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1

Site characterization handbook  

SciTech Connect

This Handbook discusses both management and technical elements that should be considered in developing a comprehensive site characterization program. Management elements typical of any project of a comparable magnitude and complexity are combined with a discussion of strategies specific to site characterization. Information specific to the technical elements involved in site characterization is based on guidance published by the Nuclear Regulatory Commission (NRC) with respect to licensing requirements for LLW disposal facilities. The objective of this Handbook is to provide a reference for both NRC Agreement States and non-Agreement States for use in developing a comprehensive site characterization program that meets the specific objectives of the State and/or site developer/licensee. Each site characterization program will vary depending on the objectives, licensing requirements, schedules/budgets, physical characteristics of the site, proposed facility design, and the specific concerns raised by government agencies and the public. Therefore, the Handbook is not a prescriptive guide to site characterization. 18 refs., 6 figs.

Not Available

1988-06-01T23:59:59.000Z

2

Site Characterization Awards | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Technology Centers Field Sites Power Marketing Administration Other Agencies You are here Home Site Characterization Awards Site Characterization Awards A description of...

3

DNAPL Site Characterization for Waste Management at Manufactured Gas Plant (MGP) Sites  

Science Conference Proceedings (OSTI)

Determining the optimal waste management strategy at manufactured gas plant (MGP) sites requires adequate site characterization to provide data for remediation decisions, a task that is particularly challenging when dense nonaqueous phase liquids (DNAPLs) are present. This report discusses development of an appropriate characterization strategy, including parameters that should be characterized, tools for characterization and the relation between characterization goals, a developing site conceptual model...

2004-12-22T23:59:59.000Z

4

Yucca Mountain Site Characterization Project technical data catalog; Yucca Mountain Site Characterization Project  

Science Conference Proceedings (OSTI)

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition.

NONE

1992-09-30T23:59:59.000Z

5

DOE Awards Small Business Contract for Site Characterization and Erosion  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Awards Small Business Contract for Site Characterization and DOE Awards Small Business Contract for Site Characterization and Erosion Control Work in Los Alamos, New Mexico DOE Awards Small Business Contract for Site Characterization and Erosion Control Work in Los Alamos, New Mexico September 30, 2013 - 12:00pm Addthis Media Contact Lynette Chafin, 513-246-0461 Lynette.Chafin@emcbc.doe.gov Cincinnati - The Department of Energy (DOE) today awarded a new contract to CTI & Associates, of Wixom, MI. CTI is a small business. The Department will issue a time and material type contract with a three year period of performance and a not-to-exceed value of $2,249,264. Work performed under this contract will be performed at the contractor's facilities and at the Los Alamos National Lab in Los Alamos, NM. The work performed under this contract includes site characterization and

6

DOE Awards Small Business Contract for Site Characterization and Erosion  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Characterization and Site Characterization and Erosion Control Work in Los Alamos, New Mexico DOE Awards Small Business Contract for Site Characterization and Erosion Control Work in Los Alamos, New Mexico September 30, 2013 - 12:00pm Addthis Media Contact Lynette Chafin, 513-246-0461 Lynette.Chafin@emcbc.doe.gov Cincinnati - The Department of Energy (DOE) today awarded a new contract to CTI & Associates, of Wixom, MI. CTI is a small business. The Department will issue a time and material type contract with a three year period of performance and a not-to-exceed value of $2,249,264. Work performed under this contract will be performed at the contractor's facilities and at the Los Alamos National Lab in Los Alamos, NM. The work performed under this contract includes site characterization and

7

DOE Awards Small Business Contract for Site Characterization...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Awards Small Business Contract for Site Characterization and Erosion Control Work in Los Alamos, New Mexico DOE Awards Small Business Contract for Site Characterization and...

8

Site Characterization Progress Report No.20  

Science Conference Proceedings (OSTI)

This is the 20th progress report issued by the U.S. Department of Energy. This report provides a summary-level discussion of Yucca Mountain Site Characterization Project progress. Accomplishments this period are presented in a format that identifies important progress achieved and conveys how that progress supports the near-term objectives in the U.S. Department of Energy's schedule. Greater detail is documented in the cited references and in deliverables listed in Appendix A to this report. Readers may request specific U.S. Department of Energy-approved program documents that are listed in Section 7, References, and Appendix A by contacting the Office of Civilian Radioactive Waste Management Information Line at 1-800-225-6972. This document provides a discussion of recently completed and ongoing activities conducted by the Yucca Mountain Site Characterization Project during the six-month reporting period from October 1, 1998, through March 31, 1999. Some information presented herein is by necessity preliminary, because some deliverables and reports that support the discussions have not been finalized. Projected future deliverables and reports are listed in Appendix B and are noted in the text as works in progress. Appendix C lists the status of milestone reports referenced in previous progress reports. A glossary of Yucca Mountain Site Characterization Project-specific terms used in this report is given in Appendix D.

DOE

1999-10-01T23:59:59.000Z

9

Site Characterization Work Plan for Gasbuggy, New Mexico  

SciTech Connect

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

DOE /NV

2000-12-14T23:59:59.000Z

10

Characterizations of Aircraft Icing Environments that Include Supercooled Large Drops  

Science Conference Proceedings (OSTI)

Measurements of aircraft icing environments that include supercooled large drops (SLD) greater than 50 ?m in diameter have been made during 38 research flights. These flights were conducted during the First and Third Canadian Freezing Drizzle ...

Stewart G. Cober; George A. Isaac; J. Walter Strapp

2001-11-01T23:59:59.000Z

11

Second ILAW Site Borehole Characterization Plan  

Science Conference Proceedings (OSTI)

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

SP Reidel

2000-08-10T23:59:59.000Z

12

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

SciTech Connect

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

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

1992-12-01T23:59:59.000Z

13

Hanford Site National Environmental Policy Act (NEPA) Characterization  

Science Conference Proceedings (OSTI)

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

Cushing, C.E. (ed.) [ed.

1992-12-01T23:59:59.000Z

14

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

Science Conference Proceedings (OSTI)

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

NONE

1988-12-01T23:59:59.000Z

15

Buildings characterization sampling plan, Weldon Spring Site  

SciTech Connect

The purpose of the Buildings Sampling Plan is to provide a systematic approach to characterizing radiological, asbestos and chemical contamination in and around the buildings and structures at the Weldon Spring Chemical Plant Site (WSCPS). This sampling plan reviews historical information; identifies data needs; and outlines sampling procedures, quality assurance, data documentation and reporting requirements for the buildings and equipment characterization at the Weldon Spring Site (WSS). The scope of this plan is limited to the buildings, structures, and equipment from the previous operation of the WSCPS. The Buildings Sampling Plan is divided into nine sections: introduction, background, data needs and sampling plan objectives, sampling rationale and procedure, sample analysis, quality assurance, data documentation, reporting requirements, and references. The data needs, sampling rationale and procedures and sample analysis sections of this work plan are subdivided into radiological, asbestos and chemical sections. Because different sampling techniques and analyses will be required for radiological, asbestos and chemical contamination, separate subsections are used. The investigations for each contaminant will be conducted independently. Similar historical and descriptive information is repeated in the subsections, but the perspective and information vary slightly. 24 refs., 5 figs., 14 tabs.

Not Available

1988-08-01T23:59:59.000Z

16

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

SciTech Connect

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

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

1995-09-01T23:59:59.000Z

17

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

SciTech Connect

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

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

1994-08-01T23:59:59.000Z

18

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

SciTech Connect

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

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

1997-08-01T23:59:59.000Z

19

SITE CHARACTERIZATION AND SELECTION GUIDELINES FOR GEOLOGICAL CARBON SEQUESTRATION  

SciTech Connect

Carbon capture and sequestration (CCS) is a key technology pathway to substantial reduction of greenhouse gas emissions for the state of California and the western region. Current estimates suggest that the sequestration resource of the state is large, and could safely and effectively accept all of the emissions from large CO2 point sources for many decades and store them indefinitely. This process requires suitable sites to sequester large volumes of CO2 for long periods of time. Site characterization is the first step in this process, and the state will ultimately face regulatory, legal, and technical questions as commercial CCS projects develop and commence operations. The most important aspects of site characterizations are injectivity, capacity, and effectiveness. A site can accept at a high rate a large volume of CO2 and store it for a long time is likely to serve as a good site for geological carbon sequestration. At present, there are many conventional technologies and approaches that can be used to estimate, quantify, calculate, and assess the viability of a sequestration site. Any regulatory framework would need to rely on conventional, easily executed, repeatable methods to inform the site selection and permitting process. The most important targets for long-term storage are deep saline formations and depleted oil and gas fields. The primary CO2 storage mechanisms for these targets are well understood enough to plan operations and simulate injection and long-term fate of CO2. There is also a strong understanding of potential geological and engineering hazards for CCS. These hazards are potential pathway to CO2 leakage, which could conceivably result in negative consequences to health and the environmental. The risks of these effects are difficult to quantify; however, the hazards themselves are sufficiently well understood to identify, delineate, and manage those risks effectively. The primary hazard elements are wells and faults, but may include other concerns as well. There is less clarity regarding the legal and regulatory issues around site characterization for large CCS injection volumes. In particular, it is not clear what would constitute due diligence for a potential selection and operation of a commercial site. This is complicated by a lack of clarity around permitting issues and subsurface ownership. However, there are many natural, industrial, regulatory, and legal analogs for these questions. However, solutions will need to evolve within the set of laws and practices current to the State. The chief conclusion of this chapter is that there is enough knowledge today to characterize a site for geological carbon sequestration safely and effective permitting and operation. From this conclusion and others flow a set of recommendations that represent potential actions for decision makers.

Friedmann, S J

2007-08-31T23:59:59.000Z

20

Microsoft Word - Site Characterization_ Awards 75.5M  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

75.5 million over three years. 75.5 million over three years. The work will be managed by the Office of Fossil Energy's National Energy Technology Laboratory. The projects selected under today's announcement include: ï‚· Board of Public Works (Holland, MI) - Focused Site Characterization for Carbon Dioxide Storage Along a Mt. Simon Sandstone Fairway in the Michigan Basin. The Board of Public Works will perform a focused site characterization for CO 2 storage along a Mt. Simon fairway in the Michigan Basin. The Mt. Simon Sandstone in southwestern Michigan represents one of the most significant formations for CO 2 storage in the Midwestern U.S. This work will focus on optimizing storage efficiency and developing regional CO 2 storage strategy for scaling up storage in the Mt. Simon.

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

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

SciTech Connect

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

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

1996-08-01T23:59:59.000Z

22

Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement  

Science Conference Proceedings (OSTI)

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

NONE

1994-03-31T23:59:59.000Z

23

Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement  

SciTech Connect

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

NONE

1994-12-31T23:59:59.000Z

24

Site characterization criteria (DOE-STD-1022-94) for natural phenomena hazards at DOE sites  

Science Conference Proceedings (OSTI)

This paper briefly summarizes requirements of site characterization for Natural Phenomena Hazards (NPH) at DOE sites. In order to comply with DOE Order 5480.28, site characterization criteria has been developed to provide site-specific information needed for development of NPH assessment criteria. Appropriate approaches are outlined to ensure that the current state-of-the-art methodologies and procedures are used in the site characterization. General and detailed site characterization requirements are provided in the areas of meteorology, hydrology, geology, seismology and geotechnical studies.

Chen, J.C.; Ueng, T.S.; Boissonnade, A.C.

1995-12-01T23:59:59.000Z

25

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

Science Conference Proceedings (OSTI)

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

NONE

1989-08-01T23:59:59.000Z

26

Hanford Site National Evnironmental Policy Act (NEPA) characterization  

Science Conference Proceedings (OSTI)

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

Cushing, C.E. (ed.) [ed.

1991-12-01T23:59:59.000Z

27

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

SciTech Connect

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

Cushing, C.E. [ed.

1991-12-01T23:59:59.000Z

28

A Multiattribute Utility Analysis of Sites Nominated For Characterization  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Multiattribute Utility Analysis of Sites Nominated For A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository - A Decision Aiding Methodology A Multiattribute Utility Analysis of Sites Nominated For Characterization For the First Radioactive Waste Repository - A Decision Aiding Methodology Summary In December 1984, the Department of Energy (DOE) published draft environmental assessments (EAs) to support the proposed nomination of five sites and the recommendation of three sites for characterization for the first radioactive-waste repository. A chapter common to all the draft EAs (Chapter 7) presented rankings of the five sites against the postclosure and the preclosure technical siting guidelines. To determine which three sites appeared most favorable for recommendation for characterization,

29

Recovery Act: Site Characterization of Promising Geologic Formations...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Recovery Act: Site Characterization of Promising Geologic Formations for CO2 Storage A Report on the The Department of Energy's (DOE's) Carbon Sequestration Program within the...

30

Mobile robotic surveying performance for planetary surface site characterization  

Science Conference Proceedings (OSTI)

Robotic systems will perform mobile surveys for scientific and engineering purposes as part of future missions on lunar and planetary surfaces. With site characterization as a task objective various system configurations and surveying techniques are ... Keywords: area coverage performance, in-situ remote sensing, planetary surface exploration, robotic surveying, site characterization

Edward Tunstel

2008-08-01T23:59:59.000Z

31

Site Characterization of Promising Geologic Formations for CO2 Storage |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Characterization of Promising Geologic Formations for CO2 Site Characterization of Promising Geologic Formations for CO2 Storage Site Characterization of Promising Geologic Formations for CO2 Storage In September 2009, the U.S. Department of Energy announced the award of 11 projects with a total project value of $75.5 million* to conduct site characterization of promising geologic formations for CO2 storage. These Recovery Act projects will increase our understanding of the potential for these formations to safely and permanently store CO2. The information gained from these projects (detailed below) will further DOE's efforts to develop a national assessment of CO2 storage capacity in deep geologic formations. Site Characterization of Promising Geologic Formations for CO2 Storage * Subsequently, the Board of Public Works project in Holland, MI has been

32

Site Characterization Plan: Uranium Stabilization through Polyphosphate Injection  

Science Conference Proceedings (OSTI)

An initial feasibility study of options to treat the uranium plume at the 300-FF-5 Operable Unit considered hydraulic containment, slurry wall containment, and groundwater extraction as potential remedial action technologies. None were selected for interim action, and reduction of contamination levels by natural processes was considered a viable alternative while source removal actions continued. Subsequent planning for a Phase III feasibility study focused on methods that would reduce the concentration of uranium in the aquifer, including multiple methods to immobilize uranium using chemical-based technologies. Based on an initial technology screening, the polyphosphate technology was identified as the best candidate to treat the for further evaluation and selected for treatability testing. The overall objective of the polyphosphate treatability test is to evaluate the efficacy of using polyphosphate injections to treat uranium contaminated groundwater in situ. The objective of the work elements included in this site characterization plan is to collect site-specific characterization data that will be needed to design and implement a field-scale demonstration of the technology.

Vermeul, Vince R.; Fruchter, Jonathan S.; Wellman, Dawn M.; Williams, Bruce A.; Williams, Mark D.

2006-12-01T23:59:59.000Z

33

Site hydrogeologic/geotechnical characterization report for Site B new municipal solid waste landfill  

Science Conference Proceedings (OSTI)

This Site Hydrogeologic/Geotechnical Characterization Report (SHCR) presents the results of a comprehensive study conducted on a proposed solid waste landfill site, identified herein as Site B, at the Savannah River Site (SRS). This report is intended to satisfy all requirements of the South Carolina Department of Health and Environmental Control (SCDHEC) with regard to landfill siting requirements and ground water and environmental protection. In addition, this report provides substantial geotechnical data pertinent to the landfill design process.

Reynolds, R.; Nowacki, P.

1991-04-01T23:59:59.000Z

34

Site characterization and hazard assessment criteria for natural phenomena hazards at DOE sites  

Science Conference Proceedings (OSTI)

This paper briefly summarizes requirements for site characterization and hazard assessment of Natural Phenomena Hazards for compliance with DOE Order 5480.28. The site characterization criteria for NPH evaluation are provided in a draft DOE-STD-1022-XX and the assessment criteria of natural phenomena hazards are provided in draft DOE-STD-1023-XX.

Chen, J.C.; Lu, S.C.; Ueng, T.S.; Boissonnade, A.C.

1993-09-01T23:59:59.000Z

35

International Symposium on Site Characterization for CO2Geological Storage  

SciTech Connect

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

Tsang, Chin-Fu

2006-02-23T23:59:59.000Z

36

Approach for tank safety characterization of Hanford site waste  

Science Conference Proceedings (OSTI)

The overall approach and associated technical basis for characterizing Hanford Site waste to help identify and resolve Waste Tank Safety Program safety issues has been summarized. The safety issues include flammable gas, noxious vapors, organic solvents, condensed-phase exothermic reactions (ferrocyanide and organic complexants), criticality, high heat, and safety screening. For the safety issues involving chemical reactions (i.e., flammable gas, organic solvents, ferrocyanide, and organic complexants), the approach to safety characterization is based on the fact that rapid exothermic reactions cannot occur if either fuel, oxidizer, or temperature (initiators) is not sufficient or controlled. The approach to characterization has been influenced by the progress made since mid-1993: (1) completion of safety analyses on ferrocyanide, criticality, organic solvent in tank 241-C-103, and sludge dryout. (2) successful mitigation of tank 241-SY-101; (3) demonstration of waste aging in laboratory experiments and from waste sampling, and (4) increased understanding of the information that can be obtained from headspace sampling. Headspace vapor sampling is being used to confirm that flammable gas does not accumulate in the single-shell tanks, and to determine whether organic solvents are present. The headspaces of tanks that may contain significant quantities of flammable gas will be monitored continuously using standard hydrogen monitors. For the noxious vapors safety issue, characterization will consist of headspace vapor sampling of most of the Hanford Site waste tanks. Sampling specifically for criticality is not required to confirm interim safe storage; however, analyses for fissile material will be conducted as waste samples are obtained for other reasons. High-heat tanks will be identified through temperature monitoring coupled with thermal analyses.

Meacham, J.E.; Babad, H.; Cash, R.J.; Dukelow, G.T.; Eberlein, S.J.; Hamilton, D.W.; Johnson, G.D.; Osborne, J.W.; Payne, M.A.; Sherwood, D.J. [and others

1995-03-01T23:59:59.000Z

37

Environmental Site Characterization and Remediation at Former Grain Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Applied Geosciences and Environmental Management (AGEM) Program Applied Geosciences and Environmental Management (AGEM) Program The EVS Applied Geosciences and Environmental Management (AGEM) program improves methods for characterizing and restoring environmental sites contaminated with carbon tetrachloride. For decades, the EVS Applied Geosciences and Environmental Management program has been improving methods for characterizing and restoring environmental sites contaminated with carbon tetrachloride. A key to our streamlined site characterization process is extensive use of cone penetrometer technology, with customized sampling and drilling tools, to minimize intrusiveness and the amount of hazardous waste generated. We have also improved analytical methods so that we can rapidly detect lower concentrations of contaminants and have developed methods for integrating

38

Characterization of active sites in zeolite catalysts  

DOE Green Energy (OSTI)

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Atomic-level details of the interaction of adsorbed molecules with active sites in catalysts are urgently needed to facilitate development of more effective and/or environmentally benign catalysts. To this end the authors have carried out neutron scattering studies combined with theoretical calculations of the dynamics of small molecules inside the cavities of zeolite catalysts. The authors have developed the use of H{sub 2} as a probe of adsorption sites by observing the hindered rotations of the adsorbed H{sub 2} molecule, and they were able to show that an area near the four-rings is the most likely adsorption site for H{sub 2} in zeolite A while adsorption of H{sub 2} near cations located on six-ring sites decreases in strength as Ni {approximately} Co > Ca > Zn {approximately} Na. Vibrational and rotational motions of ethylene and cyclopropane adsorption complexes were used as a measure for zeolite-adsorbate interactions. Preliminary studies of the binding of water, ammonia, and methylamines were carried out in a number of related guest-host materials.

Eckert, J. [Los Alamos National Lab., NM (United States); Bug, A. [Swarthmore Coll., PA (United States); Nicol, J.M. [MOLTECH (United States)] [and others

1997-11-01T23:59:59.000Z

39

Site characterization plan overview: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Consultation Draft  

SciTech Connect

The consultation draft of the site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site-characterization plan; it is not a substitute for the site-characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the disposal system -- the site, the repository, and the waste package -- preceding the discussion of the characterization program to be carried out at the Yucca Mountain site. It is intended primarily for the management staff of organizations involved in the DOE`s repository program -- staff who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 22 figs., 1 tab.

NONE

1988-01-01T23:59:59.000Z

40

Coupled Site Characterization and Foundation Analysis Research Project  

E-Print Network (OSTI)

Analysis Research Project: Rational Selection of for Drained-Strength Bearing Capacity Analysis Manhattan Research Project: Rational Selection of for Drained-Strength Bearing Capacity Analysis Manhattan CollegeCoupled Site Characterization and Foundation Analysis Research Project: Rational Selection

Horvath, John S.

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

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

SciTech Connect

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

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

1992-01-01T23:59:59.000Z

42

Characterization of the Hanford Site and environs  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) proposes to site, construct, and operate a new production reactor (NPR) intended to produce materials for the US nuclear weapons program. The DOE has determined that this proposed action constitutes an action that may significantly affect the quality of the human environment; therefore, the DOE is preparing an environmental impact statement (EIS) to assess the potential impacts of the proposed action and reasonable alternatives on the human and natural environment. The NPR-EIS is being prepared in accordance with Section 102(2)(C) of the National Environmental Policy Act of 1969 (NEPA), as implemented in regulations (40 CFR 1500--1508) promulgated by the Council on Environmental Quality (CEQ). Information on the potentially affected environment at the Hanford Site and its environs was provided to ANL by PNL in various submissions during CY-1989, and some of that information was consolidated into this report, which is considered to be supporting documentation for the NPR-EIS. 93 refs., 35 figs., 46 tabs.

Cushing, C.E. (ed.)

1991-03-01T23:59:59.000Z

43

Sitewide Categorical Exclusion for Site Characterization and Environmental Monitoring  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

.1 SWCX for Site Characterization and Environmental Monitoring- .1 SWCX for Site Characterization and Environmental Monitoring- Revision 0 Sitewide Categorical Exclusion for Site Characterization and Environmental Monitoring Introduction As defined in the U.S. Department of Energy's (DOE) Richland Operations Office L'ltegrated l\1anagement System Procedure, .._1\fEPA Analysis at Hanford, a sitewide categorical exclusion is: An application of DOE categorical exclusions described in 10 CFR 1021, Appendices A and B, which may apply to Hanford Site proposed actions (activities) that are "sitewide" in nature and extent, which the cognizant DOE Hanford NCO has determined fit within the scope (i.e., same nature and intent, and of the same or lesser scope) of DOE categorical exclusions described in 10 CFR 1021 Appendices A and B. The cognizant DOE Hanford NCO may issue specific sitewide

44

PISCES Water Characterization Field Study: Volume I: Site D Report; Volume II: Site D Appendix  

Science Conference Proceedings (OSTI)

In 1988, EPRI initiated the Power Plant Integrated System-Chemical Emissions Study (PISCES) project to characterize the distribution of trace substances in air, liquid, and solid waste streams from fossil-fuel-fired electric utility power plants. Studies have been completed at PISCES Sites A, B, and C. The results for PISCES Site D are presented in this report, which provides a comprehensive characterization of wastewater at a coal-fired power plant.

1998-11-18T23:59:59.000Z

45

PISCES Water Characterization Field Study: Volume I: Site D Report; Volume II: Site D Appendix  

Science Conference Proceedings (OSTI)

In 1988, EPRI initiated the Power Plant Integrated System-Chemical Emissions Study (PISCES) project to characterize the distribution of trace substances in air, liquid, and solid waste streams from fossil-fuel-fired electric utility power plants. Studies have been completed at PISCES Sites A, B, and C. The results for PISCES Site D are presented in this report, which provides a comprehensive characterization of wastewater at a coal-fired power plant.

1998-11-12T23:59:59.000Z

46

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

Science Conference Proceedings (OSTI)

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

NONE

1988-12-01T23:59:59.000Z

47

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

Science Conference Proceedings (OSTI)

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

NONE

1988-12-01T23:59:59.000Z

48

New 'Tool Box' Approaches for Innovative Characterization of NAPL at MGP Sites  

Science Conference Proceedings (OSTI)

This report contains papers presented at a workshop held by EPRI's Contaminant Characterization and Source Attribution project on June 23, 2004. The project seeks to improve risk management and decision making by delivering better methods and new scientific information for characterizing soils, non-aqueous phase liquids (NAPLs), and groundwater at manufactured gas plant (MGP) sites. This research will deliver improved conventional methods as well as new methods for characterizing NAPLs, including field a...

