerating liver and an increase in micronuclei in red blood cells. Biochemical and microdosimetry studies showed that animals placed on the HTO regimen reached tritium equilibrium in the body water in approximately 17 to 21 days with a more gradual increase in bound tritium. When animals maintained for 180 days on 3.0 ..mu..Ci/ml HTO were placed on a tap water regimen, the tritium level in tissue dropped from the equilibrium value of 2.02 ..mu..Ci/ml before withdrawal to 0.001 ..mu..Ci/ml at 28 days. 18 references.

  14. SWAAM-LT: The long-term, sodium/water reaction analysis method computer code

    SciTech Connect (OSTI)

    Shin, Y.W.; Chung, H.H.; Wiedermann, A.H.; Tanabe, H.

    1993-01-01

    The SWAAM-LT Code, developed for analysis of long-term effects of sodium/water reactions, is discussed. The theoretical formulation of the code is described, including the introduction of system matrices for ease of computer programming as a general system code. Also, some typical results of the code predictions for available large scale tests are presented. Test data for the steam generator design with the cover-gas feature and without the cover-gas feature are available and analyzed. The capabilities and limitations of the code are then discussed in light of the comparison between the code prediction and the test data.

  15. LONG-TERM DEMONSTRATION OF SORBENT ENHANCEMENT ADDITIVE TECHNOLOGY FOR MERCURY CONTROL

    SciTech Connect (OSTI)

    Jason D. Laumb; Dennis L. Laudal; Grant E. Dunham; John P. Kay; Christopher L. Martin; Jeffrey S. Thompson; Nicholas B. Lentz; Alexander Azenkeng; Kevin C. Galbreath; Lucinda L. Hamre

    2011-05-27

    Long-term demonstration tests of advanced sorbent enhancement additive (SEA) technologies have been completed at five coal-fired power plants. The targeted removal rate was 90% from baseline conditions at all five stations. The plants included Hawthorn Unit 5, Mill Creek Unit 4, San Miguel Unit 1, Centralia Unit 2, and Hoot Lake Unit 2. The materials tested included powdered activated carbon, treated carbon, scrubber additives, and SEAs. In only one case (San Miguel) was >90% removal not attainable. The reemission of mercury from the scrubber at this facility prevented >90% capture.

  16. The long-term problems of contaminated land: Sources, impacts and countermeasures

    SciTech Connect (OSTI)

    Baes, C.F. III

    1986-11-01

    This report examines the various sources of radiological land contamination; its extent; its impacts on man, agriculture, and the environment; countermeasures for mitigating exposures; radiological standards; alternatives for achieving land decontamination and cleanup; and possible alternatives for utilizing the land. The major potential sources of extensive long-term land contamination with radionuclides, in order of decreasing extent, are nuclear war, detonation of a single nuclear weapon (e.g., a terrorist act), serious reactor accidents, and nonfission nuclear weapons accidents that disperse the nuclear fuels (termed ''broken arrows'').

  17. Improvement of capabilities of the Distributed Electrochemistry Modeling Tool for investigating SOFC long term performance

    SciTech Connect (OSTI)

    Gonzalez Galdamez, Rinaldo A.; Recknagle, Kurtis P.

    2012-04-30

    This report provides an overview of the work performed for Solid Oxide Fuel Cell (SOFC) modeling during the 2012 Winter/Spring Science Undergraduate Laboratory Internship at Pacific Northwest National Laboratory (PNNL). A brief introduction on the concept, operation basics and applications of fuel cells is given for the general audience. Further details are given regarding the modifications and improvements of the Distributed Electrochemistry (DEC) Modeling tool developed by PNNL engineers to model SOFC long term performance. Within this analysis, a literature review on anode degradation mechanisms is explained and future plans of implementing these into the DEC modeling tool are also proposed.

  18. Summary Notes from 5 March 2008 Generic Technical Issue Discussion on Long-Term Grout Performance

    Office of Environmental Management (EM)

    6, 2008 Page 1 of 6 Summary Notes from 5 March 2008 Generic Technical Issue Discussion on Long-Term Grout Performance Attendees: Representatives from Department of Energy-Headquarters (DOE-HQ) and the U.S. Nuclear Regulatory Commission staff (NRC) met at the DOE offices in Germantown, Maryland on 5 March 2008. Representatives from Department of Energy- Savannah River (DOE-SR), Department of Energy-Idaho (DOE-ID), Department of Energy-Richland (DOE-RL), Department of Energy-River Protection

  19. An Organophosphine Oxide Redox Shuttle Additive that Delivers Long-term

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

    Overcharge Protection for 4 V Lithium-ion Batteries - Joint Center for Energy Storage Research 4, 2015, Research Highlights An Organophosphine Oxide Redox Shuttle Additive that Delivers Long-term Overcharge Protection for 4 V Lithium-ion Batteries Organophosphine oxide groups not only can provide suitable steric protection of the generated radical cation, but also can increase the redox potential to 4.5 V, which is suitable for overcharge protection of LiMn2O4 cathode material Scientific

  20. Over 150years of long-term fertilization alters spatial scaling of microbial biodiversity

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Liang, Yuting; Wu, Liyou; Clark, Ian M.; Xue, Kai; Yang, Yunfeng; Van Nostrand, Joy D.; Deng, Ye; He, Zhili; McGrath, Steve; Storkey, Jonathan; et al

    2015-04-07

    Spatial scaling is a critical issue in ecology, but how anthropogenic activities like fertilization affect spatial scaling is poorly understood, especially for microbial communities. Here, we determined the effects of long-term fertilization on the spatial scaling of microbial functional diversity and its relationships to plant diversity in the 150-year-old Park Grass Experiment, the oldest continuous grassland experiment in the world. Nested samples were taken from plots with contrasting inorganic fertilization regimes, and community DNAs were analyzed using the GeoChip-based functional gene array. The slopes of microbial gene-area relationships (GARs) and plant species-area relationships (SARs) were estimated in a plot receivingmorenitrogen (N), phosphorus (P), and potassium (K) and a control plot without fertilization. Our results indicated that long-term inorganic fertilization significantly increased both microbial GARs and plant SARs. Microbial spatial turnover rates (i.e., z values) were less than 0.1 and were significantly higher in the fertilized plot (0.0583) than in the control plot (0.0449) (P z values also varied significantly with different functional genes involved in carbon (C), N, P, and sulfur (S) cycling and with various phylogenetic groups (archaea, bacteria, and fungi). Similarly, the plant SARs increased significantly (P less