2004-12-27T23:59:59.000Z

49

Characterization Report for the David Witherspoon Screen Art Site  

SciTech Connect

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

Phyllis C. Weaver

2011-01-31T23:59:59.000Z

50

Tomographic Site Characterization Using CPT, ERT, and GPR  

SciTech Connect

The U.S. Department of Energy (DOE) is responsible for the cleanup of inactive DOE sites and for bringing DOE sites and facilities into compliance with federal, state and local laws and regulations. The DOE's Office of Environmental Management (EM) needs advanced technologies that can make environmental restoration and waste management operations more efficient and less costly. These techniques are required to better characterize the physical, hydrogeological, and chemical properties of the subsurface while minimizing and optimizing the use of boreholes and monitoring wells. Today the cone penetrometer technique (CPT) is demonstrating the value of a minimally invasive deployment system fix site characterization. Applied Research Associates is developing two new sensor packages for site characterization and monitoring. The two new methods are: . Electrical Resistivity Tomography (ERT) and . Ground Penetrating Radar (GPR) Tomography. These sensor systems are now integrated with the Cone Penetrometer Technique (CPT). The results of this program now make it possible to install ERT and GPR units by CPT methods and thereby reduce installation costs and total costs for ERT and GPR surveys. These two techniques can complement each other in regions of low resistivity where ERT is more effective and regions of high resistivity where GPR is more effective. The results show that CPT-installed GeoWells can be used in both ERT and GPR borehole tomographic subsurface imaging. These two imaging techniques can be used for environmental site characterization and environmental remediation monitoring. Technologies used for site characterization and monitoring have numerous and diverse applications within site clean-up and waste management operations.

Rexford M. Morey

1997-05-23T23:59:59.000Z

51

Soil characterization methods for unsaturated low-level waste sites  

SciTech Connect

To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies.

Wierenga, P.J.; Young, M.H. (Arizona Univ., Tucson, AZ (United States). Dept. of Soil and Water Science); Gee, G.W.; Kincaid, C.T. (Pacific Northwest Lab., Richland, WA (United States)); Hills, R.G. (New Mexico State Univ., Las Cruces, NM (United States). Dept. of Mechanical Engineering); Nicholson, T.J.; Cady, R.E. (Nuclear Regulatory Commission, Washington, DC (United States))

1993-01-01T23:59:59.000Z

52

Expedited Site Characterization Geophysics: Geophysical Methods and Tools for Site Characterization  

E-Print Network (OSTI)

storage and disposal of mixed waste. References Bendix Fieldwas tested by Sandia at the Mixed Waste Landfill Integratedtested over Sandia's mixed-waste landfill test site. Both

Goldstein, N.E.

2009-01-01T23:59:59.000Z

53

Teapot Dome: Site Characterization of a CO2- Enhanced Oil Recovery Site in Eastern Wyoming  

Science Conference Proceedings (OSTI)

Naval Petroleum Reserve No. 3 (NPR-3), better known as the Teapot Dome oil field, is the last U.S. federally-owned and -operated oil field. This provides a unique opportunity for experiments to provide scientific and technical insight into CO{sub 2}-enhanced oil recovery (EOR) and other topics involving subsurface fluid behavior. Towards that end, a combination of federal, academic, and industrial support has produced outstanding characterizations of important oil- and brine-bearing reservoirs there. This effort provides an unparalleled opportunity for industry and others to use the site. Data sets include geological, geophysical, geochemical, geomechanical, and operational data over a wide range of geological boundary conditions. Importantly, these data, many in digital form, are available in the public domain due to NPR-3's federal status. Many institutions are already using portions of the Teapot Dome data set as the basis for a variety of geoscience, modeling, and other research efforts. Fifteen units, 9 oil-bearing and 6 brine-bearing, have been studied to varying degrees. Over 1200 wells in the field are active or accessible, and over 400 of these penetrate 11 formations located below the depth that corresponds to the supercritical point for CO{sub 2}. Studies include siliciclastic and carbonate reservoirs; shale, carbonate, and anhydrite cap rocks; fractured and unfractured units; and over-pressured and under-pressured zones. Geophysical data include 3D seismic and vertical seismic profiles. Reservoir data include stratigraphic, sedimentological, petrologic, petrographic, porosity, and permeability data. These have served as the basis for preliminary 3D flow simulations. Geomechanical data include fractures (natural and drilling induced), in-situ stress determination, pressure, and production history. Geochemical data include soil gas, noble gas, organic, and other measures. The conditions of these reservoirs directly or indirectly represent many reservoirs in the U.S., Canada, and overseas.

Friedmann, S J; Stamp, V

2005-11-01T23:59:59.000Z

54

Characterization of the evolution of a news Web site  

Science Conference Proceedings (OSTI)

The Web has become a ubiquitous tool for distributing knowledge and information and for conducting businesses. To exploit the huge potential of the Web as a global information repository, it is necessary to understand its dynamics. These issues are particularly ... Keywords: Models of news Web sites, Web dynamics, characterization of Web content

Maria Carla Calzarossa; Daniele Tessera

2008-12-01T23:59:59.000Z

55

Coupled Site Characterization and Foundation Analysis Research Project  

E-Print Network (OSTI)

Coupled Site Characterization and Foundation Analysis Research Project: Further Research into the Rational Selection of for Bearing Capacity Analysis under Drained-Strength Conditions Manhattan College Research Report No. CE/GE-00-3 by John S. Horvath, Ph.D., P.E. Professor of Civil Engineering Manhattan

Horvath, John S.

56

Site characterization progress report: Yucca Mountain, Nevada, October 1, 1992--March 31, 1993, No. 8  

SciTech Connect

In accordance with requirements of Section 113(b)(3) of the Nuclear Waste Policy Act of 1982, as amended, and 10 CFR 60.18(g), the US Department of Energy has prepared this report on the progress of site characterization activities at Yucca Mountain, Nevada, for the period October 1, 1992, through March 31, 1993. This report is the eighth in a series issued at intervals of approximately six months during site characterization of Yucca Mountain as a possible site for a geologic repository for the permanent disposal of high-level radioactive waste. Also included in this report are activities such as public outreach and international programs that are not formally part of the site characterization process. Information on these activities is provided to report on all aspects of the Yucca Mountain studies.

NONE

1993-08-01T23:59:59.000Z

57

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

Science Conference Proceedings (OSTI)

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

NONE

1994-02-01T23:59:59.000Z

58

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

SciTech Connect

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

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

1998-09-01T23:59:59.000Z

59

Site characterization criteria (DOE-STD-1022-94) for natural phenomena hazards at DOE sites. Revision 1  

SciTech Connect

This paper briefly summarizes requirements of site characterization for Natural Phenomena Hazards (NPH) at DOE sites. In order to comply with DOE Order 5480.28, site characterization criteria has been developed to provide site-specific information needed for development of NPH assessment criteria. Appropriate approaches are outlined to ensure that the current state-of-the-art methodologies and procedures are used in the site characterization. General and detailed site characterization requirements are provided in the areas of meteorology, hydrology, geology, seismology and geotechnical studies.

Chen, J.C.; Ueng, Tzou-Shin; Boissonnade, A.C.

1995-03-23T23:59:59.000Z

60

Guidance for characterizing explosives contaminated soils: Sampling and selecting on-site analytical methods  

SciTech Connect

A large number of defense-related sites are contaminated with elevated levels of secondary explosives. Levels of contamination range from barely detectable to levels above 10% that need special handling due to the detonation potential. Characterization of explosives-contaminated sites is particularly difficult due to the very heterogeneous distribution of contamination in the environment and within samples. To improve site characterization, several options exist including collecting more samples, providing on-site analytical data to help direct the investigation, compositing samples, improving homogenization of samples, and extracting larger samples. On-site analytical methods are essential to more economical and improved characterization. On-site methods might suffer in terms of precision and accuracy, but this is more than offset by the increased number of samples that can be run. While verification using a standard analytical procedure should be part of any quality assurance program, reducing the number of samples analyzed by the more expensive methods can result in significantly reduced costs. Often 70 to 90% of the soil samples analyzed during an explosives site investigation do not contain detectable levels of contamination. Two basic types of on-site analytical methods are in wide use for explosives in soil, calorimetric and immunoassay. Calorimetric methods generally detect broad classes of compounds such as nitroaromatics or nitramines, while immunoassay methods are more compound specific. Since TNT or RDX is usually present in explosive-contaminated soils, the use of procedures designed to detect only these or similar compounds can be very effective.

Crockett, A.B. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Craig, H.D. [Environmental Protection Agency, Portland, OR (United States). Oregon Operations Office; Jenkins, T.F. [Army Cold Regions Research and Engineering Lab., Hanover, NH (United States); Sisk, W.E. [Army Environmental Center, Aberdeen Proving Grounds, MD (United States)

1996-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Proceedings: Site Characterization and Final Release Technology Workshop  

Science Conference Proceedings (OSTI)

This report presents the proceedings of an EPRI workshop on characterization and site release. The workshop was the third in a series initiated by EPRI to aid utility personnel in assessing technologies for decommissioning nuclear power plants. Each of the workshops focuses on a specific aspect of decommissioning, and presents information that will help utilities select technologies for their individual projects and reduce decommissioning costs.

1999-08-17T23:59:59.000Z

62

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

SciTech Connect

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

NONE

1994-10-01T23:59:59.000Z

63

Site characterization plan overview: Yucca Mountain site, Nevada Research and Development Area, Nevada  

SciTech Connect

To help the public better understand both the SCP and the site characterization program, the DOE has prepared this overview and the SCP Public Handbook. The overview presents summaries of selected topics covered in the SCP; it is not a substitute for the SCP. The organization of the overview is similar to that of the SCP itself, with brief descriptions of the Yucca Mountain site, the repository, and the containers in which the waste would be packaged, followed by a discussion of the characterization program to be carried out at the Yucca Mountain site. This overview is intended primarily for those persons who want to understand the general scope and basis of the site-characterization program, the activities to be conducted, and the facilities to be constructed without spending the time necessary to become familiar with all of the technical details presented in the SCP. For the readers of the SCP, the overview will be useful as a general guide to the plan. The SCP Public Handbook is a short document that contains brief descriptions of the SCP process and the contents of the SCP. It also explains how the public can submit comments on the SCP and lists the libraries and reading rooms at which the SCP is available. 9 refs., 18 tabs.

NONE

1988-12-01T23:59:59.000Z

64

Site characterization and monitoring data from Area 5 Pilot Wells, Nevada Test Site, Nye County, Nevada  

SciTech Connect

The Special Projects Section (SPS) of Reynolds Electrical & Engineering Co., Inc. (REECO) is responsible for characterizing the subsurface geology and hydrology of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division, Waste Operations Branch. The three Pilot Wells that comprise the Pilot Well Project are an important part of the Area 5 Site Characterization Program designed to determine the suitability of the Area 5 RWMS for disposal of low-level waste (LLW), mixed waste (MW), and transuranic waste (TRU). The primary purpose of the Pilot Well Project is two-fold: first, to characterize important water quality and hydrologic properties of the uppermost aquifer; and second, to characterize the lithologic, stratigraphic, and hydrologic conditions which influence infiltration, redistribution, and percolation, and chemical transport through the thick vadose zone in the vicinity of the Area 5 RWMS. This report describes Pilot Well drilling and coring, geophysical logging, instrumentation and stemming, laboratory testing, and in situ testing and monitoring activities.

NONE

1994-02-01T23:59:59.000Z

65

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

SciTech Connect

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

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

2002-01-14T23:59:59.000Z

66

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

Science Conference Proceedings (OSTI)

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

DOE /NV

2001-02-13T23:59:59.000Z

67

Site characterization progress report, Yucca Mountain, Nevada: Number 19, April 1, 1998--September 30, 1998  

Science Conference Proceedings (OSTI)

The nineteenth semiannual report of the Yucca Mountain Site Characterization Project (YMP) summarizes activities during the period from April 1, 1998, through September 30, 1998. Project activities are aimed at evaluating Yucca Mountain as a potential location for permanent geologic disposal of nuclear materials, as directed by the Nuclear Waste Policy Act of 1982, as amended (NWPA). The progress report documents activities this period that contribute to completing the Project`s near-term programmatic and statutory objectives. These objectives include completing the Viability Assessment, the Environmental Impact Statement (EIS), a possible US Department of Energy (DOE) Secretarial Site Recommendation to the President, and, if the site is suitable, submittal of a license application to the US Nuclear Regulatory Commission (NRC). Project work this period continued to be concentrated in three integrated activities: site characterization, engineering design and construction, and performance assessment. Accomplishments this period and their relation to near-term objectives are briefly summarized.

Not Available

1999-06-01T23:59:59.000Z

68

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

Science Conference Proceedings (OSTI)

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

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

2002-01-25T23:59:59.000Z

69

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

SciTech Connect

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

NONE

1997-10-01T23:59:59.000Z

70

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

SciTech Connect

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

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

1991-09-01T23:59:59.000Z

71

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

Science Conference Proceedings (OSTI)

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

Hogan, R.G. (ed.)

1981-03-01T23:59:59.000Z

72

NETL: EPAct Projects: Characterization of Potential Sites for Near Miscible  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization of Potential Sites for Near Miscible CO2 Applications to Improve Oil Recovery in Arbuckle Reservoirs Characterization of Potential Sites for Near Miscible CO2 Applications to Improve Oil Recovery in Arbuckle Reservoirs 09123-18 Primary Performer University of Kansas Center for Research, Inc. Additional Participants Tertiary Oil Recovery Project, University of Kansas Kansas Geological Survey Carmen Schmitt, Inc. Abstract Arbuckle reservoirs have significant potential in Kansas for Improved Oil Recovery (IOR). The Arbuckle has produced an estimated 2.2 billion barrels of oil representing 35% of the 6.1 billion barrels of oil of total Kansas oil production. Because of the characteristic production history, Arbuckle reservoirs have been viewed as fracture-controlled karstic reservoirs with strong pressure support from either a bottom water or edge water aquifer. A common practice of operation in Arbuckle reservoirs is to drill the well into the top of the zone with relative shallow penetration (under 10 feet) and complete open hole. No waterflooding application has been reported in these reservoirs in the published resources.

73

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect

This document describes the U.S. Department of Energy's (DOE) Hanford Site environment. It is updated each year and is intended to provide a consistent description of the Hanford Site environment for the many National Environmental Policy Act (NEPA) documents being prepared by DOE contractors. No conclusions or recommendations are provided. This year's report is the twelfth revision of the original document published in 1988 and is (until replaced by the thirteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. The two chapters included in this document (Chapters 4 and 6) are numbered to correspond to the chapters where such information is typically presented in environmental impact statements (EISs) and other Pacific Northwest National Laboratory (PNNL) NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology, geology, hydrology, ecology, cultural, archaeological, and historical resources, socioeconomic, occupational safety, and noise. Sources for extensive tabular data related to these topics are provided in the chapter. Most subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information, where available, of the 100, 200, 300, and other areas. This division allows the reader to go directly to those sections of particular interest. When specific information on each of these separate areas is not complete or available, the general Hanford Site description should be used. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to the NEPA documents prepared for Hanford Site activities. Information in Chapter 6 of this document can be adapted and supplemented with specific information for a chapter covering statutory and regulatory requirements in an environment assessment or environmental impact statement.

Neitzel, Duane A. (BATTELLE (PACIFIC NW LAB)); Antonio, Ernest J. (BATTELLE (PACIFIC NW LAB)); Fosmire, Christian J. (BATTELLE (PACIFIC NW LAB)); Fowler, Richard A. (BATTELLE (PACIFIC NW LAB)); Glantz, Clifford S. (BATTELLE (PACIFIC NW LAB)); Goodwin, Shannon M. (BATTELLE (PACIFIC NW LAB)); Harvey, David W. (BATTELLE (PACIFIC NW LAB)); Hendrickson, Paul L. (BATTELLE (PACIFIC NW LAB)); Horton, Duane G. (BATTELLE (PACIFIC NW LAB)); Poston, Ted M. (BATTELLE (PACIFIC NW LAB)); Rohay, Alan C. (BATTELLE (PACIFIC NW LAB)); Thorne, Paul D. (BATTELLE (PACIFIC NW LAB)); Wright, Mona K. (BATTELLE (PACIFIC NW LAB))

1999-12-01T23:59:59.000Z

74

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

Science Conference Proceedings (OSTI)

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

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

1981-09-01T23:59:59.000Z

75

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

SciTech Connect

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

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

2003-09-01T23:59:59.000Z

76

Hanford Site National Environmental Policy Act (NEPA) Characterization Report  

Science Conference Proceedings (OSTI)

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

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

2004-09-22T23:59:59.000Z

77

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect

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

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

2001-09-01T23:59:59.000Z

78

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect

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

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

2002-09-01T23:59:59.000Z

79

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect

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

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

1999-09-28T23:59:59.000Z

80

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

SciTech Connect

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

NONE

1988-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

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

Science Conference Proceedings (OSTI)

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

NONE

1988-01-01T23:59:59.000Z

82

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

Science Conference Proceedings (OSTI)

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

Stein, Joshua S.; Rautman, Christopher Arthur

2005-04-01T23:59:59.000Z

83

DOE Standard Natural Phenomena Hazards Site Characterization Criteria  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2-94 2-94 March 1994 Change Notice No. 1 January 1996 Reaffirmed with Errata April 2002 DOE STANDARD NATURAL PHENOMENA HAZARDS SITE CHARACTERIZATION CRITERIA U.S. Department of Energy AREA FACR Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Environment Safety and Health Technical Information Services, U.S. Department of Energy, (800) 473-4376, Fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. DOE-STD-1022-94 ERRATA FOR DOE-STD-1022-94 REVISED FOREWORD ADDED REFERENCE TO DOE G 420.1-2

84

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

Science Conference Proceedings (OSTI)

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

NONE

1988-01-01T23:59:59.000Z

85

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

Science Conference Proceedings (OSTI)

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

NONE

1988-01-01T23:59:59.000Z

86

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 6  

Science Conference Proceedings (OSTI)

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

NONE

1988-01-01T23:59:59.000Z

87

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

Science Conference Proceedings (OSTI)

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

NONE

1988-01-01T23:59:59.000Z

88

Hanford Site National Environmental Policy Act (NEPA) Characterization  

SciTech Connect

This document describes the U.S. Department of Energy’s (DOE) Hanford Site environment. It is intended to provide a consistent description of the Hanford Site for the many environmental documents being prepared by DOE contractors concerning the National Environmental Policy Act (NEPA). No statements regarding significance or environmental consequences are provided. This year’s report is the eighteen revision of the original document published in 1988 and is (until replaced by the nineteenth revision) the only version that is relevant for use in the preparation of Hanford NEPA, State Environmental Policy Act (SEPA), and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) documents. Two chapters are included in this document (Chapters 4 and 6), numbered to correspond to chapters typically presented in environmental impact statements (EISs) and other Hanford Site NEPA or CERCLA documentation. Chapter 4.0 (Affected Environment) describes Hanford Site climate and meteorology; air quality; geology; hydrology; ecology; cultural, archaeological, and historical resources; socioeconomics; noise; and occupational health and safety. Sources for extensive tabular data related to these topics are provided in the chapter. When possible, subjects are divided into a general description of the characteristics of the Hanford Site, followed by site-specific information, where available, for the 100, 200, 300 and other areas. This division allows the reader to go directly to those sections of particular interest. When specific information on each of these separate areas is not complete or available, the general Hanford Site description should be used. Chapter 6.0 (Statutory and Regulatory Requirements) describes federal and state laws and regulations, DOE directives and permits, and presidential executive orders that are applicable to NEPA documents prepared for Hanford Site activities. Information in Chapter 6 can be adapted and supplemented with specific information covering statutory and regulatory requirements for use in an environmental assessment or environmental impact statement. When preparing environmental assessments and EISs, authors should consult Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements published by the DOE Office of NEPA Oversight (DOE 2004). Additional direction and guidance on the preparation of DOE NEPA documents can be found at http://tis.eh.doe.gov/nepa/guidance.html. Individuals seeking baseline data on the Hanford Site and its past activities may also use the information contained in this document to evaluate projected activities and their impacts. Pacific Northwest National Laboratory (PNNL) staff prepared individual sections of this document, with input from other Hanford Site contractors with the best available information through May 2007. More detailed data are available from reference sources cited or from the authors. For this 2007 revision, the following sections of the document were reviewed by the authors and updated with the best available information through May 2005: Climate and Meteorology Air Quality Geology – Seismicity section only Hydrology – Flow charts for the Columbia and Yakima rivers only Ecology – Threatened and Endangered Species subsection only Socioeconomics Occupational Safety All of Chapter 6.

Duncan, Joanne P.; Burk, Kenneth W.; Chamness, Mickie A.; Fowler, Richard A.; Fritz, Brad G.; Hendrickson, Paul L.; Kennedy, Ellen P.; Last, George V.; Poston, Ted M.; Sackschewsky, Michael R.; Scott, Michael J.; Snyder, Sandra F.; Sweeney, Mark D.; Thorne, Paul D.

2007-09-27T23:59:59.000Z

89

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

SciTech Connect

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

Stephan, P.M. [ed.

1996-01-01T23:59:59.000Z

90

Three dimensional visualization in support of Yucca Mountain Site characterization activities  

SciTech Connect

An understanding of the geologic and hydrologic environment for the proposed high-level nuclear waste repository at Yucca Mountain, NV is a critical component of site characterization activities. Conventional methods allow visualization of geologic data in only two or two and a half dimensions. Recent advances in computer workstation hardware and software now make it possible to create interactive three dimensional visualizations. Visualization software has been used to create preliminary two-, two-and-a-half-, and three-dimensional visualizations of Yucca Mountain structure and stratigraphy. The three dimensional models can also display lithologically dependent or independent parametric data. Yucca Mountain site characterization studies that will be supported by this capability include structural, lithologic, and hydrologic modeling, and repository design.

Brickey, D.W.

1992-02-01T23:59:59.000Z

91

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

SciTech Connect

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

Stephan, P.M. [ed.

1995-01-01T23:59:59.000Z

92

Industrial Sites Work Plan for Leachfield Corrective Action Units: Nevada Test Site and Tonopah Test Range, Nevada (including Record of Technical Change Nos. 1, 2, 3, and 4)  

SciTech Connect

This Leachfield Corrective Action Units (CAUs) Work Plan has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the U.S. Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the U.S. Department of Defense (FFACO, 1996). Under the FFACO, a work plan is an optional planning document that provides information for a CAU or group of CAUs where significant commonality exists. A work plan may be developed that can be referenced by leachfield Corrective Action Investigation Plans (CAIPs) to eliminate redundant CAU documentation. This Work Plan includes FFACO-required management, technical, quality assurance (QA), health and safety, public involvement, field sampling, and waste management documentation common to several CAUs with similar site histories and characteristics, namely the leachfield systems at the Nevada Test Site (NTS) and the Tonopah Test Range (TT R). For each CAU, a CAIP will be prepared to present detailed, site-specific information regarding contaminants of potential concern (COPCs), sampling locations, and investigation methods.

DOE /NV

1998-12-18T23:59:59.000Z

93

Design, Fabrication and Characterization of a Piezoelectric Microgenerator Including a Power Management Circuit  

E-Print Network (OSTI)

We report in this paper the design, fabrication and experimental characterization of a piezoelectric MEMS microgenerator. This device scavenges the energy of ambient mechanical vibrations characterized by frequencies in the range of 1 kHz. This component is made with Aluminum Nitride thin film deposited with a CMOS compatible process. Moreover we analyze two possible solutions for the signal rectification: a discrete doubler-rectifier and a full custom power management circuit. The ASIC developed for this application takes advantage of diodes with very low threshold voltage and therefore allows the conversion of extremely low input voltages corresponding to very weak input accelerations. The volume of the proposed generator is inferior to 1mm3 and the generated powers are in the range of 1$\\mu$W. This system is intended to supply power to autonomous wireless sensor nodes.

Marzencki, M; Basrour, S

2008-01-01T23:59:59.000Z

94

DESIGN, FABRICATION AND CHARACTERIZATION OF A PIEZOELECTRIC MICROGENERATOR INCLUDING A POWER MANAGEMENT CIRCUIT  

E-Print Network (OSTI)

We report in this paper the design, fabrication and experimental characterization of a piezoelectric MEMS microgenerator. This device scavenges the energy of ambient mechanical vibrations characterized by frequencies in the range of 1 kHz. This component is made with Aluminum Nitride thin film deposited with a CMOS compatible process. Moreover we analyze two possible solutions for the signal rectification: a discrete doubler-rectifier and a full custom power management circuit. The ASIC developed for this application takes advantage of diodes with very low threshold voltage and therefore allows the conversion of extremely low input voltages corresponding to very weak input accelerations. The volume of the proposed generator is inferior to 1mm 3 and the generated powers are in the range of 1µW. This system is intended to supply power to autonomous wireless sensor nodes. 1.

M. Marzencki; Y. Ammar; S. Basrour

2008-01-01T23:59:59.000Z

95

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

SciTech Connect

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

NONE

1988-12-01T23:59:59.000Z

96

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 4, Part B: Chapter 8, Sections 8.0 through 8.3.1.4  

Science Conference Proceedings (OSTI)

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 74 figs., 32 tabs.

NONE

1988-12-01T23:59:59.000Z

97

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

SciTech Connect

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

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

1989-07-01T23:59:59.000Z

98

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

SciTech Connect

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

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

2006-06-01T23:59:59.000Z

99

International Symposium on Site Characterization for CO2 Geological Storage  

E-Print Network (OSTI)

SMALL SCALE FEATURES INTRODUCTION Seismic attribute technology is a standard reservoir characterization component for assessment of hydro-

Tsang, Chin-Fu

2006-01-01T23:59:59.000Z

100

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

Science Conference Proceedings (OSTI)

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

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

1998-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Data Summary Report for Hanford Site Coal Ash Characterization  

Science Conference Proceedings (OSTI)

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

Sulloway, H. M.

2012-03-06T23:59:59.000Z

102

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

SciTech Connect

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

NONE

1992-08-01T23:59:59.000Z

103

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

SciTech Connect

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

1995-03-01T23:59:59.000Z

104

A vehicle mounted multi-sensor array for waste site characterization  

Science Conference Proceedings (OSTI)

Personnel at AlliedSignal Aerospace, Kirtland Operations (formerly EG&G Energy Measurements, Kirtland Operations) and EG&G Energy Measurements, Los Alamos Operations, have successfully developed and demonstrated a number of technologies which can be applied to the environmental remediation and waste management problem. These applications have included the development of self-contained and towed remote sensing platforms and advanced signal analysis techniques for the detection and characterization of subsurface features. This presentation will provide a brief overview of applications that have been and are currently being fielded by both AlliedSignal and EG&G Energy Measurements personnel and will describe some of the ways that such technologies can and are being used for the detection and characterization of hazardous waste sites.

Baumgart, C.W. [AlliedSignal, Kansas City, KS (United States); Ciarcia, C.A.; Tunnell, T.W. [EG& G Energy Measurements, Inc., Los Alamos, NM (United States)

1995-02-01T23:59:59.000Z

105

International Symposium on Site Characterization for CO2 Geological Storage  

E-Print Network (OSTI)

southern oil fields of Fortescue, Kingfish and Bream (FigureThe second site is the Fortescue Field area, also for 15 Mt/For the Kingfish and Fortescue field areas, the con- cept

Tsang, Chin-Fu

2006-01-01T23:59:59.000Z

106

International Symposium on Site Characterization for CO2 Geological Storage  

E-Print Network (OSTI)

fracture characterization in a shale reservoir, North Texas,of intra- aquifer shales and the relative effectiveness ofgreat degree of sandstone/shale inter- beds in channel-fill

Tsang, Chin-Fu

2006-01-01T23:59:59.000Z

107

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

DOE Green Energy (OSTI)

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

None

1980-12-01T23:59:59.000Z

108

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

SciTech Connect

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

None

1982-11-01T23:59:59.000Z

109

Site characterization progress report: Yucca Mountain, Nevada, October 1, 1990--March 31, 1991; Number 4  

Science Conference Proceedings (OSTI)

In accordance with the requirements of Section 113 (b) (3) of the Nuclear Waste Policy Act of 1982, as amended (NWPA), the US Department of Energy (DOE) has prepared this report on the progress of site characterization activities at Yucca Mountain, Nevada, for the period October 1, 1990, through March 31, 1991. This report is the fourth in a series of reports that are issued at intervals of approximately six months during site characterization. The report covers a number of initiatives to improve the effectiveness of the site characterization program, and covers continued efforts related to preparatory activities, Study Plans, and performance assessment.

NONE

1991-10-01T23:59:59.000Z

110

Guide for Characterization of Sites Contaminated with Energetic Materials  

E-Print Network (OSTI)

for the remediation of federal facility sites contaminated with explosives or radioactive wastes. EPA/625/R-93 be contaminated by EM: · Firing ranges - Small-arms ranges - Artillery ranges - Anti-tank ranges - Tank/013. EPA Method (1994) Nitroaromatics and nitramines by HPLC. In Test Methods for Evaluating Solid Waste

111

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

Science Conference Proceedings (OSTI)

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

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

2003-02-25T23:59:59.000Z

112

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

Science Conference Proceedings (OSTI)

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

NONE

1992-06-01T23:59:59.000Z

113

Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada: Revision 0, Including Errata Sheet  

Science Conference Proceedings (OSTI)

This Corrective Action Decision Document identifies the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's corrective action alternative recommendation for each of the corrective action sites (CASs) within Corrective Action Unit (CAU) 204: Storage Bunkers, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. An evaluation of analytical data from the corrective action investigation, review of current and future operations at each CAS, and a detailed comparative analysis of potential corrective action alternatives were used to determine the appropriate corrective action for each CAS. There are six CASs in CAU 204, which are all located between Areas 1, 2, 3, and 5 on the NTS. The No Further Action alternative was recommended for CASs 01-34-01, 02-34-01, 03-34-01, and 05-99-02; and a Closure in Place with Administrative Controls recommendation was the preferred corrective action for CASs 05-18-02 and 05-33-01. These alternatives were judged to meet all requirements for the technical components evaluated as well as applicable state and federal regulations for closure of the sites and will eliminate potential future exposure pathways to the contaminated media at CAU 204.

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

2004-04-01T23:59:59.000Z

114

Corrective Action Investigation Plan for Corrective Action Unit 536: Area 3 Release Site, Nevada Test Site, Nevada (Rev. 0 / June 2003), Including Record of Technical Change No. 1  

Science Conference Proceedings (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 536: Area 3 Release Site, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 536 consists of a single Corrective Action Site (CAS): 03-44-02, Steam Jenny Discharge. The CAU 536 site is being investigated because existing information on the nature and extent of possible contamination is insufficient to evaluate and recommend corrective action alternatives for CAS 03-44-02. The additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating CAAs and selecting the appropriate corrective action for this CAS. The results of this field investigation are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3-2004.

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

2003-06-27T23:59:59.000Z

115

Engineering Characterization of Strong Ground Motion Recorded at Rock Sites  

Science Conference Proceedings (OSTI)

The objective of this project is to define the engineering characteristics of strong ground motion recorded at rock sites. Particular emphasis is placed upon resolving the factors that control the shape of response spectra in both WNA (western North America) and ENA (central and eastern North America) tectonic environments. To accomplish this objective, a simple band-limited white noise (BLWN) ground motion model employing a constant-stress-drop, single-corner-frequency, omega-square source combined with...

1995-08-17T23:59:59.000Z

116

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

Science Conference Proceedings (OSTI)

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

NONE

1992-12-01T23:59:59.000Z

117

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

SciTech Connect

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

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

1986-12-01T23:59:59.000Z

118

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

SciTech Connect

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

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

2002-02-26T23:59:59.000Z

119

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

SciTech Connect

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

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

1993-12-01T23:59:59.000Z

120

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

SciTech Connect

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

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

2002-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

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

SciTech Connect

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

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

2002-02-27T23:59:59.000Z

122

Review of geophysical characterization methods used at the Hanford Site  

SciTech Connect

This paper presents a review of geophysical methods used at Hanford in two parts: (1) shallow surface-based geophysical methods and (2) borehole geophysical methods. This review was not intended to be ``all encompassing'' but should represent the vast majority (>90% complete) of geophysical work conducted onsite and aimed at hazardous waste investigations in the vadose zone and/or uppermost groundwater aquifers. This review did not cover geophysical methods aimed at large-scale geologic structures or seismicity and, in particular, did not include those efforts conducted in support of the Basalt Waste Isolation Program. This review focused primarily on the more recent efforts.

GV Last; DG Horton

2000-03-23T23:59:59.000Z

123

Audit of the Richland Operations Office Site Characterization Program, IG-0368  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0, 1995 0, 1995 IG-1 INFORMATION: Report on "Audit of the Richland Operations Office Site Characterization Program" The Secretary BACKGROUND: With its designation as an environmental cleanup site in 1989, the Hanford Site has represented a major activity of the Department of Energy (Department). The final cleanup of this site is estimated to take over 50 years and cost close to $100 billion. Although there are many factors influencing the operations at Hanford, the Department and the Richland Operations Office (Richland) are ultimately responsible for its success. The Department and Richland are responsible for establishing procedures that ensure program goals are accomplished using the most cost-effective methods. DISCUSSION:

124

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

SciTech Connect

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

Bechtel Nevada Geotechnical Sciences

2005-06-01T23:59:59.000Z

125

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

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

126

Post-decontamination and dismantlement (D&D) characterization report for CFA-669 site  

SciTech Connect

This report presents results of post-decontamination and dismantling (D&D) characterization surveys performed by EG&G Idaho, Inc. (EG&G Idaho), at Central Facilities Area (CFA)-669, which was the Hot Laundry Facility. The site was characterized to determine and document the radiological and chemical conditions of the site following D&D and to determine if the site satisfies the release criteria. Constructed in 1950, CFA-669 served as the ``hot`` and ``cold`` laundry for Idaho National Engineering Laboratory site contractors until the boiler exploded in 1981. The building was shut down at that time. Before D&D activities began in 1992, the facility was characterized and the results documented. D&D activities were completed in July 1994. The post-D&D radiological characterization consisted of radiation measurements and analyses of soil samples to identify man-made radionuclides and determine the specific activity of each sample. The chemical characterization consisted of toxicity characterization leaching procedure (TCLP) analysis for metals and for volatile and semivolatile organic contamination.

Smith, D.L. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-01-01T23:59:59.000Z

127

Evaluation of the effects of underground water usage and spillage in the Exploratory Studies Facility; Yucca Mountain Site Characterization Project  

SciTech Connect

The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level radioactive waste repository. Analyses reported herein were performed to support the design of site characterization activities so that these activities will have a minimal impact on the ability of the site to isolate waste and a minimal impact on underground tests performed as part of the characterization process. These analyses examine the effect of water to be used in the underground construction and testing activities for the Exploratory Studies Facility on in situ conditions. Underground activities and events where water will be used include construction, expected but unplanned spills, and fire protection. The models used predict that, if the current requirements in the Exploratory Studies Facility Design Requirements are observed, water that is imbibed into the tunnel wall rock in the Topopah Springs welded tuff can be removed over the preclosure time period by routine or corrective ventilation, and also that water imbibed into the Paintbrush Tuff nonwelded tuff will not reach the potential waste storage area.

Dunn, E.; Sobolik, S.R.

1993-12-01T23:59:59.000Z

128

Occupational Exposure Evaluation of Complex Vapor Mixtures at the Hanford Nuclear Waste Site, Washington Work-site Vapor Characterization  

SciTech Connect

Extensive sampling and analysis has been done over the years to characterize the radioactive and chemical properties of hazardous waste stored in 177 underground tanks at the Hanford site in eastern Washington State. The purpose of these analyses was to evaluate safety and environmental concerns related to tank stability. More recently, characterization studies have broadened to evaluate potential health hazards of chemical vapors at the ground surface, where workers perform maintenance and waste transfer activities. Chemical vapor emissions from underground hazardous waste storage tanks on the Hanford site are a potential concern because workers enter the tank farms on a regular basis for waste retrievals, equipment maintenance, and surveillance. The extensive sampling done during this campaign evaluated vapor concentrations of more than 100 different chemical at 70 sites in and around one section of the tank farms. Sampling identified only four vapors (ammonia, nitrous oxide, nitrosodimethylamine, and nitrosomethylethylamine) that were present above occupational exposure limits. These elevated concentrations were detected only at exhaust stacks and passive breather filter outlets. Beyond five feet from the sources, vapors disperse rapidly. No vapors were measured above 10% of their OELs more than five feet from the source. This suggests that vapor controls can be focused on limited hazard zones around sources. (authors)

Anderson, T. J. [CH2M HILL Hanford Group, Inc. / Environmental Health, P.O. Box 1000, S7-70, Richland, WA 99352 (United States)

2006-07-01T23:59:59.000Z

129

Audit of Management of the Site Characterization Program at Yucca Mountain, IG-0366  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5, 1995 5, 1995 IG-1 INFORMATION: "Audit of Management of the Site Characterization Program at Yucca Mountain" The Secretary BACKGROUND: The Department of Energy (Department) is responsible for establishing an underground repository to store high-level nuclear waste. In accordance with the amended Nuclear Waste Policy Act of 1982, the Department began characterization of the Yucca Mountain site to assess the feasibility of safely storing spent fuel and high-level waste for 10,000 years. Site characterization was originally scheduled to be completed in 1995. Subsequently, the Secretary of Energy changed the plan completion date to 2001. The purpose of our audit was to determine if the Department is making adequate progress in

130

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

SciTech Connect

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

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

2006-01-01T23:59:59.000Z

131

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

SciTech Connect

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

NONE

1992-01-01T23:59:59.000Z

132

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

SciTech Connect

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

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

1983-01-01T23:59:59.000Z

133

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

Science Conference Proceedings (OSTI)

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

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

2002-08-08T23:59:59.000Z

134

Seismic Hazard Characterization at the DOE Savannah River Site (SRS): Status report  

Science Conference Proceedings (OSTI)

The purpose of the Seismic Hazard Characterization project for the Savannah River Site (SRS-SHC) is to develop estimates of the seismic hazard for several locations within the SRS. Given the differences in the geology and geotechnical characteristics at each location, the estimates of the seismic hazard are to allow for the specific local conditions at each site. Characterization of seismic hazard is a critical factor for the design of new facilities as well as for the review and potential retrofit of existing facilities at SRS. The scope of the SRS seismic hazard characterization reported in this document is limited to the Probabilistic Seismic Hazard Analysis (PSHA). The goal of the project is to provide seismic hazard estimates based on a state-of-the-art method which is consistent with developments and findings of several ongoing studies which are deemed to bring improvements in the state of the seismic hazard analyses.

Savy, J.B.

1994-06-24T23:59:59.000Z

135

Site characterization progress report: Yucca Mountain, Nevada, April 1, 1991--September 30, 1991, Number 5; Nuclear Waste Policy Act (Section 113)  

SciTech Connect

The Site Characterization Progress Report of Yucca Mountain (PR) presents brief summaries of the status of site characterization activities and cites the technical reports and research products that provide more detailed information on the activities. The report provides highlights of work started during the reporting period, work in progress, and work completed and documented during the reporting period. In addition, the report is the vehicle for the discussion of changes to the DOE`s site characterization program resulting from ongoing collection and evaluation of site information; the development of repository and waste-package designs; the results of performance assessments; and any changes that occur in response to external comments. Information covered includes geochemistry, hydrology, geology, climate, and radiation dose estimate calculations.

NONE

1992-06-01T23:59:59.000Z

136

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

DOE Green Energy (OSTI)

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

None

1980-12-01T23:59:59.000Z

137

Autoradiographic localization and characterization of atrial natriuretic peptide binding sites in the rat central nervous system and adrenal gland  

SciTech Connect

Atrial natriuretic peptides (ANP) have recently been identified in both heart and CNS. These peptides possess potent natriuretic, diuretic, and vasorelaxant activities, and are all apparently derived from a single prohormone. Specific ANP binding sites have been characterized in the adrenal zona glomerulosa and kidney cortex, and one study reported ANP binding sites in the CNS. However, a detailed examination of the localization of ANP binding sites throughout the brain has not been reported. In this study, quantitative autoradiography was employed to examine the distribution of ANP receptors in the rat CNS. The binding of (3-/sup 125/I-iodotyrosyl28) rat ANP-28 to binding sites in the rat CNS was saturable, specific for ANP-related peptides, and displayed high affinity (Kd = 600 pM). When the relative concentrations of ANP binding sites were determined throughout the rat brain, the highest levels of ANP binding were localized to the circumventricular organs, including the area postrema and subfornical organ, and the olfactory apparatus. Moderate levels of ANP binding sites were present throughout the midbrain and brain stem, while low levels were found in the forebrain, diencephalon, basal ganglia, cortex, and cerebellum. The presence of ANP binding sites in the subfornical organ and the area postrema, regions considered to be outside the blood-brain barrier, suggests that peripheral ANP levels may regulate some aspects of CNS control of salt and water balance. The possible functions of ANP binding sites in other regions of the rat brain are not known, but, like many other peptides, ANP may act as a neurotransmitter or neuromodulator at these loci.

Gibson, T.R.; Wildey, G.M.; Manaker, S.; Glembotski, C.C.

1986-07-01T23:59:59.000Z

138

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

Science Conference Proceedings (OSTI)

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

Goranson, C.

1992-09-01T23:59:59.000Z

139

Los Alamos National Laboratory Yucca Mountain Site Characterization Project 1992 quality program status report  

SciTech Connect

This status report summarizes the activities and accomplishments of the Los Alamos Yucca Mountain Site Characterization Project`s quality assurance program for calendar year 1992. The report includes major sections on Program Activities and Trend Analysis. Program Activities are discussed periodically at quality meetings. The most significant issue addressed in 1992 has been the timely revision of quality administrative procedures. The procedure revision process was streamlined from 55 steps to 7. The number of forms in procedures was reduced by 38%, and the text reduced by 29%. This allowed revision in 1992 of almost half of all implementing procedures. The time necessary to complete the revision process (for a procedure) was reduced from 11 months to 3 months. Other accomplishments include the relaxation of unnecessarily strict training requirements, requiring quality assurance reviews only from affected organizations, and in general simplifying work processes. All members of the YMP received training to the new Orientation class Eleven other training classed were held. Investigators submitted 971 records to the Project and only 37 were rejected. The software program has 115 programs approved for quality-affecting work. The Project Office conducted 3 audits and 1 survey of Los Alamos activities. We conducted 14 audits and 4 surveys. Eight corrective action reports were closed, leaving only one open. Internally, 22 deficiencies were recognized. This is a decrease from 65 in 1991. Since each deficiency requires about 2 man weeks to resolve, the savings are significant. Problems with writing acceptable deficiency reports have essentially disappeared. Trend reports for 1992 were examined and are summarized herein. Three adverse trends have been closed; one remaining adverse trend will be closed when the affected procedures are revised. The number of deficiencies issued to Los Alamos compared to other participants is minimal.

Bolivar, S.L.; Burningham, A.; Chavez, P. [and others

1994-03-01T23:59:59.000Z

140

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 5, Part B: Chapter 8, Sections 8.3.1.5 through 8.3.1.17  

Science Conference Proceedings (OSTI)

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

NONE

1988-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

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

SciTech Connect

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

NONE

1988-12-01T23:59:59.000Z

142

Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 6, Part B: Chapter 8, Sections 8.3.2 through 8.3.4.4  

Science Conference Proceedings (OSTI)

This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 35 figs., 70 tabs.

NONE

1988-12-01T23:59:59.000Z

143

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

Science Conference Proceedings (OSTI)

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

NONE

1985-05-01T23:59:59.000Z

144

Corrective Action Investigation Plan for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada (December 2002, Revision No.: 0), Including Record of Technical Change No. 1  

SciTech Connect

The Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 204 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 204 is located on the Nevada Test Site approximately 65 miles northwest of Las Vegas, Nevada. This CAU is comprised of six Corrective Action Sites (CASs) which include: 01-34-01, Underground Instrument House Bunker; 02-34-01, Instrument Bunker; 03-34-01, Underground Bunker; 05-18-02, Chemical Explosives Storage; 05-33-01, Kay Blockhouse; 05-99-02, Explosive Storage Bunker. Based on site history, process knowledge, and previous field efforts, contaminants of potential concern for Corrective Action Unit 204 collectively include radionuclides, beryllium, high explosives, lead, polychlorinated biphenyls, total petroleum hydrocarbons, silver, warfarin, and zinc phosphide. The primary question for the investigation is: ''Are existing data sufficient to evaluate appropriate corrective actions?'' To address this question, resolution of two decision statements is required. Decision I is to ''Define the nature of contamination'' by identifying any contamination above preliminary action levels (PALs); Decision II is to ''Determine the extent of contamination identified above PALs. If PALs are not exceeded, the investigation is completed. If PALs are exceeded, then Decision II must be resolved. In addition, data will be obtained to support waste management decisions. Field activities will include radiological land area surveys, geophysical surveys to identify any subsurface metallic and nonmetallic debris, field screening for applicable contaminants of potential concern, collection and analysis of surface and subsurface soil samples from biased locations, and step-out sampling to define the extent of contamination, as necessary. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NSO

2002-12-12T23:59:59.000Z

145

Characterization of angiotensin-binding sites in the bovine adrenal and the rat brain  

SciTech Connect

The first study was designed to determine whether systemically administered MSG affects neurons in the CVOs that are potentially important in mediating angiotensin-dependent responses. Rats were pretreated with MSG and the receptors for angiotensin II were assayed by radioligand binding in brain homogenates from the septum anteroventral third ventricular region (AV3V) and the thalamus/hypothalamus region using {sup 125}I-angiotensin II as the radioligand. The results of this experiment indicate that systematically administered MSG in the rat significantly reduced the number (Bmax) of Ang II receptors in a tissue sample which contained both extra blood-brain barrier organs as well as tissue within the blood-brain barrier with no change in the affinity (Kd) of the binding sites. The second chapter reports the successful solubilization of bovine adrenal {sup 125}I Ang II and {sup 125}I Sar{sup 1},Ile{sup 8}-Ang II binding sites with the detergent CHAPS. The results of our studies indicate the presence of two angiotensin binding sites. The one site is specific for naturally occurring angiotensins as well as sarcosine-1 substituted angiotensin analogues. The other site which can be optimally stabilized be re-addition of 0.3% CHAPS into the incubation assay binds sarcosine-1 substituted angiotensins exclusively. Hydrophobic interaction chromatography experiments suggest that these sites, possibly, represent distinct proteins. The third chapter discusses the successful solubilization and partial characterization of the rat brain angiotensin receptor.

Rogulja, I.

1989-01-01T23:59:59.000Z

146

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

SciTech Connect

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

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

2007-06-11T23:59:59.000Z

147

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

SciTech Connect

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

1997-04-01T23:59:59.000Z

148

Washington, D.C.Abandoned Mine Site Characterization and Cleanup Handbook Contributors  

E-Print Network (OSTI)

(Handbook) is the result of the collective efforts and contributions of a number of individuals. During the earliest days of Handbook development, Mike Bishop of EPA Region 8 lead the effort to develop a Superfund Mine Waste Reference Document for EPA project managers working on mine site cleanup. That effort evolved into the Handbook in recognition of the many regulatory and non-regulatory mechanisms that are used today to manage the characterization and cleanup of mines sites. Users are encouraged to consider the information presented in the Handbook against the backdrop of site specific environmental and regulatory factors. The Handbook has been developed as a source of information and ideas for project managers involved in the characterization and cleanup of inactive mine sites. It is not guidance or policy. The list that follows acknowledges the efforts of writers, reviewers, editors, and other contributors that made development of the Handbook possible. It is always a bit risky to develop a list of contributors because it is inevitable

Attn Of; Nick Ceto; Shahid Mahmud; Fred Macmillan; Brad Bradley; Shawn Ghose; Mark Doolan; Mike Bishop; Matt Cohn; Carol Russ; Jim Dunn; Elisabeth Evans; Holly Fliniau; Eva Hoffman; Sonya Pennock; Mike Holmes; Andy Lensink; Ken Wangerud; Sara Weinstock; Chris Weis; Patti Collins; Ken Greenberg; Mike Hingerty; Nick Ceto; Bruce Duncan; Earl Liverman; Roseanne Lorenzana; Patty Mcgrath; Don Metheny

2000-01-01T23:59:59.000Z

149

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

Science Conference Proceedings (OSTI)

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

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

1994-04-01T23:59:59.000Z

150

Sandia National Laboratories site-wide hydrogeologic characterization project calendar year 1992 annual report  

Science Conference Proceedings (OSTI)

The Sandia National Laboratories, New Mexico (SNL/NM) Site-Wide Hydrogeologic Characterization (SWHC) project has been implemented as part of the SNL/NM Environmental Restoration (ER) Program to develop the regional hydrogeologic framework and baseline for the approximately 100 mi of Kirtland Air Force Base (KAFB) and adjacent withdrawn public lands upon which SNL/NM has performed research and development activities. Additionally, the SWHC project will investigate and characterize generic hydrogeologic issues associated with the 172 ER sites owned by SNL/NM across its facilities on KAFB. As called for in the Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA) Part B permit agreement between the U.S. Environmental Protection Agency (EPA) as the permitter and the U.S. Department of Energy (DOE) and SNL/NM as the permittees, an annual report is to be prepared by the SWHC project team. This document serves two primary purposes: (1) to identify and describe the conceptual framework for the hydrogeologic system underlying SNL/NM and (2) to describe characterization activities undertaken in the preceding year that add to our understanding (reduce our uncertainties) regarding the conceptual and quantitative hydrogeologic framework. This SWHC project annual report focuses primarily on purpose 1, providing a summary description of the current {open_quotes}state of knowledge{close_quotes} of the Sandia National Laboratories/Kirtland Air Force Base (SNL/KAFB) hydrogeologic setting.

Crowson, D.; Gibson, J.D.; Haase, C.S.; Holt, R.; Hyndman, D.; Krumhansl, J.; Lauffer, F.; McCord, J.P.; McCord, J.T.; Neel, D. [and others

1993-10-01T23:59:59.000Z

151

Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Addendum D1  

Science Conference Proceedings (OSTI)

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

Ludlam, J.R.

1985-01-01T23:59:59.000Z

152

DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.  

Science Conference Proceedings (OSTI)

The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures.

KALB,P.D.; MILIAN,L.; LUCKETT,L.; WATTERS,D.; MILLER,K.M.; GOGOLAK,C.

2001-05-01T23:59:59.000Z

153

A Case Study on the Use of Innovative Methods for Comprehensive Site Characterization at Former Manufactured Gas Plant Sites  

Science Conference Proceedings (OSTI)

This report is a case study on using innovative technologies for investigating former manufactured gas plant sites.

2002-06-25T23:59:59.000Z

154

A Survey of Department of Energy-Sponsored Geophysical Research for Shallow Waste Site Characterization  

Science Conference Proceedings (OSTI)

Subsurface contamination plagues many U.S. Department of Energy (DOE) sites and threatens groundwater supplies. This survey discusses research sponsored by the DOE Environmental Management Science Program (EMSP) for geophysical characterization of the vadose zone at the Idaho National Engineering and Environmental Laboratory (INEEL) and other contaminated sites. Various types of geophysical imaging techniques are used to characterize the shallow subsurface—electromagnetic, ground-penetrating radar, electrical, seismic, and nuclear magnetic resonance. Three common themes appear in the research surveyed in this article: (1) the development of high-resolution imaging capabilities to capture important details of the heterogeneous nature of subsurface properties and processes, (2) the coupling of non-intrusive survey geophysical measurements (e.g., electrical surveys) with detailed quantitative precise point-sensor measurements (e.g., lysimeters and vapor-port systems) or borehole (e.g., nuclear magnetic resonance, neutron-based moisture, and geochemical tools) measurements to extend high-precision knowledge away from the borehole, and finally (3) the application of multiple geophysical methods to constrain the uncertainty in determining critical subsurface physical properties. Laboratory, field, theoretical, and computational studies are necessary to develop our understanding of the manner in which contaminants travel through the vadose zone. Applications of geophysical methods to various contaminated areas at the INEEL are given.

Donna Post Guillen

2004-01-01T23:59:59.000Z

155

Identification and characterization of conservative organic tracers for use as hydrologic tracers for the Yucca Mountain site characterization study. Final report  

Science Conference Proceedings (OSTI)

Extensive tracer testing is expected to take place at the C-well complex in the Nevada Test Site as part of the Yucca Mountain Site Characterization Project. The C-well complex consists of one pumping well, C3, and two injection wells, C1 and C2 into which tracer will be introduced. The goal of this research was to provide USGS with numerous tracers to completed these tests. Several classes of fluorinated organic acids have been evaluated. These include numerous isomers of fluorinated benzoic acids, cinnamic acids, and salicylic acids. Also several derivatives of 2-hydroxy nicotinic acid (pyridone) have been tested. The stability of these compounds was determined using batch and column tests. Ames testing (mutagenicity/carcinogenicity) was conducted on the fluorinated benzoic acids and a literature review of toxicity of the fluorobenzoates and three perfluoro aliphatic acids was prepared. Solubilities were measured and method development work was performed to optimize the detection of these compounds. A Quality Assurance (QA) Program was developed under existing DOE and USGS guidelines. The program includes QA procedures and technical standard operating procedures. A tracer test, using sodium iodide, was performed at the C-well complex. HRC chemists performed analyses on site, to provide real time data for the USGS hydrologists and in the laboratories at UNLV. Over 2,500 analyses were performed. This report provides the results of the laboratory experiments and literature reviews used to evaluate the potential tracers and reports on the results of the iodide C-well tracer test.

Stetzenbach, K.; Farnham, I.

1996-06-01T23:59:59.000Z

156

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

SciTech Connect

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

NONE

1992-09-01T23:59:59.000Z

157

Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site  

SciTech Connect

A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation`s first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities.

Simecka, W.B. [USDOE Nevada Field Office, Las Vegas, NV (United States); Grant, T.A.; Voegele, M.D. [Science Applications International Corp., Las Vegas, NV (United States); Cline, K.M. [Woodward-Clyde Federal Services, Washington, DC (United States)

1992-12-31T23:59:59.000Z

158

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

Science Conference Proceedings (OSTI)

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

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

1994-07-01T23:59:59.000Z

159

Identifying and Characterizing Candidate Areas for Siting New Nuclear Capacity in the United States  

Science Conference Proceedings (OSTI)

Oak Ridge National Laboratory (ORNL) staff recently completed an internal 'Energy Assurance' study examining the key issues associated with the country's energy needs for the future focusing on generation sources, baseload options, transmission and distribution, reduction of greenhouse gases, and overall energy security issues. In examining the various generation sources including nuclear power and renewables, one principal finding was that 300 GW(e) of new nuclear electrical generating capacity would be needed by 2050. With that need, the initial, obvious question is can 300 GW(e) of nuclear capacity be sited in the United States? In an attempt to address that question as well as others, ORNL initiated a 'National Electric Generation Siting Study,' which is to be a multiphase study to address several key questions related to our national electrical energy supply. The initial phase of this study is to examine the nuclear option. This paper summarizes the approach developed for screening sites, the methodology employed that includes spatial modeling, and preliminary results using the southeast United States to demonstrate the usefulness of the overall approach as a test case.

Mays, Gary T [ORNL; Jochem, Warren C [ORNL; Greene, Sherrell R [ORNL; Belles, Randy [ORNL; Cetiner, Mustafa Sacit [ORNL; Hadley, Stanton W [ORNL

2009-01-01T23:59:59.000Z

160

Corrective Action Investigation Plan for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 529 consists of one Corrective Action Site (25-23-17). For the purpose of this investigation, the Corrective Action Site has been divided into nine parcels based on the separate and distinct releases. A conceptual site model was developed for each parcel to address the translocation of contaminants from each release. The results of this investigation will be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

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

2003-02-26T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

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

SciTech Connect

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

GANDER MJ; LEARY KD; LEVITT MT; MILLER CW

2011-01-14T23:59:59.000Z

162

Characterization of ventilation ductwork in Building K-33 at the Oak Ridge K-25 Site  

Science Conference Proceedings (OSTI)

An extensive sampling and analysis program was initiated in September 1991 to characterize the ductwork of Building K-33, which is located at the Oak Ridge K-25 Site. This building, 32.4 acres under roof, contains nearly 3 miles of main plenums without considering the side laterals, which are extensive. A large number (i.e., 131) of hexane-moistened wipe samples were taken from within randomly selected locations in the 16 main plenums and the side lateral network. Samples were analyzed for polychlorinated biphenyls (PCBs), uranium, and technetium. These samples were augmented by 5 bulk material and 13 metal coupon samples that were subjected to TCLP (Toxicity Characteristic Leaching Procedure) analyses for arsenic, barium, cadmium, chromium, lead, nickel, selenium, silver, and mercury.

Mrochek, J.E.

1992-05-01T23:59:59.000Z

163

Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project  

SciTech Connect

Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project.

Siegel, M.D.; Cheng, W.C. [Sandia National Labs., Albuquerque, NM (United States); Ward, D.B.; Bryan, C.R. [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences

1995-08-01T23:59:59.000Z

164

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

Science Conference Proceedings (OSTI)

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

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

1993-09-01T23:59:59.000Z

165

Physicochemical and mineralogical characterization of uranium-contaminated soils from the Fernald Integrated Demonstration Site  

SciTech Connect

An integrated approach that utilizes various characterization technologies has been developed for the Uranium Soil Integrated Demonstration program. The Fernald Environmental Restoration Management Corporation site near Cincinnati, Ohio, was selected as the host facility for this demonstration. Characterization of background, untreated contaminated, and treated contaminated soils was performed to assess the contamination and the effect of treatment efforts to remove uranium from these soils. Carbonate minerals were present in the contaminated soils (added for erosion control) but were absent in the nearby background soils. Because of the importance of the carbonate anion to uranium solubility, the occurrence of carbonate minerals in these soils will be an important factor in the development of a successful remediation technology. Uranium partitioning data among several particle-size fractions indicate that conventional soil washing will be ineffective for remediation of these soils and that chemical extraction will be necessary to lower the uranium concentration to the target level (52 mg/kg). Carbonate-based (sodium carbonate/bicarbonate) and acid-based (sulfuric and citric acids) lixiviants were employed for the selective removal of uranium from these soils. Characterization results have identified uranium phosphate minerals as the predominant uranium mineral form in both the untreated and treated soils. The low solubility associated with phosphate minerals is primarily responsible for their occurrence in the posttreated soils. Artificial weathering of the treated soils caused by the treatments, particularly acid-based lixiviants, was documented by their detrimental effects on several physicochemical characteristics of these soils (e.g., soil pH, particle-size distribution, and mineralogy).

Elless, M.P.; Lee, S.Y.; Timpson, M.E.

1994-09-01T23:59:59.000Z

166

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

SciTech Connect

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

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

2008-07-16T23:59:59.000Z

167

SITE CHARACTERIZATION AND MONITORING DATA FROM THE AREA 5 PILOT WELLS  

SciTech Connect

Three exploratory boreholes were drilled and completed to the uppermost alluvial aquifer in Area 5 of the Nevada Test Site, Nye County, Nevada, in 1992. The boreholes and associated investigations were part of the Area 5 Site Characterization Program developed to meet data needs associated with regulatory requirements applicable to the disposal of low-level, mixed, and high-specific-activity waste at this site. This series of boreholes was specifically designed to characterize the hydrogeology of the thick vadose zone and to help define the water quality and hydraulic properties of the uppermost aquifer. Wells UE5PW-1, UE5PW-2, and UE5PW-3 are located in a triangular array near the southeast, northeast, and northwest corners, respectively, of the approximately 2.6-square-kilometer Area 5 Radioactive Waste Management Site to give reasonable spatial coverage for sampling and characterization, and to help define the nearly horizontal water table. Two of the wells, UE5PW-1 and UE5PW-2, penetrated only unconsolidated alluvial materials. The third well, located closer to the margin of the basin, penetrated both alluvium and underlying ash-flow and bedded tuff units. The watertable was encountered at the elevation of approximately 734 meters. The results of laboratory testing of core and drill cuttings samples indicate that the mineralogical, material, and hydrologic properties of the alluvium are very similar within and between boreholes. Additional tests on the same core and drill cuttings samples indicate that hydrologic conditions within the alluvium are also similar between pilot wells. Both core and drill cuttings samples are dry (less than 10 percent water content by weight) throughout the entire unsaturated section of alluvium, and water content increases slightly with depth in each borehole. Water potential measurements on core samples show a large positive potential gradient (water tends to move upward, rather than downward) to a depth of approximately 30.5 meters in each borehole, and a nearly zero potential gradient throughout the remaining portion of the vadose zone. These hydrologic condition data and hydrologic property data indicate that little net downward liquid flow is occurring (if any) through the thick vadose zone. Conversely, gas flow by diffusion, and possibly by advection, may be an important transport mechanism. Environmental tracer measurements made on water extracted from geologic samples suggest that water vapor in the upper portion of the vadose zone is moving upward in response to evaporative demand of the present arid climate. Preliminary water quality data indicate that the key hazardous and radioactive constituents do not exceed appropriate standards. Monitoring instruments and equipment were installed in each pilot well for making in-situ measurements of key hydrologic and pneumatic parameters and to monitor change in these parameters over time.

BECHTEL NEVADA; U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

2005-09-01T23:59:59.000Z

168

Data management implementation plan for the site characterization of the Waste Area Grouping 1 Groundwater Operable Unit at Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

The Waste Area Grouping (WAG) 1 Groundwater Operable Unit (OU) at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is undergoing a site characterization. This project is not mandated by the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); therefore, no formalized meetings for data quality objective (DQO) development were held. Internally, DQOs were generated by the project team based on the end uses of the data to be collected. The 150-acre WAG 1 is contained within the ORNL security area. It includes all of the former ORNL radioisotope research, production, and maintenance facilities; former waste management areas; and some former administrative facilities. The goal of the WAG 1 Groundwater Site Characterization is to provide the necessary data on the nature and extent of groundwater contamination with an acceptable level of uncertainty to support the selection of remedial alternatives and to identify additional data needs for future actions. Primary objectives for the site characterization are: (1) To identify and characterize contaminant migration pathways based on the collection of groundwater data; (2) to identify sources of groundwater contamination and evaluate remedial actions which could be implemented to control or eliminate these sources; and (3) To conduct groundwater monitoring in support of other OUs in WAG 1 and the ORNL Groundwater OU.

Ball, T.S.; Nickle, E.B.

1994-10-01T23:59:59.000Z

169

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

SciTech Connect

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

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

2005-09-30T23:59:59.000Z

170

Characterization of wastes in and around early reactors at the Hanford Site: The use of historical research  

SciTech Connect

This paper will present the waste characterization knowledge that has been gained in the first, ``Large-Scale Remediation Study`` to be performed on the reactor areas (100 Areas) of the Hanford Site. Undertaken throughout the past year, this research project has identified thousands of pieces of buried hardware, as well as the volumes of liquid wastes in burial sites in the reactor areas. The author of this landmark study, Dr. Michele Gerber, will discuss historical research as a safe and cost-effective characterization tool.

Gerber, M.S.

1993-10-01T23:59:59.000Z

171

Geological characterization report, Waste Isolation Pilot Plant (WIPP) site, Southeastern New Mexico  

SciTech Connect

Geotechnical information is presented relevant to the WIPP site in the Delaware Basin in SE New Mexico. This volume covers regional geology, site geology, and seismology. (DLC)

Powers, D.W.; Lambert, S.J.; Shaffer, S.E.; Hill, L.R.; Weart, W.D. (eds.)

1978-08-01T23:59:59.000Z

172

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

Science Conference Proceedings (OSTI)

The major objectives of the proposed study were to: 1.) determine the leaching characteristics of hexavalent chromium [Cr(VI)] from contaminated sediments collected from 100 Area spill sites; 2.) elucidate possible Cr(VI) mineral and/or chemical associations that may be responsible for Cr(VI) retention in the Hanford Site 100 Areas through the use of i.) macroscopic leaching studies and ii.) microscale characterization of contaminated sediments; and 3.) provide information to construct a conceptual model of Cr(VI) geochemistry in the Hanford 100 Area vadose zone. In addressing these objectives, additional benefits accrued were: (1) a fuller understanding of Cr(VI) entrained in the vadose zone that will that can be utilized in modeling potential Cr(VI) source terms, and (2) accelerating the Columbia River 100 Area corridor cleanup by providing valuable information to develop remedial action based on a fundamental understanding of Cr(VI) vadose zone geochemistry. A series of macroscopic column experiments were conducted with contaminated and uncontaminated sediments to study Cr(VI) desorption patterns in aged and freshly contaminated sediments, evaluate the transport characteristics of dichromate liquid retrieved from old pipelines of the 100 Area; and estimate the effect of strongly reducing liquid on the reduction and transport of Cr(VI). Column experiments used the with the column studies. Cr(VI) is found as ubiquitous coatings on sediment grain surfaces. Small, higher concentration, chromium sites are associated with secondary clay mineral inclusions, with occasional barium chromate minerals, and reduced to Cr(III) in association with iron oxides that are most likely magnetite primary minerals. Within the restricted access domains of sediment matrix, ferrous iron could also diffuse from in situ, high-surface-area minerals to cause the reductive immobilization of chromate. This process may be favored at microscale geochemical zones where ferrous iron could be supplied. Once nucleated, micrometer-scale precipitates are favored as growing locales for further accumulation, causing the formation of discrete zones of Cr(III).

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

2008-07-16T23:59:59.000Z

173

Corrective Action Investigation Plan for Corrective Action Unit 516: Septic Systems and Discharge Points, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Sites Office's (NNSA/NSO's) approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 516, Septic Systems and Discharge Points, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 516 consists of six Corrective Action Sites: 03-59-01, Building 3C-36 Septic System; 03-59-02, Building 3C-45 Septic System; 06-51-01, Sump Piping, 06-51-02, Clay Pipe and Debris; 06-51-03, Clean Out Box and Piping; and 22-19-04, Vehicle Decontamination Area. Located in Areas 3, 6, and 22 of the NTS, CAU 516 is being investigated because disposed waste may be present without appropriate controls, and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. Existing information and process knowledge on the expected nature and extent of contamination of CAU 516 are insufficient to select preferred corrective action alternatives; therefore, additional information will be obtained by conducting a corrective action investigation. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3/2004.

U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Sites Office

2003-04-28T23:59:59.000Z

174

Corrective Action Investigation Plan for Corrective Action Unit 516: Septic Systems and Discharge Points, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Sites Office's (NNSA/NSO's) approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 516, Septic Systems and Discharge Points, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 516 consists of six Corrective Action Sites: 03-59-01, Building 3C-36 Septic System; 03-59-02, Building 3C-45 Septic System; 06-51-01, Sump Piping, 06-51-02, Clay Pipe and Debris; 06-51-03, Clean Out Box and Piping; and 22-19-04, Vehicle Decontamination Area. Located in Areas 3, 6, and 22 of the NTS, CAU 516 is being investigated because disposed waste may be present without appropriate controls, and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. Existing information and process knowledge on the expected nature and extent of contamination of CAU 516 are insufficient to select preferred corrective action alternatives; therefore, additional information will be obtained by conducting a corrective action investigation. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3/2004.

U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Sites Office

2003-04-28T23:59:59.000Z

175

CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL  

SciTech Connect

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

Farfan, E.; Coleman, R.

2011-03-31T23:59:59.000Z

176

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

SciTech Connect

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

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

2013-01-10T23:59:59.000Z

177

Characterization and reaction behavior of ferrocyanide simulants and Hanford Site high-level ferrocyanide waste  

Science Conference Proceedings (OSTI)

Nonradioactive waste simulants and initial ferrocyanide tank waste samples were characterized to assess potential safety concerns associated with ferrocyanide high-level radioactive waste stored at the Hanford Site in underground single-shell tanks (SSTs). Chemical, physical, thermodynamic, and reaction properties of the waste simulants were determined and compared to properties of initial samples of actual ferrocyanide wastes presently in the tanks. The simulants were shown to not support propagating reactions when subjected to a strong ignition source. The simulant with the greatest ferrocyanide concentration was shown to not support a propagating reaction that would involve surrounding waste because of its high water content. Evaluation of dried simulants indicated a concentration limit of about 14 wt% disodium mononickel ferrocyanide, below which propagating reactions could not occur in the ambient temperature bulk tank waste. For postulated localized hot spots where dried waste is postulated to be at an initial temperature of 130 C, a concentration limit of about 13 wt% disodium mononickel ferrocyanide was determined, below which propagating reactions could not occur. Analyses of initial samples of the presently stored ferrocyanide waste indicate that the waste tank ferrocyanide concentrations are considerably lower than the limit for propagation for dry waste and that the water content is near that of the as-prepared simulants. If the initial trend continues, it will be possible to show that runaway ferrocyanide reactions are not possible under present tank conditions. The lower ferrocyanide concentrations in actual tank waste may be due to tank waste mixing and/or degradation from radiolysis and/or hydrolysis, which may have occurred over approximately 35 years of storage.

Jeppson, D.W.; Simpson, B.C.

1994-02-01T23:59:59.000Z

178

The role of optimality in characterizing CO2 seepage from geological carbon sequestration sites  

SciTech Connect

Storage of large amounts of carbon dioxide (CO{sub 2}) in deep geological formations for greenhouse gas mitigation is gaining momentum and moving from its conceptual and testing stages towards widespread application. In this work we explore various optimization strategies for characterizing surface leakage (seepage) using near-surface measurement approaches such as accumulation chambers and eddy covariance towers. Seepage characterization objectives and limitations need to be defined carefully from the outset especially in light of large natural background variations that can mask seepage. The cost and sensitivity of seepage detection are related to four critical length scales pertaining to the size of the: (1) region that needs to be monitored; (2) footprint of the measurement approach, and (3) main seepage zone; and (4) region in which concentrations or fluxes are influenced by seepage. Seepage characterization objectives may include one or all of the tasks of detecting, locating, and quantifying seepage. Each of these tasks has its own optimal strategy. Detecting and locating seepage in a region in which there is no expected or preferred location for seepage nor existing evidence for seepage requires monitoring on a fixed grid, e.g., using eddy covariance towers. The fixed-grid approaches needed to detect seepage are expected to require large numbers of eddy covariance towers for large-scale geologic CO{sub 2} storage. Once seepage has been detected and roughly located, seepage zones and features can be optimally pinpointed through a dynamic search strategy, e.g., employing accumulation chambers and/or soil-gas sampling. Quantification of seepage rates can be done through measurements on a localized fixed grid once the seepage is pinpointed. Background measurements are essential for seepage detection in natural ecosystems. Artificial neural networks are considered as regression models useful for distinguishing natural system behavior from anomalous behavior suggestive of CO{sub 2} seepage without need for detailed understanding of natural system processes. Because of the local extrema in CO{sub 2} fluxes and concentrations in natural systems, simple steepest-descent algorithms are not effective and evolutionary computation algorithms are proposed as a paradigm for dynamic monitoring networks to pinpoint CO{sub 2} seepage areas.

Cortis, Andrea; Oldenburg, Curtis M.; Benson, Sally M.

2008-09-15T23:59:59.000Z

179

Joint NEA-IAEA International Peer Review of the Yucca Mountain Site Characterization Project's Total System Performance Assessment Supporting the Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NEA-IAEA International Peer Review of the NEA-IAEA International Peer Review of the Yucca Mountain Site Characterization Project's Total System Performance Assessment Supporting the Site Recommendation Process Final Report December 2001 This document is not an official copy and is for informational purposes only. CONTENTS Summary Objectives International perspective Recommendations for future assessments 1 Introduction 1.1 Background to the Yucca Mountain Project 1.2 Terms of reference, objectives and scope of the review 1.3 Conduct of the review 1.4 Organisation of this report 2 General Considerations 2.1 Regulatory perspective 2.2 Performance assessment rationale 2.3 General approach to performance assessment 2.4 Documentation 3 Sub-system methodology 3.1 Repository design

180

[Characterization of historical infiltration in the unsaturated zone at the Nevada Test Site using chloride, bromide, and chlorine-36 as environmental tracers]; [Final subcontract report  

SciTech Connect

This document is an end-of-contract report, prepared by Hydro Geo Chem for Los Alamos National Laboratory under contract number 9-XDD-6329F-1. The ultimate goal of this work is to characterize historical infiltration and unsaturated flow in the Yucca Mountain area of the Nevada Test Site. Work on this contract has focused on using chloride, bromide, stable chlorine isotopes, and chlorine-36 distributions to evaluate the depth of infiltration in the unsaturated zone. Effort in support of this work has included developing analytical procedures, exploring ways in which to separate the. meteoric component from the rock component, and meeting quality assurance requirements.

NONE

1991-05-17T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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181

Bibliography of publications related to the Yucca Mountain Site Characterization Project prepared by U.S. Geological Survey personnel through April 1991  

Science Conference Proceedings (OSTI)

Personnel of the US Geological Survey have participated in nuclear-waste management studies in the State of Nevada since the mid-1970`s. A bibliography of publications prepared principally for the US Department of Energy Yucca Mountain Site Characterization Project (formerly Nevada Nuclear Waste Storage Investigations) through April 1991 contains 475 entries in alphabetical order. The listing includes publications prepared prior to the inception of the Nevada Nuclear Waste Storage Investigations Project in April 1977 and selected publications of interest to the Yucca Mountain region. 480 refs.

Glanzman, V.M.

1991-11-01T23:59:59.000Z

182

SYSTHESIS OF VOLCANISM STUDIES FOR THE YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT  

SciTech Connect

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

FV PERRY, GA CROWE, GA VALENTINE AND LM BOWKER

1997-09-23T23:59:59.000Z

183

SYSTHESIS OF VOLCANISM STUDIES FOR THE YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT  

Science Conference Proceedings (OSTI)

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

FV PERRY, GA CROWE, GA VALENTINE AND LM BOWKER

1997-09-23T23:59:59.000Z

184

Corrective Action Investigation Plan for Corrective Action Unit 322: Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 322, Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 322 consists of three Corrective Action Sites (CASs): 01-25-01, AST Release (Area 1); 03-25-03, Mud Plant AST Diesel Release (Area 3); 03-20-05, Injection Wells (Area 3). Corrective Action Unit 322 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. The investigation of three CASs in CAU 322 will determine if hazardous and/or radioactive constituents are present at concentrations and locations that could potentially pose a threat to human health and the environment. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

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

2003-07-16T23:59:59.000Z

185

In Situ Characterization of Unsaturated Soil Hydraulic Properties at the Maricopa Environmental Monitoring Site.  

E-Print Network (OSTI)

??Characterization of the unsaturated hydraulic properties is fundamental in modeling soil water flow and contaminant transport in the vadose zone. The objective of this study… (more)

Graham, Aaron Robert.

2004-01-01T23:59:59.000Z

186

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

SciTech Connect

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

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

1995-10-01T23:59:59.000Z

187

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

Science Conference Proceedings (OSTI)

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

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

2010-11-01T23:59:59.000Z

188

Site characterization progress report: Yucca Mountain, Nevada. Progress report number 17, April 1, 1997--September 30, 1997  

Science Conference Proceedings (OSTI)

The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM), created with the enactment of the Nuclear Waste Policy Act of 1982 (NWPA), is tasked to accept and dispose of the nation`s high-level radioactive waste and spent nuclear fuel in a deep geologic repository (high-level radioactive waste program). The report summarizes significant site characterization activities during the period from April 1, 1997 through September 30, 1997, in the evaluation of Yucca Mountain as a potential site for the geologic disposal of spent nuclear fuel and high-level radioactive wastes. The progress report also cites technical reports and research products that provide the detailed information on these activities. Chapter 2 outlines technical and regulatory issues that must be addressed by the Project and planned work toward achieving future objectives concerning the viability assessment, the environmental impact statement, the site recommendation, and the license application. Chapter 3 describes technical progress in preclosure radiological safety analysis, postclosure performance assessment, and performance confirmation activities. Chapter 4 describes various aspects of repository and waste package design and construction. It also discusses the Exploration Studies Facility cross drift. Chapter 5 describes site characterization activities, and Chapter 6 contains a complete list of references.

NONE

1998-04-01T23:59:59.000Z

189

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

DOE Green Energy (OSTI)

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

None

1980-12-01T23:59:59.000Z

190

A hypothesis driven approach to condition specific transcription factor binding site characterization in S.c.  

Science Conference Proceedings (OSTI)

We demonstrate a computational process by which transcription factor binding sites can be elucidated using genome-wide expression and binding profiles. The profiles direct us to the intergenic locations likely to contain the promoter regions for a given ...

Rhonda Harrison; Charles DeLisi

2002-03-01T23:59:59.000Z

191

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

SciTech Connect

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

1995-08-01T23:59:59.000Z

192

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 357: Mud Pits and Waste Dump, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) plan was prepared as a characterization and closure report for Corrective Action Unit (CAU) 357, Mud Pits and Waste Dump, in accordance with the Federal Facility Agreement and Consent Order. The CAU consists of 14 Corrective Action Sites (CASs) located in Areas 1, 4, 7, 8, 10, and 25 of the Nevada Test Site (NTS). All of the CASs are found within Yucca Flat except CAS 25-15-01 (Waste Dump). Corrective Action Site 25-15-01 is found in Area 25 in Jackass Flat. Of the 14 CASs in CAU 357, 11 are mud pits, suspected mud pits, or mud processing-related sites, which are by-products of drilling activities in support of the underground nuclear weapons testing done on the NTS. Of the remaining CASs, one CAS is a waste dump, one CAS contains scattered lead bricks, and one CAS has a building associated with Project 31.2. All 14 of the CASs are inactive and abandoned. Clean closure with no further action of CAU 357 will be completed if no contaminants are detected above preliminary action levels. A closure report will be prepared and submitted to the Nevada Division of Environmental Protection for review and approval upon completion of the field activities. Record of Technical Change No. 1 is dated 3/2004.

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

2003-06-25T23:59:59.000Z

193

Characterization of uranium contaminated soils from DOE Fernald Environmental Management Project Site: Results of Phase 1 characterization  

Science Conference Proceedings (OSTI)

The Integrated Demonstration (ID) for remediation of uranium- contaminated soils has been established by the DOE Office of Technology Development. The Fernald (Feed Materials Production Center) site was selected as the DOE facility for the field demonstration. The principle objective of this ID is to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems for the removal of uranium from contaminated soils. Several leaching solutions were employed to determine their effectiveness in extracting uranium from the soil. The extractants and their means of preparation were: 0.1 N nitric acid [HNO{sub 3}]: 6.25 mL of concentrated nitric acid was diluted to 1 L with distilled water; 2% ammonium carbonate [(NH{sub 4}){sub 2}CO{sub 3}]: 20 g of (NH{sub 4}){sub 2}CO{sub 3} was dissolved in distilled water and diluted to 1 L; 5% sodium hypochlorite (NaOCl): 50 mL of NaOCl reagent (Cl HCl) in 0.01 N nitric acid: 6.95 g (NH{sub 2}OH{center_dot}HCl) was dissolved and diluted to 1 L with 0.01 N HNO{sub 3}. The 0.01 N nitric acid was prepared by diluting 3 mL concentrated nitric acid to 5 L with distilled water; and the sodium citrate-bicarbonate-dithionite (CBD) method: 0.3 M sodium citrate (88 g tribasic sodium citrate, Na{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}2H{sub 2}O, per liter); 1 M sodium bicarbonate (84 g NaHCO{sub 3} per liter); and 5 g sodium dithionite, Na{sub 2}S{sub 2}O{sub 4}.

Lee, S.Y.; Marsh, J.D. Jr.

1992-01-01T23:59:59.000Z

194

Reconnaissance radiological characterization for the White Point Nike Missile Site, San Pedro, California  

SciTech Connect

This report is the result of field work performed at the former White Point Nike Missile Site, San Pedro, California. The Hazardous Waste Remedial Actions Program tasked the Oak Ridge National Laboratory Pollutant Assessments Group in Grand Junction, Colo., with this project. The objective was to determine whether or not radioisotopes possibly associated with past Department of Defense (DOD) operations were present and within accepted background levels. The radiation survey was accomplished by performing three independent radiation surveys, both outdoors and indoors, and random soil sampling. Initially, the site was land surveyed to develop a grid block system. A background radiation investigation was performed out in the San Pedro area.

Espegren, M.L.; Jensen, M.K.; Pierce, G.A. [Oak Ridge National Lab., TN (United States); Smith, S.M. [Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States)

1993-05-01T23:59:59.000Z

195

Reconnaissance radiological characterization for the White Point Nike Missile Site, San Pedro, California  

SciTech Connect

This report is the result of field work performed at the former White Point Nike Missile Site, San Pedro, California. The Hazardous Waste Remedial Actions Program tasked the Oak Ridge National Laboratory Pollutant Assessments Group in Grand Junction, Colo., with this project. The objective was to determine whether or not radioisotopes possibly associated with past Department of Defense (DOD) operations were present and within accepted background levels. The radiation survey was accomplished by performing three independent radiation surveys, both outdoors and indoors, and random soil sampling. Initially, the site was land surveyed to develop a grid block system. A background radiation investigation was performed out in the San Pedro area.

Espegren, M.L.; Jensen, M.K.; Pierce, G.A. (Oak Ridge National Lab., TN (United States)); Smith, S.M. (Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States))

1993-01-01T23:59:59.000Z

196

Site characterization progress report: Yucca Mountain, Nevada, April 1, 1990--September 30, 1990, Number 3; Nuclear Waste Policy Act (Section 113)  

SciTech Connect

In accordance with the requirements of Section 113(b)(3) of the Nuclear Waste Policy Act of 1982 (NWPA), as amended, the US Department of Energy has prepared this report on the progress of site characterization activities at Yucca Mountain, Nevada, for the period April 1 through September 30, 1990. This report is the third of a series of reports that are issued at intervals of approximately six months during site characterization. The report covers a number of new initiatives to improve the effectiveness of the site characterization program and covers continued efforts related to preparatory activities, study plans, and performance assessment. 85 refs., 2 figs., 3 tabs.

NONE

1991-03-01T23:59:59.000Z

197

Characterization of uranium contaminated soils from DOE Fernald Environmental Management Project Site: Results of Phase 1 characterization  

SciTech Connect

The Integrated Demonstration (ID) for remediation of uranium- contaminated soils has been established by the DOE Office of Technology Development. The Fernald (Feed Materials Production Center) site was selected as the DOE facility for the field demonstration. The principle objective of this ID is to evaluate and compare the versatility, efficiency, and economics of various technologies that may be combined into systems for the removal of uranium from contaminated soils. Several leaching solutions were employed to determine their effectiveness in extracting uranium from the soil. The extractants and their means of preparation were: 0.1 N nitric acid [HNO{sub 3}]: 6.25 mL of concentrated nitric acid was diluted to 1 L with distilled water; 2% ammonium carbonate [(NH{sub 4}){sub 2}CO{sub 3}]: 20 g of (NH{sub 4}){sub 2}CO{sub 3} was dissolved in distilled water and diluted to 1 L; 5% sodium hypochlorite (NaOCl): 50 mL of NaOCl reagent (Cl < 6%) was diluted to 1 L with distilled water; 0.1 M ethylenediaminetetraacetric acid, disodium salt (EDTA): 37.224 g EDTA was dissolved in distilled water and diluted to 1 L; 2% citric acid monohydrate solution (H{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}H{sub 2}O): 20 g of critic acid was diluted to 1 L with distilled water; 0.1 M hydroxylamine-hydrochloride (NH{sub 2}OH{center_dot}HCl) in 0.01 N nitric acid: 6.95 g (NH{sub 2}OH{center_dot}HCl) was dissolved and diluted to 1 L with 0.01 N HNO{sub 3}. The 0.01 N nitric acid was prepared by diluting 3 mL concentrated nitric acid to 5 L with distilled water; and the sodium citrate-bicarbonate-dithionite (CBD) method: 0.3 M sodium citrate (88 g tribasic sodium citrate, Na{sub 3}C{sub 6}H{sub 5}O{sub 7}{center_dot}2H{sub 2}O, per liter); 1 M sodium bicarbonate (84 g NaHCO{sub 3} per liter); and 5 g sodium dithionite, Na{sub 2}S{sub 2}O{sub 4}.

Lee, S.Y.; Marsh, J.D. Jr.

1992-01-01T23:59:59.000Z

198

Autoradiographic localization and characterization of angiotensin II binding sites in the spleen of rats and mice  

SciTech Connect

Specific binding sites for angiotensin II (Ang II) were localized in the red pulp of the spleen of rats and mice by quantitative autoradiography using /sup 125/I-Sar1-Ang II as a ligand. In the rat, the binding was saturable and specific, and the rank order for Ang II derivatives as competitors of /sup 125/I-Sar1-Ang II binding correlates well with their affinity for Ang II receptors in other tissues. Kinetic analysis in the rat spleen revealed a single class of binding sites with a KD of 1.11 nM and a Bmax value of 81.6 fmol/mg protein. Ang II binding sites were also localized on isolated rat spleen cells with similar affinity but with much lower Bmax, 9.75 fmol/mg protein. Ang II receptors were not detected in thymus sections from rats or mice, or on isolated rat thymocytes. The binding sites described here might represent a functional Ang II receptor with a role in the regulation of splenic volume and blood flow and in the modulation of the lymphocyte function.

Castren, E.; Kurihara, M.; Saavedra, J.M.

1987-07-01T23:59:59.000Z

199

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

Science Conference Proceedings (OSTI)

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

Fellows, R.L. [ed.

1993-02-26T23:59:59.000Z

200

Development of Aerosol Models for Radiative Flux Calculations at ARM Sites: Utility of Trajectory Clustering for Characterizing Aerosol Climatology  

NLE Websites -- All DOE Office Websites (Extended Search)

Development of Aerosol Models for Radiative Flux Development of Aerosol Models for Radiative Flux Calculations at ARM Sites: Utility of Trajectory Clustering for Characterizing Aerosol Climatology E. Andrews Cooperative Institute for Research in the Environment University of Colorado Boulder, Colorado E. Andrews, J. A. Ogren, P. J. Sheridan, and J. M. Harris Climate Monitoring and Diagnostics Laboratory National Oceanic and Atmospheric Administration Boulder, Colorado P. K. Quinn Pacific Marine Environmental Laboratory National Oceanic and Atmospheric Administration Seattle, Washington Abstract The uncertainties associated with assumptions of generic aerosol properties in radiative transfer codes are unknown, which means that these uncertainties are frequently invoked when models and

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

A sitewide approach to the characterization and use of soil and groundwater background at the Hanford Site  

SciTech Connect

A Sitewide approach to the characterization and use of soil and groundwater background has been developed for use in environmental restoration activities on the Hanford Site. Sitewide background more accurately represents the range of background compositions that exist in soil and groundwater at the over 140 Resource Conservation and Recovery Act of 1976 facilities and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 operable units, and provides a more consistent, credible, integrated, and efficient basis for identifying and evaluating contamination in these media than using unit-specific backgrounds.

Hoover, J.D.; Ruck, F.A. [Westinghouse Hanford Co., Richland, WA (United States); LeGore, T. [Boeing Computer Services Co., Richland, WA (United States); Thompson, K.M. [USDOE Richland Operations Office, WA (United States)

1993-10-01T23:59:59.000Z

202

Optimal utilization of field generated analytical data for site characterization and remedial decision making. Master's thesis  

Science Conference Proceedings (OSTI)

This study developed data quality standards for assessing environmental analytical data quality and its use in remedial decision making, specifically in risk assessment calculations. The primary purpose was to increase the use of field generated data in environmental site investigations versus the continued reliance on costly and time consuming EPA Contract Lab Program data. Increased reliance on field lab data could significantly reduce remedial investigation costs. The standards developed are based on regulatory criteria for data useability, achievable quality in a CLP lab setting, and basic statistical methods. The standards were applied to sets of Volatile Organic Compound data in water and soil matrices from CLP generated data from one Installation Restoration Program site and field lab generated data from another site. The CLP data failed the test for data useability based on the standards as established where the field generated data performed much better but also had its specific failures. The results of the test of the standards on actual data sets indicate that the standards may be more stringent than necessary. Also seen in the results is a strong performance of field labs in generating data of acceptable quality.

Lester, R.J.

1994-09-01T23:59:59.000Z

203

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

SciTech Connect

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

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

2010-07-13T23:59:59.000Z

204

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

Science Conference Proceedings (OSTI)

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

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

2010-09-01T23:59:59.000Z

205

Characterization of Waste Tar Associated with Abandoned Wood Chemical Plant Sites in Northwest Pennsylvania, USA  

SciTech Connect

Over 70 wood chemical plants operated in northern Pennsylvania between ca. 1890 and 1950, all located within 72 km of the New York state border. Their original purpose was to salvage the small unwanted hardwood trees left behind by the lumber mills, and to make charcoal, calcium acetate and methanol for a number of industrial uses via destructive distillation. At many old wood chemical plant sites, unknown quantities of wood tar remain as a residual contaminant and pose a pollution threat to aquatic life in nearby streams. Research on the composition and properties of residual wood tars from five abandoned industrial sites in Pennsylvania are described. Weathered wood tars were more viscous and contained fewer volatile and semivolatile organic compounds than did soil-buried tars. Phenol, 2-methylphenol (o-cresol), 4-methylphenol (p-cresol), and 2, 4-dimethylphenol were found in all sampled tars. These water-soluble phenolic compounds were released quasi-instantaneously in aqueous solution, followed by a slower rate of release, consistent with the behavior of similar compounds in other dense non-aqueous liquids. Air-exposed wood tar deposits developed a hard crust, which contained fewer volatiles and semivolatiles and had a higher softening point than other samples. These tars eroded to form a powdered soil colonized by lichens and mosses. Residual wood tar material found at one site was shown to be thermally altered, likely during the historical destruction of the chemical plant by fire. Recovered wood tar wastes have a relatively high heating value and may have use as a potential, but limited, alternate energy source.

Edendorn, H.M.; Severson, D. (Allegheny Institute of Natural History, Bradford, PA)

2007-07-01T23:59:59.000Z

206

Characterization of the Burma Road Rubble Pit at the Savannah River Site, Aiken, South Carolina  

Science Conference Proceedings (OSTI)

The Burma Road Rubble Pit (BRRP) is located at the Savannah River Site (SRS). The BRRP unit consists of two unlined earthen pits dug into surficial soil and filled with various waste materials. It was used from 1973--1983 for the disposal of dry inert rubble such as metal, concrete, lumber, poles, light fixtures, and glass. No record of the disposal of hazardous substances at the BRRP has been found. In 1983, the BRRP was closed by covering it with soil. In September 1988, a Ground Penetrating Radar survey detected three disturbed areas of soil near the BRRP, and a detailed and combined RCRA Facility Investigation/Remedial Investigation was conducted from November 1993 to February 1994 to determine whether hazardous substances were present in the subsurface, to evaluate the nature and extent of contamination, and to evaluate the risks posed to the SRS facility due to activities conducted at the BRRP site. Metals, semi-volatile organic compounds, volatile organic compounds, radionuclides and one pesticide (Aldrin) were detected in soil and groundwater samples collected from seventeen BRRP locations. A baseline risk assessment (BRA) was performed quantitatively to evaluate whether chemical and radionuclide concentrations detected in soil and groundwater at the BRRP posed an unacceptable threat to human health and the environment. The exposure scenarios identifiable for the BRRP were for environmental researchers, future residential and occupational land use. The total site noncancer hazard indices were below unity, and cancer risk levels were below 1.0E-06 for the existing and future case environmental researcher scenario. The future case residential and occupational scenarios showed total hazard and risk levels which exceeded US EPA criterion values relative to groundwater scenarios. For the most part, the total carcinogenic risks were within the 1.0E-04 to 1.0E-06 risk range. Only the future adult residential scenario was associated with risks exceeding 1.0E-04.

Ward, K.G.; Frazier, W.L.; McAdams, T.D.; McFalls, S.L.; Rabin, M. [Westinghouse Savannah River Co., Aiken, SC (United States); Voss, L. [Westinghouse Savannah River Co., Aiken, SC (United States)]|[Neptune and Co., Los Alamos, NM (United States)

1996-05-01T23:59:59.000Z

207

Buildings characterization work plan: Weldon Spring Site Remedial Action Project: Appendix  

Science Conference Proceedings (OSTI)

The following tables and location diagrams are furnished to assist the contractor in identifying and locating known ACM and potential ACM. Each location listed on the tables and shown on the diagrams represents the presence of a major concentration of ACM. Not every location of ACM at the WSCP is listed, two buildings (108 and 403) have not been surveyed, and portions of several buildings were inaccessible. However, the tables reflect all ACM that can be identified at the site prior to the dismantling of buildings.

Not Available

1988-04-01T23:59:59.000Z

208

The Underground Test Area Project of the Nevada Test Site: Building Confidence in Groundwater Flow and Transport Models at Pahute Mesa Through Focused Characterization Studies  

SciTech Connect

Pahute Mesa at the Nevada Test Site contains about 8.0E+07 curies of radioactivity caused by underground nuclear testing. The Underground Test Area Subproject has entered Phase II of data acquisition, analysis, and modeling to determine the risk to receptors from radioactivity in the groundwater, establish a groundwater monitoring network, and provide regulatory closure. Evaluation of radionuclide contamination at Pahute Mesa is particularly difficult due to the complex stratigraphy and structure caused by multiple calderas in the Southwestern Nevada Volcanic Field and overprinting of Basin and Range faulting. Included in overall Phase II goals is the need to reduce the uncertainty and improve confidence in modeling results. New characterization efforts are underway, and results from the first year of a three-year well drilling plan are presented.

Pawloski, G A; Wurtz, J; Drellack, S L

2009-12-29T23:59:59.000Z

209

Characterization Activities Conducted at the 183-DR Site in Support of an In Situ Gaseous Reduction Demonstration  

Science Conference Proceedings (OSTI)

In Situ Gaseous Reduction (ISGR) is a technology developed by DOE for the remediation of soil waste sites contaminated with hexavalent chromium. This document presents information associated with characterization activities conducted at the 183-DR site at Hanford, which is associated with a significant groundwater contaminant plume and was formerly a water treatment facility that utilized chromate as a corrosion inhibitor. Geotechnical and chemical data were collected during the excavation of trenches and the drilling of two vadose zone boreholes to support a possible ISGR demonstration at 183-DR. Although elevated total chromium and trace levels of hexavalent chromium were identified from one of the trenches and one of the boreholes, it appears that the boreholes missed the vadose zone contaminant source responsible for the chromium groundwater plume located downgradient of the 183-DR site. Recommendations are provided, however, for future work at 183-DR that may serve to identify the source for the groundwater plume and possibly provide an opportunity for an ISGR demonstration.

Thornton, Edward C.; Gilmore, Tyler J.; Olsen, Khris B.; Schalla, Ronald; Cantrell, Kirk J.

2001-03-30T23:59:59.000Z

210

Corrective Action Investigation Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility, Nevada Test Site, Nevada (includes ROTC No. 1, date 01/25/1999)  

Science Conference Proceedings (OSTI)

This Corrective Action Investigation Plan contains the US Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 254 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 254 consists of Corrective Action Site (CAS) 25-23-06, Decontamination Facility. Located in Area 25 at the Nevada Test Site (NTS), CAU 254 was used between 1963 through 1973 for the decontamination of test-car hardware and tooling used in the Nuclear Rocket Development Station program. The CAS is composed of a fenced area measuring approximately 119 feet by 158 feet that includes Building 3126, an associated aboveground storage tank, a potential underground storage area, two concrete decontamination pads, a generator, two sumps, and a storage yard. Based on site history, the scope of this plan is to resolve the problem statement identified during the Data Quality Objectives process that decontamination activities at this CAU site may have resulted in the release of contaminants of concern (COCs) onto building surfaces, down building drains to associated leachfields, and to soils associated with two concrete decontamination pads located outside the building. Therefore, the scope of the corrective action field investigation will involve soil sampling at biased and random locations in the yard using a direct-push method, scanning and static radiological surveys, and laboratory analyses of all soil/building samples. Historical information provided by former NTS employees indicates that solvents and degreasers may have been used in the decontamination processes; therefore, potential COCs include volatile/semivolatile organic compounds, Resource Conservation and Recovery Act metals, petroleum hydrocarbons, polychlorinated biphenyls, pesticides, asbestos, gamma-emitting radionuclides, plutonium, uranium, and strontium-90. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

DOE /NV

1999-07-29T23:59:59.000Z

211

All Sky Cameras for the characterization of the Cherenkov Telescope Array candidate sites  

E-Print Network (OSTI)

The All Sky Camera (ASC) was developed as a universal device for the monitoring of the night sky quality. Eight ASCs are already installed and measure night sky parameters at eight of the candidate sites of the Cherenkov Telescope Array (CTA) gamma-ray observatory. The ACS system consists of an astronomical CCD camera, a fish eye lens, a control computer and associated electronics. The measurement is carried out during astronomical night. The images are automatically taken every 5 minutes and automatically processed using the control computer of the device. The analysis results are the cloud fraction (the percentage of the sky covered by clouds) and night sky brightness (in mag/arcsec$^{2}$)

Mandát, Dušan; Ebr, Jan; Hrabovský, Miroslav; Prouza, Michael; Bulik, Tomasz; Allekotte, Ingomar

2013-01-01T23:59:59.000Z

212

Characterizing the Vertical Distribution of Aerosols Over the ARM SGP Site  

Science Conference Proceedings (OSTI)

This project focused on: 1) evaluating the performance of the DOE ARM SGP Raman lidar system in measuring profiles of water vapor and aerosols, and 2) the use of the Raman lidar measurements of aerosol and water vapor profiles for assessing the vertical distribution of aerosols and water vapor simulated by global transport models and examining diurnal variability of aerosols and water vapor. The highest aerosol extinction was generally observed close to the surface during the nighttime just prior to sunrise. The high values of aerosol extinction are most likely associated with increased scattering by hygroscopic aerosols, since the corresponding average relative humidity values were above 70%. After sunrise, relative humidity and aerosol extinction below 500 m decreased with the growth in the daytime convective boundary layer. The largest aerosol extinction for altitudes above 1 km occurred during the early afternoon most likely as a result of the increase in relative humidity. The water vapor mixing ratio profiles generally showed smaller variations with altitude between day and night. We also compared simultaneous measurements of relative humidity, aerosol extinction, and aerosol optical thickness derived from the ARM SGP Raman lidar and in situ instruments on board a small aircraft flown routinely over the ARM SGP site. In contrast, the differences between the CARL and IAP aerosol extinction measurements are considerably larger. Aerosol extinction derived from the IAP measurements is, on average, about 30-40% less than values derived from the Raman lidar. The reasons for this difference are not clear, but may be related to the corrections for supermicron scattering and relative humidity that were applied to the IAP data. The investigators on this project helped to set up a major field mission (2003 Aerosol IOP) over the DOE ARM SGP site. One of the goals of the mission was to further evaluate the aerosol and water vapor retrievals from this lidar system. Analysis of the aerosol and water vapor data collected by the Raman lidar during the 2003 Aerosol IOP indicated that the sensitivity of the lidar was significantly lower than when the lidar was initially deployed. A detailed analysis after the IOP of the long-term dataset demonstrated that the lidar began degrading in early 2002, and that it lost approximately a factor of 4 in sensitivity between 2002 and 2004. We participated in the development of the remediation plan for the system to restore its initial performance. We conducted this refurbishment and upgrade from May- September 2004. This remediation lead to an increase in the signal-to-noise ratio of 10 and 30 for the Raman lidar's water vapor mixing ratio and aerosol backscatter coefficient data, respectively as compared to the signal strengths when the system was first deployed. The DOE ARM Aerosol Lidar Validation Experiment (ALIVE), which was conducted during September 2005, evaluated the impact of these modifications and upgrades on the SGP Raman lidar measurements of aerosol extinction and optical thickness. The CARL modifications significantly improved the accuracy and temporal resolution of the aerosol measurements. Aerosol extinction profiles measured by the Raman lidar were also used to evaluate aerosol extinction profiles and aerosol optical thickness (AOT) simulated by aerosol models as part of the Aerosol module inter-Comparison in global models (AEROCOM) (http://nansen.ipsl.jussieu.fr/AEROCOM/aerocomhome.html) project. There was a wide range in how the models represent the aerosol extinction profiles over the ARM SGP site, even though the average annual AOT represented by the various models and measured by CARL and the Sun photometer were in general agreement, at least within the standard deviations of the averages. There were considerable differences in the average vertical distributions among the models, even among models that had similar average aerosol optical thickness. Deviations between mean aerosol extinction profiles were generally small (~20-30%) for altitudes above 2 km, and grew consider

Richard Ferrare, Connor Flynn, David Turner

2009-05-05T23:59:59.000Z

213

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

Science Conference Proceedings (OSTI)

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

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

2011-01-04T23:59:59.000Z

214

Hydraulic Characterization of Overpressured Tuffs in Central Yucca Flat, Nevada Test Site, Nye County, Nevada  

Science Conference Proceedings (OSTI)

A sequence of buried, bedded, air-fall tuffs has been used extensively as a host medium for underground nuclear tests detonated in the central part of Yucca Flat at the Nevada Test Site. Water levels within these bedded tuffs have been elevated hundreds of meters in areas where underground nuclear tests were detonated below the water table. Changes in the ground-water levels within these tuffs and changes in the rate and distribution of land-surface subsidence above these tuffs indicate that pore-fluid pressures have been slowly depressurizing since the cessation of nuclear testing in 1992. Declines in ground-water levels concurrent with regional land subsidence are explained by poroelastic deformation accompanying ground-water flow as fluids pressurized by underground nuclear detonations drain from the host tuffs into the overlying water table and underlying regional carbonate aquifer. A hydraulic conductivity of about 3 x 10-6 m/d and a specific storage of 9 x 10-6 m-1 are estimated using ground-water flow models. Cross-sectional and three-dimensional ground-water flow models were calibrated to measured water levels and to land-subsidence rates measured using Interferometric Synthetic Aperture Radar. Model results are consistent and indicate that about 2 million m3 of ground water flowed from the tuffs to the carbonate rock as a result of pressurization caused by underground nuclear testing. The annual rate of inflow into the carbonate rock averaged about 0.008 m/yr between 1962 and 2005, and declined from 0.005 m/yr in 2005 to 0.0005 m/yr by 2300.

K.J. Halford; R.J. Laczniak; D.L. Galloway

2005-10-07T23:59:59.000Z

215

Corrective Action Investigation Plan for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1 and No. 2  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 214 under the Federal Facility Agreement and Consent Order. Located in Areas 5, 11, and 25 of the Nevada Test Site, CAU 214 consists of nine Corrective Action Sites (CASs): 05-99-01, Fallout Shelters; 11-22-03, Drum; 25-99-12, Fly Ash Storage; 25-23-01, Contaminated Materials; 25-23-19, Radioactive Material Storage; 25-99-18, Storage Area; 25-34-03, Motor Dr/Gr Assembly (Bunker); 25-34-04, Motor Dr/Gr Assembly (Bunker); and 25-34-05, Motor Dr/Gr Assembly (Bunker). These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). The suspected contaminants and critical analyte s for CAU 214 include oil (total petroleum hydrocarbons-diesel-range organics [TPH-DRO], polychlorinated biphenyls [PCBs]), pesticides (chlordane, heptachlor, 4,4-DDT), barium, cadmium, chronium, lubricants (TPH-DRO, TPH-gasoline-range organics [GRO]), and fly ash (arsenic). The land-use zones where CAU 214 CASs are located dictate that future land uses will be limited to nonresidential (i.e., industrial) activities. The results of this field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the corrective action decision document.

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

2003-05-16T23:59:59.000Z

216

CHARACTERIZATION OF INDIVIDUAL CHEMICAL REACTIONS CONSUMING ACID DURING NUCLEAR WASTE PROCESSING AT THE SAVANNAH RIVER SITE - 136B  

DOE Green Energy (OSTI)

Conversion of legacy radioactive high-level waste at the Savannah River Site into a stable glass waste form involves a chemical pretreatment process to prepare the waste for vitrification. Waste slurry is treated with nitric and formic acids to achieve certain goals. The total quantity of acid added to a batch of waste slurry is constrained by the catalytic activity of trace noble metal fission products in the waste that can convert formic acid into hydrogen gas at many hundreds of times the radiolytic hydrogen generation rate. A large block of experimental process simulations were performed to characterize the chemical reactions that consume acid prior to hydrogen generation. The analysis led to a new equation for predicting the quantity of acid required to process a given volume of waste slurry.

Koopman, D.; Pickenheim, B.; Lambert, D.; Newell, J.; Stone, M.

2009-09-02T23:59:59.000Z

217

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

SciTech Connect

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

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

1996-10-01T23:59:59.000Z

218

CHARACTERIZATION OF PLUTONIUM CONTAMINATED SOILS FROM THE NEVADA TEST SITE IN SUPPORT OF EVALUATION OF REMEDIATION TECHNOLOGIES  

SciTech Connect

The removal of plutonium from Nevada Test Site (NTS) area soils has previously been attempted using various combinations of attrition scrubbing, size classification, gravity based separation, flotation, air flotation, segmented gate, bioremediation, magnetic separation and vitrification. Results were less than encouraging, but the processes were not fully optimized. To support additional vendor treatability studies soil from the Clean Slate II site (located on the Tonopah Test Range, north of the NTS) were characterized and tested. These particular soils from the NTS are contaminated primarily with plutonium-239/240 and Am-241. Soils were characterized for Pu-239/240, Am-241 and gross alpha. In addition, wet sieving and the subsequent characterization were performed on soils before and after attrition scrubbing to determine the particle size distribution and the distribution of Pu- 239/240 and gross alpha as a function of particle size. Sequential extraction was performed on untreated soil to provide information about how tightly bound the plutonium was to the soil. Magnetic separation was performed to determine if this could be useful as part of a treatment approach. The results indicate that about a 40% volume reduction of contaminated soil should be achievable by removing the >300 um size fraction of the soil. Attrition scrubbing does not effect particle size distribution, but does result in a slight shift of plutonium distribution to the fines. As such, attrition scrubbing may be able to slightly increase the ability to separate plutonium-contaminated particles from clean soil. This could add another 5-10% to the mass of the clean soil, bringing the total clean soil to 45-50%. Additional testing would be needed to determine the value of using attrition scrubbing as well as screening the soil through a sieve size slightly smaller than 300 um. Since only attrition scrubbing and wet sieving would be needed to attain this, it would be good to conduct this investigation. Magnetic separation did not work well. The sequential extraction studies indicated that a significant amount of plutonium was soluble in the ''organic'' and ''resistant'' extracts. As such chemical extraction based on these or similar extractants should also be considered as a possible treatment approach.

Torrao, Guilhermina; Carlino, Robert; Hoeffner, Steve L.; Navratil, James D.

2003-02-27T23:59:59.000Z

219

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

SciTech Connect

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

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

2011-11-01T23:59:59.000Z

220

Preliminary characterization of the F-Area Railroad Crosstie Pile at the Savannah River Site  

SciTech Connect

Historical information about the F-Area Railroad Crosstie Pile is limited. The unit is believed to have been a borrow area for earth fill that began receiving railroad crossties during the 1960s. The number of crossties at the unit began to increase significantly in 1984 when major repair of the SRS rail system was initiated. An estimated 100,000 used railroad crossties have accumulated at the unit since 1984. In an effort to determine the impact of the railroad crossties on the environment a total of 28 soil samples were collected from four test borings in March of 1991. Sample depths ranged from ground surface to 21.5 feet. Three of the borings were extended to the water table and groundwater samples were collected, one in an upgradient background'' area, and two downgradient from the unit. Few analytes were reported above detection limits. Test results are summarized in Section 4.0 and analytes not detected are summarized in Appendix A to this report. In three soil samples collected from depths between 10 and 21.5 feet, copper occurred at levels slightly above background. These copper values were detected in the sidegradient test boring and in the two downgradient test borings. Three organic analytes, acetone, pyridine, and Toluene, were reported above detection limits but well below drinking water standards (DWS) in all test borings, including the upgradient boring. Radionuclide activities were reported above background in both soil and water samples from all test borings. There do not appear to be any statistically significant trends in radionuclide activities with depth, or between upgradient or downgradient borings. The analytes detected in the test borings downgradient from the unit cannot be attributed to the railroad crosstie pile as they are not significantly different than the values reported for the upgradient, background test boring.

Not Available

1991-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Environmental assessment, Deaf Smith County site, Texas  

SciTech Connect

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

Not Available

1986-05-01T23:59:59.000Z

222

TSPA 1991: An initial total-system performance assessment for Yucca Mountain; Yucca Mountain Site Characterization Project  

Science Conference Proceedings (OSTI)

This report describes an assessment of the long-term performance of a repository system that contains deeply buried highly radioactive waste; the system is assumed to be located at the potential site at Yucca Mountain, Nevada. The study includes an identification of features, events, and processes that might affect the potential repository, a construction of scenarios based on this identification, a selection of models describing these scenarios (including abstraction of appropriate models from detailed models), a selection of probability distributions for the parameters in the models, a stochastic calculation of radionuclide releases for the scenarios, and a derivation of complementary cumulative distribution functions (CCDFs) for the releases. Releases and CCDFs are calculated for four categories of scenarios: aqueous flow (modeling primarily the existing conditions at the site, with allowances for climate change), gaseous flow, basaltic igneous activity, and human intrusion. The study shows that models of complex processes can be abstracted into more simplified representations that preserve the understanding of the processes and produce results consistent with those of more complex models.

Barnard, R.W.; Wilson, M.L.; Dockery, H.A.; Kaplan, P.G.; Eaton, R.R.; Bingham, F.W. [Sandia National Labs., Albuquerque, NM (United States); Gauthier, J.H.; Robey, T.H. [Spectra Research Inst., Albuquerque, NM (United States)

1992-07-01T23:59:59.000Z

223

Corrective Action Investigation Plan for Corrective Action Unit 5: Landfills, Nevada Test Site, Nevada (Rev. No.: 0) includes Record of Technical Change No. 1 (dated 9/17/2002)  

Science Conference Proceedings (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 5 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 5 consists of eight Corrective Action Sites (CASs): 05-15-01, Sanitary Landfill; 05-16-01, Landfill; 06-08-01, Landfill; 06-15-02, Sanitary Landfill; 06-15-03, Sanitary Landfill; 12-15-01, Sanitary Landfill; 20-15-01, Landfill; 23-15-03, Disposal Site. Located between Areas 5, 6, 12, 20, and 23 of the Nevada Test Site (NTS), CAU 5 consists of unlined landfills used in support of disposal operations between 1952 and 1992. Large volumes of solid waste were produced from the projects which used the CAU 5 landfills. Waste disposed in these landfills may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present at concentrations and locations that could potentially pose a threat to human health and/or the environment. During the 1992 to 1995 time frame, the NTS was used for various research and development projects including nuclear weapons testing. Instead of managing solid waste at one or two disposal sites, the practice on the NTS was to dispose of solid waste in the vicinity of the project. A review of historical documentation, process knowledge, personal interviews, and inferred activities associated with this CAU identified the following as potential contaminants of concern: volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls, pesticides, petroleum hydrocarbons (diesel- and gasoline-range organics), Resource Conservation and Recovery Act Metals, plus nickel and zinc. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution criteria and resolve the decision statements. Phase I will concentrate on geophysical surveys to confirm the presence or absence of disposed waste within a CAS and verify the boundaries of disposal areas; penetrate disposal feature covers via excavation and/or drilling; perform geodetic surveys; and be used to collect both soil and environmental samples for laboratory analyses. Phase II will deal only with those CASs where a contaminant of concern has been identified. This phase will involve the collection of additional soil and/or environmental samples for laboratory analyses. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

IT Corporation, Las Vegas, NV

2002-05-28T23:59:59.000Z

224

Characterization of the corrosion behavior of the carbon steel liner in Hanford Site single-shell tanks  

SciTech Connect

Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few single-shell tanks. Since that time there have been intertank transfers, evaporation, and chemical alterations of the waste. These activities have changed the character and the present composition of the waste is not well characterized. All conclusions and recommendations are made in the absence of relevant laboratory experimental data and tank inspection data. The report attempts to identify the failure mechanisms by a literature survey of carbon steel data in environments similar to the single-shell tank wastes, and by a review of the work performed at the Savannah River Site where similar wastes are stored in similar carbon steel tanks. Based on these surveys, and in the absence of data specific to Hanford single-shell tanks, it may be concluded that the single-shell tanks identified as leakers failed primarily by stress corrosion cracking due to the presence of high nitrate/low hydroxide wastes and residual stresses. In addition, some failures may be attributed to pitting under crevices in low hydroxide locations.

Anantatmula, R.P.; Schwenk, E.B. [Westinghouse Hanford Co., Richland, WA (United States); Danielson, M.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-06-01T23:59:59.000Z

225

SITE CHARACTERIZATION FOR CO  

NLE Websites -- All DOE Office Websites (Extended Search)

Stratigraphy Stratigraphy Pashin (2011) WILLIAM CRAWFORD GORGAS STEAM PLANT PROJECT TEAM The University of Alabama (Lead) Peter Clark, Eric Carlson, Andrew Goodliffe Geological Survey of Alabama Jack Pashin Rice University Mason Tomson University of Alabama at Birmingham Pete Walsh Southern Company, Alabama Power Richard Esposito Schlumberger Carbon Services Micro-g Lacoste SECARB OUTLINE * Project Overview * Geological Analysis * Geophysics * Simulation PROJECT GOALS Assess the risks associated with geologic carbon storage in the Black Warrior basin. Develop a regional plan and BPM for carbon sequestration. Analyze the CO 2 storage capacity and injectivity of stacked saline formations in the Cambrian-Pennsylvanian section of the Black Warrior basin. PROJECT OBJECTIVES

226

SITE CHARACTERIZATION FOR CO  

NLE Websites -- All DOE Office Websites (Extended Search)

* Constrain regional stress state and fracture direction and compare results with other methods *Identify potential cross-formational flow Integrate continuum and discrete...

227

Subsurface Site Characterization  

Office of Legacy Management (LM)

and limestone. The Green River Formation is the primary formation of interest for oil shale development in the region. Quaternary-age deposits of alluvium, mudflows, talus...

228

SITE CHARACTERIZATION FOR CO  

NLE Websites -- All DOE Office Websites (Extended Search)

Mason Tomson University of Alabama at Birmingham Pete Walsh Southern Company, Alabama Power Richard Esposito Schlumberger Carbon Services Micro-g Lacoste SECARB OUTLINE *...

229

SITE CHARACTERIZATION FOR CO  

NLE Websites -- All DOE Office Websites (Extended Search)

H. Lu, S. N. Work, J. Yu and M. B. Tomson SPE 130690. Scale prediction and inhibition for unconventional oil and gas production. SPE International Conference on Oilfield Scale held...

230

Characterization and Segmental Distribution of ‘251-Bolton-Hunterlabeled Substance P Binding Sites in Rat Spinal Cord’  

E-Print Network (OSTI)

Substance P (SP) is widely distributed in the spinal cord and has been implicated as a neurotransmitter in several spinal cord neuronal systems. To investigate SP receptors in the spinal cord, 1251-Bolton-Hunter-SP (‘*‘I-BH-SP) was used to identify and characterize spinal cord binding sites for the peptide. The binding of ‘*%BH-SP had the following characteristics: high affinity; time, temperature, and membrane concentration dependent; reversible; and saturable. The KS0 of SP in whole spinal cord was 0.46 nM as compared with 0.95, 60, and 150 nM for physalaemin, eledoisin, and kassinin. Four putative antagonists of SP were e 0.0001 times as potent as SP in inhibiting ‘*%BH-SP binding. lCsos were 5, 7.5, 7.0, and 45 PM for D-Pro*, D-Trp73s-SP; D-Pro*, D-Phe’, D-Trp’-SP; D-Arg’, D-Pro*, D-Tqfss, Leu”-SP; and D-Pro4, D-Trp7Vs3’0-SP(4-1 I), respectively.

Clivel G. Charlton; Cinda; J. Helke

1984-01-01T23:59:59.000Z

231

Corrective Action Investigation Plan for Corrective Action Unit 165: Areas 25 and 26 Dry Well and Washdown Areas, Nevada Test Site, Nevada (including Record of Technical Change Nos. 1, 2, and 3) (January 2002, Rev. 0)  

DOE Green Energy (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 165 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 165 consists of eight Corrective Action Sites (CASs): CAS 25-20-01, Lab Drain Dry Well; CAS 25-51-02, Dry Well; CAS 25-59-01, Septic System; CAS 26-59-01, Septic System; CAS 25-07-06, Train Decontamination Area; CAS 25-07-07, Vehicle Washdown; CAS 26-07-01, Vehicle Washdown Station; and CAS 25-47-01, Reservoir and French Drain. All eight CASs are located in the Nevada Test Site, Nevada. Six of these CASs are located in Area 25 facilities and two CASs are located in Area 26 facilities. The eight CASs at CAU 165 consist of dry wells, septic systems, decontamination pads, and a reservoir. The six CASs in Area 25 are associated with the Nuclear Rocket Development Station that operated from 1958 to 1973. The two CASs in Area 26 are associated with facilities constructed for Project Pluto, a series of nuclear reactor tests conducted between 1961 to 1964 to develop a nuclear-powered ramjet engine. Based on site history, the scope of this plan will be a two-phased approach to investigate the possible presence of hazardous and/or radioactive constituents at concentrations that could potentially pose a threat to human health and the environment. The Phase I analytical program for most CASs will include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons, polychlorinated biphenyls, and radionuclides. If laboratory data obtained from the Phase I investigation indicates the presence of contaminants of concern, the process will continue with a Phase II investigation to define the extent of contamination. Based on the results of Phase I sampling, the analytical program for Phase II investigation may be reduced. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

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

2002-01-09T23:59:59.000Z

232

Site Lead TQP Standard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of specific site safety functions. C. Must have the ability to provide an overall systematic assessment of site safety performance and to characterize the major issues and...

233

FY94 site characterization and multilevel well installation at a west Bear Creek Valley research site on the Oak Ridge Reservation  

SciTech Connect

The goals of this project are to collect data that will assist in determining what constitutes a representative groundwater sample in fractured shale typical of much of the geology underlying the ORR waste disposal sites, and to determine how monitoring-well construction and sampling methods impact the representativeness of the sample. This report details the FY94 field activities at a research site in west Bear Creek Valley on the Oak Ridge Reservation (ORR). These activities funded by the Energy Systems Groundwater Program Office through the Oak Ridge Reservation Hydrologic and Geologic Studies (ORRHAGS) task, focus on developing appropriate sampling protocols for the type of fractured media that underlies many of the ORR waste disposal sites. Currently accepted protocols were developed for porous media and are likely to result in nonrepresentative samples in fractured systems.

Moline, G.R. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.; Schreiber, M.E. [Univ. of Wisconsin, Madison, WI (United States). Dept. of Geology and Geophysics

1996-03-01T23:59:59.000Z

234

Corrective Action Investigation Plan for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada (Rev. 0) includes Record of Technical Change No. 1 (dated 8/28/2002), Record of Technical Change No. 2 (dated 9/23/2002), and Record of Technical Change No. 3 (dated 6/2/2004)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit 168 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 168 consists of a group of twelve relatively diverse Corrective Action Sites (CASs 25-16-01, Construction Waste Pile; 25-16-03, MX Construction Landfill; 25-19-02, Waste Disposal Site; 25-23-02, Radioactive Storage RR Cars; 25-23-18, Radioactive Material Storage; 25-34-01, NRDS Contaminated Bunker; 25-34-02, NRDS Contaminated Bunker; CAS 25-23-13, ETL - Lab Radioactive Contamination; 25-99-16, USW G3; 26-08-01, Waste Dump/Burn Pit; 26-17-01, Pluto Waste Holding Area; 26-19-02, Contaminated Waste Dump No.2). These CASs vary in terms of the sources and nature of potential contamination. The CASs are located and/or associated wit h the following Nevada Test Site (NTS) facilities within three areas. The first eight CASs were in operation between 1958 to 1984 in Area 25 include the Engine Maintenance, Assembly, and Disassembly Facility; the Missile Experiment Salvage Yard; the Reactor Maintenance, Assembly, and Disassembly Facility; the Radioactive Materials Storage Facility; and the Treatment Test Facility Building at Test Cell A. Secondly, the three CASs located in Area 26 include the Project Pluto testing area that operated from 1961 to 1964. Lastly, the Underground Southern Nevada Well (USW) G3 (CAS 25-99-16), a groundwater monitoring well located west of the NTS on the ridgeline of Yucca Mountain, was in operation during the 1980s. Based on site history and existing characterization data obtained to support the data quality objectives process, contaminants of potential concern (COPCs) for CAU 168 are primarily radionuclide; however, the COPCs for several CASs were not defined. To address COPC uncertainty, the analytical program for most CASs will include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons, polychlorinated biphenyls, and radionuclides. Upon reviewing historical data and current site conditions, it has been determined that no further characterization is required at USW G3 (CAS 25-99-16) to select the appropriate corrective action. A cesium-137 source was encased in cement within the vadous zone during the drilling of the well (CAS 25-99-16). A corrective action of closure in place with a land-use restriction for drilling near USW G3 is appropriate. This corrective action will be documented in the Corrective Action Decision Document (CADD) for CAU 168. The results of the remaining field investigation will support a defensible evaluation of corrective action alternatives for the other CASs within CAU 168 in this CADD.

U.S. Department of Energy, National Nuclear Security Administration Nevada

2001-11-21T23:59:59.000Z

235

DRAFT ENVIRONMENTAL ASSESSMENT FOR CHARACTERIZATION OF THE HANFORD SITE PURSUANT TO THE NUCLEAR WASTE POLICY ACT OF 1982  

E-Print Network (OSTI)

step-by-step process by which the President, Congress, affected individual states and Indian tribes, U.S. Department of Energy (DOE), and other Federal agencies can work together in the siting, construction, and operation of a high-level nuclear waste repository. The DOE is required by Section 116(a) of the Act to identify states having potentially acceptable sites for a waste repository. A potentially acceptable site is defined by the Act as...any site at which, after geologic studies and field mapping but before detailed geologic data gathering, the Department undertakes preliminary drilling and geophysical testing for the definition of the site location. " By letter dated February 2, 1983, the Secretary of the DOE notified the Governor and Legislature of the State of Washington that the Hanford Site, near

Public Law; Public Law; Ooe-richland Wa Foreword

1983-01-01T23:59:59.000Z

236

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

SciTech Connect

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

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

1984-11-01T23:59:59.000Z

237

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

Science Conference Proceedings (OSTI)

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

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

2012-09-28T23:59:59.000Z

238

Corrective Action Investigation Plan for Corrective Action Unit 527: Horn Silver Mine, Nevada Test Site, Nevada: Revision 1 (Including Records of Technical Change No.1, 2, 3, and 4)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 527, Horn Silver Mine, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 527 consists of one Corrective Action Site (CAS): 26-20-01, Contaminated Waste Dump No.1. The site is located in an abandoned mine site in Area 26 (which is the most arid part of the NTS) approximately 65 miles northwest of Las Vegas. Historical documents may refer to this site as CAU 168, CWD-1, the Wingfield mine (or shaft), and the Wahmonie mine (or shaft). Historical documentation indicates that between 1959 and the 1970s, nonliquid classified material and unclassified waste was placed in the Horn Silver Mine's shaft. Some of the waste is known to be radioactive. Documentation indicates that the waste is present from 150 feet to the bottom of the mine (500 ft below ground surface). This CAU is being investigated because hazardous constituents migrating from materials and/or wastes disposed of in the Horn Silver Mine may pose a threat to human health and the environment as well as to assess the potential impacts associated with any potential releases from the waste. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office

2002-12-06T23:59:59.000Z

239

Corrective Action Decision Document for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of recommended corrective action alternatives (CAAs) to facilitate the closure of Corrective Action Unit (CAU)168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 25 and 26 at the NTS in Nevada, CAU 168 is comprised of twelve Corrective Action Sites (CASs). Review of data collected during the corrective action investigation, as well as consideration of current and future operations in Areas 25 and 26 of the NTS, led the way to the development of three CAAs for consideration: Alternative 1 - No Further Action; Alternative 2 - Clean Closure; and Alternative 3 - Close in Place with Administrative Controls. As a result of this evaluation, a combination of all three CAAs is recommended for this CAU. Alternative 1 was the preferred CAA for three CASs, Alternative 2 was the preferred CAA for six CASs (and nearly all of one other CAS), and Alternative 3 was the preferred CAA for two CASs (and a portion of one other CAS) to complete the closure at the CAU 168 sites. These alternatives were judged to meet all requirements for the technical components evaluated as well as all applicable state and federal regulations for closure of the sites and elimination of potential future exposure pathways to the contaminated soils at CAU 168.

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

2003-08-08T23:59:59.000Z

240

Characterization  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization Characterization of the Rust Fungus, Puccinia emaculata, and Evaluation of Genetic Variability for Rust Resistance in Switchgrass Populations Srinivasa Rao Uppalapati & Desalegn D. Serba & Yasuhiro Ishiga & Les J. Szabo & Shipra Mittal & Hem S. Bhandari & Joseph H. Bouton & Kirankumar S. Mysore & Malay C. Saha # The Author(s) 2012. This article is published with open access at Springerlink.com Abstract Several fungal pathogens have been identified on ornamental and native stands of switchgrass (Panicum virga- tum L.). Diseases of switchgrass, particularly rust, have been largely neglected and are likely to become the major limiting factor to biomass yield and quality, especially when monocul- tured over a large acreage. Based on teliospore morphology and internal transcribed spacer-based diagnostic primers, the rust pathogen collected

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
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241

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

SciTech Connect

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

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

2009-09-24T23:59:59.000Z

242

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

Science Conference Proceedings (OSTI)

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.

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

2011-04-01T23:59:59.000Z

243

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

Science Conference Proceedings (OSTI)

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

Lance Prothro, Sigmund Drellack, Margaret Townsend

2009-03-25T23:59:59.000Z

244

Preliminary numerical modeling for the G-Tunnel welded tuff mining experiment; Yucca Mountain site characterization project  

Science Conference Proceedings (OSTI)

Yucca Mountain, located in Southern Nevada, is to be considered as a potential site for a nuclear waste repository. Located in Rainier Mesa on the Nevada Test Site, G-Tunnel has been the site of a series of experiments, part of whose purpose is to evaluate measurement techniques for rock mechanics before testing in the Exploratory Shaft. Rainier Mesa is composed of welded and nonwelded tuffs that have thermal and mechanical properties and stress states similar to those of tuffs expected to be encountered at Yucca Mountain. A series of finite element calculations were performed to aid in designing instrumentation for the experiments in G-Tunnel and later to correlate with measured data. In this report are presented the results of the preliminary finite element calculations performed in conjunction with experimental measurements of drift convergence, or closure, and rock mass relaxation zones made before, during, and after completing the welded tuff mining experiment in G-Tunnel. Tape extensometer measurements of drift convergences and measurements determined by multiple point borehole extensometers are compared with corresponding calculated values using linear elastic and jointed rock material models. 9 refs., 25 figs., 7 tabs.

Johnson, R.L.; Bauer, S.J.

1991-09-01T23:59:59.000Z

245

Preliminary Site Characterization Report, Rulison Site, Colorado...  

Office of Legacy Management (LM)

The most notable unit of the upper Green River, the Parachute Creek member, is an oil shale. This formation is composed of mostly shale and marlstone with minor amounts of...

246

A quantitative analysis of the flame produced by a gas-fueled propellant simulating burner including: soot field characterization, temperature diagnostic techniques, spectral analysis, heat flux, and aluminum particle combustion.  

E-Print Network (OSTI)

??This study details the characterization and implementation of a burner devised to simulate solid propellant fires. The burner is designed with the ability to introduce… (more)

Jackson, Matt

2007-01-01T23:59:59.000Z

247

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

Science Conference Proceedings (OSTI)

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

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

2009-09-25T23:59:59.000Z

248

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

Science Conference Proceedings (OSTI)

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

Not Available

1987-12-01T23:59:59.000Z

249

Chapter 3: Building Siting  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

: Building Siting : Building Siting Site Issues at LANL Site Inventory and Analysis Site Design Transportation and Parking LANL | Chapter 3 Site Issues at LANL Definitions and related documents Building Siting Laboratory site-wide issues include transportation and travel distances for building occupants, impacts on wildlife corridors and hydrology, and energy supply and distribution limitations. Decisions made during site selec- tion and planning impact the surrounding natural habitat, architectural design integration, building energy con- sumption, occupant comfort, and occupant productivity. Significant opportunities for creating greener facilities arise during the site selection and site planning stages of design. Because LANL development zones are pre- determined, identify the various factors affecting devel-

250

YUCCA MOUNTAIN SITE DESCRIPTION  

SciTech Connect

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

A.M. Simmons

2004-04-16T23:59:59.000Z

251

YUCCA MOUNTAIN SITE DESCRIPTION  

SciTech Connect

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

A.M. Simmons

2004-04-16T23:59:59.000Z

252

The application of borehole logging to characterize the hydrogeology of the Faultless site, Central Nevada Test Area  

SciTech Connect

The Central Nevada Test Area was the site of the Faultless underground nuclear test that could be a source of radionuclide contamination to aquifers in Hot Creek Valley, Nevada. Field studies in 1992 and 1993 have used hydrologic logging and water sampling to determine the adequacy of the current groundwater monitoring network and the status of water-level recovery to pre-shot levels in the nuclear chimney. The field studies have determined that there is a possibility for contaminant migration away from the Faultless event though the pre-event water level has not been attained, while new data raise questions about the ability of the current monitoring network to detect migration. Hydrologic logs from the postshot hole (drilled into the chimney created by the nuclear detonation) reveal inflow around 485 m below land surface. The physical and chemical characteristics of the inflow water indicate that its source is much deeper in the chimney, perhaps driven upward in a convection cell generated by heat near the nuclear cavity. Logging and sampling at monitoring wells HTH-1 and HTH-2 revealed that the completion of HTH-1 may be responsible for its elevated water level (as compared to pre-nuclear test levels) and may have also created a local mound in the water table in the alluvium that accounts for higher post-test water levels at HTH-2. This mound would serve to divert flow around the monitoring wells, so that only migration of contaminants through the underlying, higher pressure, volcanic units is currently monitored. A hydraulic high found in an abandoned hole located between the nuclear chimney and the monitoring wells further reduces the likelihood of HTH-1 or HTH-2 intercepting contaminant migration.

Chapman, J.B.; Mihevc, T.M.; Lyles, B.F.

1994-08-01T23:59:59.000Z

253

Plutonium carbonate speciation changes as measured in dilute solutions with photoacoustic spectroscopy: Yucca Mountain Site Characterization Program Milestone report 3350  

SciTech Connect

The stability fields for dilute Pu-carbonate species versus pH (8.4 to 12.0) and total carbonate concentrations (3 mM to 1.0 M) have been mapped-out using photoacoustic absorption spectroscopy (PAS). At least four different plutonium species, characterized by absorption peaks at 486, 492, 500, and 513 rim, have been found. A redox change to a Pu(VI) complex can not account for the speciation change associated with the first two spectra (486 and 492 nm peaks). Moreover, the data are consistent with what is predicted from a previous YMP milestone. This previous study was performed under very different conditions of plutonium concentration and carbonate/pH changes, and extension of these conditions to much lower Pu concentrations and to more neutral pHs was made possible with PAS spectroscopy. These new results reinforce the previous results by extending the range of direct observation and by eliminating other possibilities such as dimerization/polymerization reactions. As bicarbonate concentration is increased from .01 M to 1.0 M at pH=8.4 to 8.9, predominately [Pu(OH){sub x+1}(CO{sub 3}){sub y}]{sup 4-(x+2y)} (492 nm peak) is converted to [Pu(OH){sub x}(CO{sub 3}){sub y+l}]{sup 4-(x+2y+2)} (486 nm peak). The starting stoichiometry (x and y values) remain undetermined, but the effect of ionic strength and temperature indicate that the 486 nm species is highly charged, and therefore x+2y{ge}3. The temperature effect on the equilibrium between these two species was also investigated, with the species giving rise to the 486 nm peak reversibly losing importance at elevated (50 and 75{degrees}C temperatures).

Tait, C.D.; Ekberg, S.A.; Palmer, P.D.; Morris, D.E.

1995-05-01T23:59:59.000Z

254

Initial field testing definition of subsurface sealing and backfilling tests in unsaturated tuff; Yucca Mountain Site Characterization Project  

SciTech Connect

This report contains an initial definition of the field tests proposed for the Yucca Mountain Project repository sealing program. The tests are intended to resolve various performance and emplacement concerns. Examples of concerns to be addressed include achieving selected hydrologic and structural requirements for seals, removing portions of the shaft liner, excavating keyways, emplacing cementitious and earthen seals, reducing the impact of fines on the hydraulic conductivity of fractures, efficient grouting of fracture zones, sealing of exploratory boreholes, and controlling the flow of water by using engineered designs. Ten discrete tests are proposed to address these and other concerns. These tests are divided into two groups: Seal component tests and performance confirmation tests. The seal component tests are thorough small-scale in situ tests, the intermediate-scale borehole seal tests, the fracture grouting tests, the surface backfill tests, and the grouted rock mass tests. The seal system tests are the seepage control tests, the backfill tests, the bulkhead test in the Calico Hills unit, the large-scale shaft seal and shaft fill tests, and the remote borehole sealing tests. The tests are proposed to be performed in six discrete areas, including welded and non-welded environments, primarily located outside the potential repository area. The final selection of sealing tests will depend on the nature of the geologic and hydrologic conditions encountered during the development of the Exploratory Studies Facility and detailed numerical analyses. Tests are likely to be performed both before and after License Application.

Fernandez, J.A. [Sandia National Labs., Albuquerque, NM (United States); Case, J.B.; Tyburski, J.R. [I. T. Corp., Albuquerque, NM (United States)

1993-05-01T23:59:59.000Z

255

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA  

Science Conference Proceedings (OSTI)

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

2005-07-01T23:59:59.000Z

256

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

Science Conference Proceedings (OSTI)

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

NONE

1995-03-01T23:59:59.000Z

257

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

SciTech Connect

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

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

1992-07-01T23:59:59.000Z

258

Converting Site Electricity to Include Generation and Transmission...  

U.S. Energy Information Administration (EIA) Indexed Site

Evaluation of Electricity Consumption in the Manufacturing Division The energy intensities presented in this report do not reflect adjustments for losses in electricity generation...

259

Preliminary characterization of the F-Area Railroad Crosstie Pile at the Savannah River Site. Revision 1  

SciTech Connect

Historical information about the F-Area Railroad Crosstie Pile is limited. The unit is believed to have been a borrow area for earth fill that began receiving railroad crossties during the 1960s. The number of crossties at the unit began to increase significantly in 1984 when major repair of the SRS rail system was initiated. An estimated 100,000 used railroad crossties have accumulated at the unit since 1984. In an effort to determine the impact of the railroad crossties on the environment a total of 28 soil samples were collected from four test borings in March of 1991. Sample depths ranged from ground surface to 21.5 feet. Three of the borings were extended to the water table and groundwater samples were collected, one in an upgradient ``background`` area, and two downgradient from the unit. Few analytes were reported above detection limits. Test results are summarized in Section 4.0 and analytes not detected are summarized in Appendix A to this report. In three soil samples collected from depths between 10 and 21.5 feet, copper occurred at levels slightly above background. These copper values were detected in the sidegradient test boring and in the two downgradient test borings. Three organic analytes, acetone, pyridine, and Toluene, were reported above detection limits but well below drinking water standards (DWS) in all test borings, including the upgradient boring. Radionuclide activities were reported above background in both soil and water samples from all test borings. There do not appear to be any statistically significant trends in radionuclide activities with depth, or between upgradient or downgradient borings. The analytes detected in the test borings downgradient from the unit cannot be attributed to the railroad crosstie pile as they are not significantly different than the values reported for the upgradient, background test boring.

Not Available

1991-10-01T23:59:59.000Z

260

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

Science Conference Proceedings (OSTI)

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

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

1992-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Hanford Site Environmental Report for Calendar Year 2005  

Science Conference Proceedings (OSTI)

This report, published annually since 1958, includes information and summary analytical data that (1) provide an overview of activities at the Hanford Site during calendar year 2005; (2) demonstrate the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and U.S. Department of Energy (DOE) policies and directives; (3) characterize Hanford Site environmental management performance; and (4) highlight significant environmental programs.

Poston, Ted M.; Hanf, Robert W.; Dirkes, Roger L.; Morasch, Launa F.

2006-09-28T23:59:59.000Z

262

Hanford Site Environmental Report for Calendar Year 2004  

Science Conference Proceedings (OSTI)

This report, published annually since 1958, includes information and summary analytical data that (1) provide an overview of activities at the Hanford Site during calendar year 2003; (2) demonstrate the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and U.S. Department of Energy (DOE) policies and directives; (3) characterize Hanford Site environmental management performance; and (4) highlight significant environmental programs.

Poston, Ted M.; Hanf, Robert W.; Dirkes, Roger L.

2005-09-29T23:59:59.000Z

263

Hanford Site Environmental Report for Calendar Year 2008  

Science Conference Proceedings (OSTI)

The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2009 information is included where appropriate.

Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

2009-09-15T23:59:59.000Z

264

Hanford Site Environmental Report for Calendar Year 2007  

Science Conference Proceedings (OSTI)

The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights signifi cant environmental and public protection programs and efforts. Some historical and early 2008 information is included where appropriate.

Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

2008-06-05T23:59:59.000Z

265

Hanford Site Environmental Report for Calendar Year 2009  

Science Conference Proceedings (OSTI)

The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2010 information is included where appropriate.

Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

2010-09-01T23:59:59.000Z

266

Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site  

Science Conference Proceedings (OSTI)

A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site.

Wike, L.D.

2000-08-17T23:59:59.000Z

267

Waste site grouping for 200 Areas soil investigations  

Science Conference Proceedings (OSTI)

The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models.

NONE

1997-01-01T23:59:59.000Z

268

Characterization and Alteration of Wettability States of Alaskan Reserviors to Improve Oil Recovery Efficiency (including the within-scope expansion based on Cyclic Water Injection - a pulsed waterflood for Enhanced Oil Recovery)  

SciTech Connect

Numerous early reports on experimental works relating to the role of wettability in various aspects of oil recovery have been published. Early examples of laboratory waterfloods show oil recovery increasing with increasing water-wetness. This result is consistent with the intuitive notion that strong wetting preference of the rock for water and associated strong capillary-imbibition forces gives the most efficient oil displacement. This report examines the effect of wettability on waterflooding and gasflooding processes respectively. Waterflood oil recoveries were examined for the dual cases of uniform and non-uniform wetting conditions. Based on the results of the literature review on effect of wettability and oil recovery, coreflooding experiments were designed to examine the effect of changing water chemistry (salinity) on residual oil saturation. Numerous corefloods were conducted on reservoir rock material from representative formations on the Alaska North Slope (ANS). The corefloods consisted of injecting water (reservoir water and ultra low-salinity ANS lake water) of different salinities in secondary as well as tertiary mode. Additionally, complete reservoir condition corefloods were also conducted using live oil. In all the tests, wettability indices, residual oil saturation, and oil recovery were measured. All results consistently lead to one conclusion; that is, a decrease in injection water salinity causes a reduction in residual oil saturation and a slight increase in water-wetness, both of which are comparable with literature observations. These observations have an intuitive appeal in that water easily imbibes into the core and displaces oil. Therefore, low-salinity waterfloods have the potential for improved oil recovery in the secondary recovery process, and ultra low-salinity ANS lake water is an attractive source of injection water or a source for diluting the high-salinity reservoir water. As part of the within-scope expansion of this project, cyclic water injection tests using high as well as low salinity were also conducted on several representative ANS core samples. These results indicate that less pore volume of water is required to recover the same amount of oil as compared with continuous water injection. Additionally, in cyclic water injection, oil is produced even during the idle time of water injection. It is understood that the injected brine front spreads/smears through the pores and displaces oil out uniformly rather than viscous fingering. The overall benefits of this project include increased oil production from existing Alaskan reservoirs. This conclusion is based on the performed experiments and results obtained on low-salinity water injection (including ANS lake water), vis-a-vis slightly altering the wetting conditions. Similarly, encouraging cyclic water-injection test results indicate that this method can help achieve residual oil saturation earlier than continuous water injection. If proved in field, this would be of great use, as more oil can be recovered through cyclic water injection for the same amount of water injected.

Abhijit Dandekar; Shirish Patil; Santanu Khataniar

2008-12-31T23:59:59.000Z

269

Assessment of speciation techniques including the application of photoacoustic spectroscopy  

Science Conference Proceedings (OSTI)

This document describes laboratory experiments that compare chromatographic and spectroscopic methods for rapidly characterizing ionic species in detail. These techniques were tested on various radioactive ion systems to develop a rapid, accurate approach to site characterization for use with Remedial Action Programs. Promising techniques were evaluated. 9 refs., 16 figs., 2 tabs.

Bucher, J.; Gehmecker, H.; Edelstein, N.

1985-08-01T23:59:59.000Z

270

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

SciTech Connect

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites. According to the Uranium Mill Tailings Radiation Control Act of 1978, (UMTRCA) the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined this assessment shall include information on hydrogeologic site characterization. The water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards is presented in Attachment 4. Site characterization activities discussed in this section include: Characterization of the hydrogeologic environment; characterization of existing groundwater quality; definition of physical and chemical characteristics of the potential contaminant source; and description of local water resources.

Not Available

1991-12-01T23:59:59.000Z

271

Calabozo Site Image #1  

NLE Websites -- All DOE Office Websites (Extended Search)

CLB-1: General view of the Trachypogon savanna at the Calabozo grassland site, Venezuela. (Trees include Curatella americana, Bowdichia virgilioides and Byrsonima crassifolia....

272

ORISE: Characterization surveys  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization surveys Characterization surveys An ORISE technicians performs a characterization survey The Oak Ridge Institute for Science and Education (ORISE) performs independent, objective characterization surveys to define the extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide guidance to determine the best remediation procedures and are a cost-effective method of ensuring a site meets preliminary regulatory standards. ORISE designs characterization surveys using the data quality objectives process. This approach focuses on the particular objective of characterization, and ensures that only the data needed to address the characterization decisions are collected. Data collection efforts are

273

Hanford Site Environmental Report for Calendar Year 2010  

Science Conference Proceedings (OSTI)

The Hanford Site environmental report is prepared annually for the U.S. Department of Energy (DOE) in accordance with regulatory requirements. The report provides an overview of activities at the Hanford Site; demonstrates the status of the site's compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2011 information is included where appropriate.

Poston, Ted M.; Duncan, Joanne P.; Dirkes, Roger L.

2011-07-12T23:59:59.000Z

274

Complexity of Groundwater Contaminants at DOE Sites  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) is responsible for the remediation and long-term stewardship of one of the world's largest groundwater contamination portfolios, with a significant number of plumes containing various contaminants, and considerable total mass and activity. As of 1999, the DOE's Office of Environmental Management was responsible for remediation, waste management, or nuclear materials and facility stabilization at 144 sites in 31 states and one U.S. territory, out of which 109 sites were expected to require long-term stewardship. Currently, 19 DOE sites are on the National Priority List. The total number of contaminated plumes on DOE lands is estimated to be 10,000. However, a significant number of DOE sites have not yet been fully characterized. The most prevalent contaminated media are groundwater and soil, although contaminated sediment, sludge, and surface water also are present. Groundwater, soil, and sediment contamination are present at 72% of all DOE sites. A proper characterization of the contaminant inventory at DOE sites is critical for accomplishing one of the primary DOE missions -- planning basic research to understand the complex physical, chemical, and biological properties of contaminated sites. Note that the definitions of the terms 'site' and 'facility' may differ from one publication to another. In this report, the terms 'site,' 'facility' or 'installation' are used to identify a contiguous land area within the borders of a property, which may contain more than one plume. The term 'plume' is used here to indicate an individual area of contamination, which can be small or large. Even though several publications and databases contain information on groundwater contamination and remediation technologies, no statistical analyses of the contaminant inventory at DOE sites has been prepared since the 1992 report by Riley and Zachara. The DOE Groundwater Data Base (GWD) presents data as of 2003 for 221 groundwater plumes at 60 DOE sites and facilities. Note that Riley and Zachara analyzed the data from only 18 sites/facilities including 91 plumes. In this paper, we present the results of statistical analyses of the data in the GWD as guidance for planning future basic and applied research of groundwater contaminants within the DOE complex. Our analyses include the evaluation of a frequency and ranking of specific contaminants and contaminant groups, contaminant concentrations/activities and total contaminant masses and activities. We also compared the results from analyses of the GWD with those from the 1992 report by Riley and Zachara. The difference between our results and those summarized in the 1992 report by Riley and Zachara could be caused by not only additional releases, but also by the use of modern site characterization methods, which more accurately reveal the extent of groundwater contamination. Contaminated sites within the DOE complex are located in all major geographic regions of the United States, with highly variable geologic, hydrogeologic, soil, and climatic conditions. We assume that the information from the 60 DOE sites included in the GWD are representative for the whole DOE complex. These 60 sites include the major DOE sites and facilities, such as Rocky Flats Environmental Technology Site, Colorado; Idaho National Laboratory, Idaho; Savannah River Site, South Carolina; Oak Ridge Reservation, Tennessee; and Hanford Reservation, Washington. These five sites alone ccount for 71% of the value of the remediation work.

Hazen, T.C.; Faybishenko, B.; Jordan, P.

2010-12-03T23:59:59.000Z

275

Buildings Included on EMS Reports"  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of Legacy Management Office of Legacy Management Buildings Included on EMS Reports" "Site","Property Name","Property ID","GSF","Incl. in Water Baseline (CY2007)","Water Baseline (sq. ft.)","Water CY2008 (sq. ft.)","Water CY2009 (sq. ft.)","Water Notes","Incl. in Energy Baseline (CY2003)","Energy Baseline (sq. ft.)","CY2008 Energy (sq. ft.)","CY2009 Energy (sq. ft.)","Energy Notes","Included as Existing Building","CY2008 Existing Building (sq. ft.)","Reason for Building Exclusion" "Column Totals",,"Totals",115139,,10579,10579,22512,,,3183365,26374,115374,,,99476 "Durango, CO, Disposal/Processing Site","STORAGE SHED","DUD-BLDG-STORSHED",100,"no",,,,,"no",,,,"OSF","no",,"Less than 5,000 GSF"

276

Nevada Test Site Waste Acceptance Criteria  

Science Conference Proceedings (OSTI)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

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

2005-10-01T23:59:59.000Z

277

Hanford Site Groundwater Monitoring for Fiscal Year 2006  

SciTech Connect

This report presents the results of groundwater monitoring for FY 2006 on DOE's Hanford Site. Results of groundwater remediation, vadose zone monitoring, and characterization are summarized. DOE monitors groundwater at the Hanford Site to fulfill a variety of state and federal regulations, including the Atomic Energy Act (AEA), the Resource Conservation and Recovery Act (RCRA), the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), and Washington Administrative Code (WAC).

Hartman, Mary J.; Morasch, Launa F.; Webber, William D.

2007-03-01T23:59:59.000Z

278

Pantex Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Pantex Site Pantex Site The primary mission of the Pantex Plant is the assembly, disassembly, testing, and evaluation of nuclear wespons in support of the NNSA stockpile...

279

Characterizing the performance of ecosystem models across time scales: A spectral analysis of the North American Carbon Program site-level synthesis  

Science Conference Proceedings (OSTI)

Ecosystem models are important tools for diagnosing the carbon cycle and projecting its behavior across space and time. Most assessments of model performance occur at individual temporal scales, but ecosystems respond to drivers at multiple time scales. Spectral methods, such as wavelet analyses, present an alternative approach that enables the identification of the dominant time scales contributing to model performance in the frequency domain. In this study we used wavelet analyses to synthesize the performance of twenty-one ecosystem models at nine eddy-covariance towers as part of the North American Carbon Program's site-level inter-comparison. This study expands upon previous single-site and single-model analyses to determine what patterns of model failure are consistent across a diverse range of models and sites.

Dietze, Michael; Vargas, Rodrigo; Richardson, Andrew D.; Stoy, Paul C.; Barr, Alan; Anderson, Ryan; Arain, M. A.; Baker, Ian; Black, T. Andrew; Chen, Jing Ming; Ciais, Philippe; Flanagan, Lawrence; Gough, Christopher; Grant, R. F.; Hollinger, D.; Izaurralde, Roberto C.; Kucharik, Chris; Lafleur, Peter; Liu, Shuguang; Lokupitiya, Erandathie; Luo, Yiqi; Munger, J. W.; Peng, Changhui; Poulter, Benjamin; Price, David T.; Ricciuto, Daniel M.; Riley, William; Sahoo, Alok Kumar; Schaefer, Kevin; Suyker, Andrew E.; Tian, Hanqin; Tonitto, Christine; Verbeeck, Hans; Verma, Shashi B.; Wang, Weifeng; Weng, Ensheng

2011-12-20T23:59:59.000Z

280

ORISE: Characterization surveys  

NLE Websites -- All DOE Office Websites (Extended Search)

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

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Mound facility physical characterization  

Science Conference Proceedings (OSTI)

The purpose of this report is to provide a baseline physical characterization of Mound`s facilities as of September 1993. The baseline characterizations are to be used in the development of long-term future use strategy development for the Mound site. This document describes the current missions and alternative future use scenarios for each building. Current mission descriptions cover facility capabilities, physical resources required to support operations, current safety envelope and current status of facilities. Future use scenarios identify potential alternative future uses, facility modifications required for likely use, facility modifications of other uses, changes to safety envelope for the likely use, cleanup criteria for each future use scenario, and disposition of surplus equipment. This Introductory Chapter includes an Executive Summary that contains narrative on the Functional Unit Material Condition, Current Facility Status, Listing of Buildings, Space Plans, Summary of Maintenance Program and Repair Backlog, Environmental Restoration, and Decontamination and Decommissioning Programs. Under Section B, Site Description, is a brief listing of the Site PS Development, as well as Current Utility Sources. Section C contains Site Assumptions. A Maintenance Program Overview, as well as Current Deficiencies, is contained within the Maintenance Program Chapter.

Tonne, W.R.; Alexander, B.M.; Cage, M.R.; Hase, E.H.; Schmidt, M.J.; Schneider, J.E.; Slusher, W.; Todd, J.E.

1993-12-01T23:59:59.000Z

282

Considered Sites | Department of Energy  

Office of Legacy Management (LM)

Sites » Considered Sites Sites » Considered Sites Considered Sites View Considered Sites View Other Sites DOE maintains the Considered Sites Database to provide information to the public about sites that were formerly used in the nation's nuclear weapons and early atomic energy programs and that had the potential for residual radioactive contamination on site. Formerly Utilized Sites Remedial Action Program The U.S. Atomic Energy Commission (AEC) established the Formerly Utilized Sites Remedial Action Program (FUSRAP) in March 1974 under the authority of the Atomic Energy Act of 1954 to identify, investigate, and take appropriate cleanup action at sites where work was performed in support of the Manhattan Engineer District (MED) and early AEC programs. Site activities included uranium ore storage and processing, uranium metal

283

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

SciTech Connect

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

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

1991-12-01T23:59:59.000Z

284

Site Environmental Report, 1993  

SciTech Connect

The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, ``General Environmental Protection Program.`` This 1993 SER provides the general public as well as scientists and engineers with the results from the site`s ongoing Environmental Monitoring Program. Also included in this report is information concerning the site`s progress toward achieving full compliance with requirements set forth by DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in the Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here.

Not Available

1994-06-01T23:59:59.000Z

285

Areal power density: A preliminary examination of underground heat transfer in a potential Yucca Mountain repository and recommendations for thermal design approaches; Yucca Mountain Site Characterization Project  

SciTech Connect

The design of the potential Yucca Mountain repository is subject to many thermal goals related to the compliance of the site with federal regulations. This report summarizes a series of sensitivity studies that determined the expected temperatures near the potential repository. These sensitivity studies were used to establish an efficient loading scheme for the spent fuel canisters and a maximum areal power density based strictly on thermal goals. Given the current knowledge of the site, a design-basis areal power density of 80 kW/acre can be justified based on thermal goals only. Further analyses to investigate the impacts of this design-basis APD on mechanical and operational aspects of the potential repository must be undertaken before a final decision is made.

Hertel, E.S. Jr.; Ryder, E.E.

1991-11-01T23:59:59.000Z

286

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

Science Conference Proceedings (OSTI)

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

David A. King

2011-10-10T23:59:59.000Z

287

Use of a Heated Transfer Line-Membrane Interface Probe to Characterize Polycyclic Aromatic Hydrocarbons at a Manufactured Gas Plant Site  

Science Conference Proceedings (OSTI)

This report describes bench-scale and field pilot tests of a system integrating a heated transfer line (HTL) and a membrane interface probe (MIP) with commercially available analytical instruments and software. Driven into the subsurface by a cone penetrometer, the HTL-MIP thermally extracts organic compounds from saturated and unsaturated soils at former manufactured gas plant (MGP) sites. The integrated system detects compounds using a screening photo-ionization detector (PID) and analyzes them in situ...

2008-04-30T23:59:59.000Z

288

Geochemical Characterization Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect

This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank (SST) farms at the U.S. Department of Energy’s (DOE’s) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical information available for the vadose zone beneath the SST farms and the Integrated Disposal Facility (IDF).

Cantrell, Kirk J.; Brown, Christopher F.; Serne, R. Jeffrey; Krupka, Kenneth M.

2008-01-07T23:59:59.000Z

289

Summary of the Hanford Site Environmental Report for Calendar Year 2008  

SciTech Connect

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2008." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2009 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2009-09-15T23:59:59.000Z

290

Summary of the Hanford Site Environmental Report for Calendar Year 2009  

Science Conference Proceedings (OSTI)

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2009." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights significant environmental and public protection programs and efforts. Some historical and early 2010 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2010-09-30T23:59:59.000Z

291

Summary of the Hanford Site Environmental Report for Calendar Year 2007  

SciTech Connect

This summary booklet summarizes the "Hanford Site Environmental Report for Calendar Year 2007." The Hanford Site environmental report, published annually since 1958, includes information and summary data that provide an overview of activities at the U.S. Department of Energy's (DOE) Hanford Site. The Hanford Site environmental report provides an overview of activities at the site; demonstrates the status of the site’s compliance with applicable federal, state, and local environmental laws and regulations, executive orders, and DOE policies and directives; and summarizes environmental data that characterize Hanford Site environmental management performance. The report also highlights signifi cant environmental and public protection programs and efforts. Some historical and early 2008 information is included where appropriate.

Duncan, Joanne P.; Poston, Ted M.; Dirkes, Roger L.

2008-09-10T23:59:59.000Z

292

Material Consolidation, Rendering, and Disposal Studies of Gas Holders at Former Manufactured Gas Plant Sites  

Science Conference Proceedings (OSTI)

This report presents results of full-scale field implementation studies conducted in conjunction with an evaluation of EPRI-sponsored bench-scale mixing tests. The study was designed to complement bench-scale mixing studies that correlated those results to full-scale remedial actions at former manufactured gas plant (MGP) sites. The field implementation study included a review of potentially applicable remedial approaches, site characterization, bench-scale treatability tests, and results of site remedia...

2001-12-13T23:59:59.000Z

293

Use of Proton-Transfer-Reaction Mass Spectrometry to Characterize Volatile Organic Compound Sources at the La Porte Super Site During the Texas Air Quality Study 2000  

SciTech Connect

Proton-transfer-reaction mass spectrometry (PTR-MS) was deployed for continuous real-time monitoring of volatile organic compounds (VOCs) at a site near the Houston Ship Channel during the Texas Air Quality Study 2000. Overall, 28 ions dominated the PTR-MS mass spectra and were assigned as anthropogenic aromatics (e.g., benzene, toluene, xylenes) and hydrocarbons (propene, isoprene), oxygenated compounds (e.g., formaldehyde, acetaldehyde, acetone, methanol, C7 carbonyls), and three nitrogencontaining compounds (e.g., HCN, acetonitrile and acrylonitrile). Biogenic VOCs were minor components at this site. Propene was the most abundant lightweight hydrocarbon detected by this technique with concentrations up to 100+ nmol mol-1, and was highly correlated with its oxidation products, formaldehyde (up to ~40 nmol mol-1) and acetaldehyde (up to ~80 nmol/mol), with typical ratios close to 1 in propene-dominated plumes. In the case of aromatic species the high time resolution of the obtained data set helped in identifying different anthropogenic sources (e.g., industrial from urban emissions) and testing current emission inventories. A comparison with results from complimentary techniques (gas chromatography, differential optical absorption spectroscopy) was used to assess the selectivity of this on-line technique in a complex urban and industrial VOC matrix and give an interpretation of mass scans obtained by ‘‘soft’’ chemical ionization using proton-transfer via H3O+. The method was especially valuable in monitoring rapidly changing VOC plumes which passed over the site, and when coupled with meteorological data it was possible to identify likely sources.

Karl, Thomas G.; Jobson, B Tom T.; Kuster, W. C.; Williams, Eric; Stutz, Jochen P.; Shetter, Rick; Hall, Samual R.; Goldan, P. D.; Fehsenfeld, Fred C.; Lindinger, Werner

2003-08-19T23:59:59.000Z

294

Site environmental report summary  

Science Conference Proceedings (OSTI)

In this summary of the Fernald 1992 Site Environmental Report the authors will describe the impact of the Fernald site on man and the environment and provide results from the ongoing Environmental Monitoring Program. Also included is a summary of the data obtained from sampling conducted to determine if the site complies with DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA) requirements. These requirements are set to protect both man and the environment.

Not Available

1992-12-31T23:59:59.000Z

295

Potential Release Sites  

NLE Websites -- All DOE Office Websites (Extended Search)

PRS PRS Potential Release Sites Legacy sites where hazardous materials are found to be above acceptable levels are collectively called potential release sites. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Less than 10 percent of the total number of potential release sites need to go through the full corrective action process. What are potential release sites? Potential release sites are areas around the Laboratory and the town of Los Alamos at which hazardous materials from past activities have been found. Some examples of potential release sites include septic tanks and associated drain lines chemical storage areas wastewater outfalls material disposal areas incinerators sumps firing ranges

296

Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure Verification Forms for CAS 03-23-06 and CAS 19-19-01 are included as Appendix C of this report. These forms include before and after photographs of the sites, descriptions and removal status of waste, and waste disposal information. CAU 537, Waste Sites, was closed by characterizing and disposing of debris. The purpose of this CR is to summarize the completed closure activities, document appropriate waste disposal, and confirm that the closure standards were met.

NSTec Envirornmental Restoration

2007-07-01T23:59:59.000Z

297

DOE/WIPP-10-2225 Waste Isolation Pilot Plant Annual Site Environmental  

NLE Websites -- All DOE Office Websites (Extended Search)

WIPP-10-2225 WIPP-10-2225 Waste Isolation Pilot Plant Annual Site Environmental Report for 2009 Errata U.S. Department of Energy September 2010 2 Waste Isolation Pilot Plant Annual Site Environmental Report for 2009 DOE/WIPP-10-2225 3 2009 Annual Site Environmental Report To our readers: This Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2009 presents summary environmental data to (1) characterize site environmental management performance, (2) summarize environmental occurrences and responses reported during the calendar year, (3) confirm compliance with environmental standards and requirements, and (4) highlight the WIPP Environmental Management System (EMS), significant environmental programs, and accomplishments including progress toward the

298

Feature Detection, Characterization and Confirmation Methodology: Final Report  

SciTech Connect

This is the final report of the NUMO-LBNL collaborative project: Feature Detection, Characterization and Confirmation Methodology under NUMO-DOE/LBNL collaboration agreement, the task description of which can be found in the Appendix. We examine site characterization projects from several sites in the world. The list includes Yucca Mountain in the USA, Tono and Horonobe in Japan, AECL in Canada, sites in Sweden, and Olkiluoto in Finland. We identify important geologic features and parameters common to most (or all) sites to provide useful information for future repository siting activity. At first glance, one could question whether there was any commonality among the sites, which are in different rock types at different locations. For example, the planned Yucca Mountain site is a dry repository in unsaturated tuff, whereas the Swedish sites are situated in saturated granite. However, the study concludes that indeed there are a number of important common features and parameters among all the sites--namely, (1) fault properties, (2) fracture-matrix interaction (3) groundwater flux, (4) boundary conditions, and (5) the permeability and porosity of the materials. We list the lessons learned from the Yucca Mountain Project and other site characterization programs. Most programs have by and large been quite successful. Nonetheless, there are definitely 'should-haves' and 'could-haves', or lessons to be learned, in all these programs. Although each site characterization program has some unique aspects, we believe that these crosscutting lessons can be very useful for future site investigations to be conducted in Japan. One of the most common lessons learned is that a repository program should allow for flexibility, in both schedule and approach. We examine field investigation technologies used to collect site characterization data in the field. An extensive list of existing field technologies is presented, with some discussion on usage and limitations. Many of the technologies on the list were in fact used during the characterization of Yucca Mountain and elsewhere by LBNL personnel. The study also includes emerging technologies and identifies the need to develop better estimation of important parameters for repository siting. Notable emerging technologies include 3-D seismic and satellite-based remote sensing and wireless micro electro mechanical systems (MEMS) sensors. They enable cost-effective and ubiquitous monitoring to be applied for site characterization. We list and classify the types of uncertainties involved in site characterization. Uncertainties can exist in all aspects of site characterization: data, interpretation, conceptualization, and modeling. We use the Swedish program to exemplify such uncertainties. We also devote a chapter on geochemical issues regarding the interaction between groundwater and natural and engineered barrier materials. A recommendation has been made to take advantage of the recent advancement in geochemical modeling capabilities in natural systems. Although it is not of immediate relevance at the preliminary investigation stage, it serves as a good reminder that geochemical investigation efforts should not be overlooked at any stage in the repository program. We construct a synthetic preliminary-investigation site based on an extensive data set available from a geoscientific project in Japan, which we use as a 'real' site to evaluate uncertainties resulting from hydrogeological modeling and examine strategies for characterizing a new site. We plan various preliminary-investigation configurations and conduct preliminary numerical investigations at the synthetic site. We construct a model of the 'real' site for each PI configuration, make predictions of particle travel times, and compare against the 'real' data obtained from the 'real' model. We conclude that drilling as many as nine boreholes does not necessarily improve the understanding of the site compared to drilling as few as three boreholes, unless there is an underlying stru

Karasaki, Kenzi; Apps, John; Doughty, Christine; Gwatney, Hope; Onishi, Celia Tiemi; Trautz, Robert; Tsang, Chin-Fu

2007-03-01T23:59:59.000Z

299

Feature Detection, Characterization and Confirmation Methodology: Final Report  

SciTech Connect

This is the final report of the NUMO-LBNL collaborative project: Feature Detection, Characterization and Confirmation Methodology under NUMO-DOE/LBNL collaboration agreement, the task description of which can be found in the Appendix. We examine site characterization projects from several sites in the world. The list includes Yucca Mountain in the USA, Tono and Horonobe in Japan, AECL in Canada, sites in Sweden, and Olkiluoto in Finland. We identify important geologic features and parameters common to most (or all) sites to provide useful information for future repository siting activity. At first glance, one could question whether there was any commonality among the sites, which are in different rock types at different locations. For example, the planned Yucca Mountain site is a dry repository in unsaturated tuff, whereas the Swedish sites are situated in saturated granite. However, the study concludes that indeed there are a number of important common features and parameters among all the sites--namely, (1) fault properties, (2) fracture-matrix interaction (3) groundwater flux, (4) boundary conditions, and (5) the permeability and porosity of the materials. We list the lessons learned from the Yucca Mountain Project and other site characterization programs. Most programs have by and large been quite successful. Nonetheless, there are definitely 'should-haves' and 'could-haves', or lessons to be learned, in all these programs. Although each site characterization program has some unique aspects, we believe that these crosscutting lessons can be very useful for future site investigations to be conducted in Japan. One of the most common lessons learned is that a repository program should allow for flexibility, in both schedule and approach. We examine field investigation technologies used to collect site characterization data in the field. An extensive list of existing field technologies is presented, with some discussion on usage and limitations. Many of the technologies on the list were in fact used during the characterization of Yucca Mountain and elsewhere by LBNL personnel. The study also includes emerging technologies and identifies the need to develop better estimation of important parameters for repository siting. Notable emerging technologies include 3-D seismic and satellite-based remote sensing and wireless micro electro mechanical systems (MEMS) sensors. They enable cost-effective and ubiquitous monitoring to be applied for site characterization. We list and classify the types of uncertainties involved in site characterization. Uncertainties can exist in all aspects of site characterization: data, interpretation, conceptualization, and modeling. We use the Swedish program to exemplify such uncertainties. We also devote a chapter on geochemical issues regarding the interaction between groundwater and natural and engineered barrier materials. A recommendation has been made to take advantage of the recent advancement in geochemical modeling capabilities in natural systems. Although it is not of immediate relevance at the preliminary investigation stage, it serves as a good reminder that geochemical investigation efforts should not be overlooked at any stage in the repository program. We construct a synthetic preliminary-investigation site based on an extensive data set available from a geoscientific project in Japan, which we use as a 'real' site to evaluate uncertainties resulting from hydrogeological modeling and examine strategies for characterizing a new site. We plan various preliminary-investigation configurations and conduct preliminary numerical investigations at the synthetic site. We construct a model of the 'real' site for each PI configuration, make predictions of particle travel times, and compare against the 'real' data obtained from the 'real' model. We conclude that drilling as many as nine boreholes does not necessarily improve the understanding of the site compared to drilling as few as three boreholes, unless there is an underlying structure that is larger than the spacing of the boreholes. The

Karasaki, Kenzi; Apps, John; Doughty, Christine; Gwatney, Hope; Onishi, Celia Tiemi; Trautz, Robert; Tsang, Chin-Fu

2007-03-01T23:59:59.000Z

300

Considered Sites | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Considered Sites Considered Sites Considered Sites View Considered Sites View Other Sites DOE maintains the Considered Sites Database to provide information to the public about sites that were formerly used in the nation's nuclear weapons and early atomic energy programs and that had the potential for residual radioactive contamination on site. Formerly Utilized Sites Remedial Action Program The U.S. Atomic Energy Commission (AEC) established the Formerly Utilized Sites Remedial Action Program (FUSRAP) in March 1974 under the authority of the Atomic Energy Act of 1954 to identify, investigate, and take appropriate cleanup action at sites where work was performed in support of the Manhattan Engineer District (MED) and early AEC programs. Site activities included uranium ore storage and processing, uranium metal

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Site Visit Report, Livermore Site Office - February 2011 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Site Visit Report, Livermore Site Office - February 2011 Site Visit Report, Livermore Site Office - February 2011 Site Visit Report, Livermore Site Office - February 2011 February 2011 Livermore Site Office Safety Basis Self-Assessment This site visit report documents the collective results of the Office of Health, Safety and Security's (HSS) assessment of National Nuclear Safety Administration (NNSA) Livermore Site Office (LSO) safety basis processes and discusses its scope, objective, results and conclusions. Appendix A provides lists of the documents, interviews, and observations and Appendix B includes the plan for the review. The assessment was sponsored by LSO as a self-assessment and conducted jointly by HSS and LSO staff. It was completed in late 2010 and included site visits from November 29 - December

302

Nevada National Security Site Waste Acceptance Criteria  

Science Conference Proceedings (OSTI)

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

NSTec Environmental Management

2011-01-01T23:59:59.000Z

303

Appendix F Cultural Resources, Including  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Appendix F Appendix F Cultural Resources, Including Section 106 Consultation STATE OF CALIFORNIA - THE RESOURCES AGENCY EDMUND G. BROWN, JR., Governor OFFICE OF HISTORIC PRESERVATION DEPARTMENT OF PARKS AND RECREATION 1725 23 rd Street, Suite 100 SACRAMENTO, CA 95816-7100 (916) 445-7000 Fax: (916) 445-7053 calshpo@parks.ca.gov www.ohp.parks.ca.gov June 14, 2011 Reply in Reference To: DOE110407A Angela Colamaria Loan Programs Office Environmental Compliance Division Department of Energy 1000 Independence Ave SW, LP-10 Washington, DC 20585 Re: Topaz Solar Farm, San Luis Obispo County, California Dear Ms. Colamaria: Thank you for seeking my consultation regarding the above noted undertaking. Pursuant to 36 CFR Part 800 (as amended 8-05-04) regulations implementing Section

304

Countries Gasoline Prices Including Taxes  

Gasoline and Diesel Fuel Update (EIA)

Countries (U.S. dollars per gallon, including taxes) Countries (U.S. dollars per gallon, including taxes) Date Belgium France Germany Italy Netherlands UK US 01/13/14 7.83 7.76 7.90 8.91 8.76 8.11 3.68 01/06/14 8.00 7.78 7.94 8.92 8.74 8.09 3.69 12/30/13 NA NA NA NA NA NA 3.68 12/23/13 NA NA NA NA NA NA 3.63 12/16/13 7.86 7.79 8.05 9.00 8.78 8.08 3.61 12/9/13 7.95 7.81 8.14 8.99 8.80 8.12 3.63 12/2/13 7.91 7.68 8.07 8.85 8.68 8.08 3.64 11/25/13 7.69 7.61 8.07 8.77 8.63 7.97 3.65 11/18/13 7.99 7.54 8.00 8.70 8.57 7.92 3.57 11/11/13 7.63 7.44 7.79 8.63 8.46 7.85 3.55 11/4/13 7.70 7.51 7.98 8.70 8.59 7.86 3.61 10/28/13 8.02 7.74 8.08 8.96 8.79 8.04 3.64 10/21/13 7.91 7.71 8.11 8.94 8.80 8.05 3.70 10/14/13 7.88 7.62 8.05 8.87 8.74 7.97 3.69

305

Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment  

Science Conference Proceedings (OSTI)

This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database. (TEM)

Not Available

1988-12-01T23:59:59.000Z

306

Evaluation of Suitability of Selected Set of Department of Defense Military Bases and Department of Energy Facilities for Siting a Small Modular Reactor  

SciTech Connect

This report summarizes the approach that ORNL developed for screening a sample set of US Department of Defense (DOD) military base sites and DOE sites for possible powering with an SMR; the methodology employed, including spatial modeling; and initial results for several sample sites. The objective in conducting this type of siting evaluation is demonstrate the capability to characterize specific DOD and DOE sites to identify any particular issues associated with powering the sites with an SMR using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

Poore III, Willis P [ORNL; Belles, Randy [ORNL; Mays, Gary T [ORNL; Omitaomu, Olufemi A [ORNL

2013-03-01T23:59:59.000Z

307

NETL: Site Environmental Quality  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Environmental Quality Site Environmental Quality About NETL Site Environmental Quality - Certified to ISO 14001:2004 Questions about NETL's Environment, Safety and Health Management System may be directed to Michael Monahan, 304-285-4408, michael.monahan@netl.doe.gov. NETL has implemented an Environment, Safety and Health (ES&H) Management System, based on DOE's Integrated Safety Management System, the International Organization for Standardization (ISO) 14000 series, and the Occupational Health and Safety Assessment (OHSAS) 18000 series. While the original scope of the ES&H Management System included the Morgantown and Pittsburgh sites, in fiscal year 2010, the Albany site was incorporated into the existing ES&H Management System. In addition, all three sites underwent ISO 14001:2004 recertification audits and Morgantown and

308

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

.. ' \ MONTICELLO NPL SITES FFA QUARTERLY REPORT: October 1 -December 31, 2008 DOE Site Manager: Jalena Dayvault JR 7CJ7 This report summarizes current project status and activities implemented during October tiU'ough December 2008, and provides a schedule of planned near term activities for the Monticello MIII Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection repmis, site meteorological data, and monitoring summary for tlw ex situ ground water treatment system. 1.0 MMTS Activities/Status Repository and Pond 4 · * Monthly and quarterly inspection of the repository identified no abnormalities (see attached repmis). .

309

1994 Site environmental report  

Science Conference Proceedings (OSTI)

The Fernald site is a Department of Energy (DOE)-owned facility that produced high-quality uranium metals for military defense for nearly 40 years. DOE suspended production at the site in 1989 and formally ended production in 1991. Although production activities have ceased, the site continues to examine the air and liquid pathways as possible routes through which pollutants from past operations and current remedial activities may leave the site. The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, General Environmental Protection Program. This 1994 SER provides the general public as well as scientists and engineers with the results from the site`s ongoing Environmental Monitoring Program. Also included in this report is information concerning the site`s progress toward achieving full compliance with requirements set forth by DOE, U.S. Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in this Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here. All information presented in this summary is discussed more fully in the main body of this report.

NONE

1995-07-01T23:59:59.000Z

310

Medical Sites  

NLE Websites -- All DOE Office Websites (Extended Search)

Medical Sites Name: Jenielle Location: NA Country: NA Date: NA Question: I started itching Aug. 1999. Diagnosed with ITP Oct.1999. I am in remission With a platelet count in...

311

Hanford Site  

NLE Websites -- All DOE Office Websites

Around the Site Current HMS Observations Daily HMS Extremes in Met Data Met and Climate Data Summary Products Contacts Hours Current NWS Forecast for the Tri-Cities NWS...

312

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

April 1 - June 30, 2008 April 1 - June 30, 2008 DOE Site Manager: Jalena Maestas This report summarizes current project status, activities implemented during April through June 2008, and provides a schedule of planned near term activities, for the Monticello Mill Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection results, and site meteorological monitoring data. 1.0 MMTS Activities/Status Repository and Pond 4 * Monthly and quarterly inspection of the repository identified no abnormalities. * Shrub seedlings planted last fall had a poor survival rate. * New damage to shrubs and vole infestation is not evident. * Monthly inspection of Pond 4 identified no abnormalities.

313

Web Site Map  

NLE Websites -- All DOE Office Websites (Extended Search)

Help » Web Site Map Help » Web Site Map Web Site Map The links listed below include all pages on the site except document topic pages. Home Privacy/Security Help Web Site Map Mailing Services Remove me from the List Contact Us About Us News and Events News Archives News/Media FAQs Internet Resources Documents DUF6 EIS Historical Context What is an EIS? Why EIS is Needed Who is Responsible? EIS Process EIS Topics EIS Alternatives EIS Schedule Public Involvement Opportunities Public Comment Form For More Info DUF6 Management and Uses Management Responsibilities DUF6 Storage How DUF6 is Stored Where DUF6 is Stored Cylinder Leakage DUF6 Storage Safety DUF6 PEIS Cylinder Surveillance and Maintenance Conversion Potential DU Uses "Business Case" for R&D on Beneficial Uses of DU Catalysts for Destruction of Air Pollutants

314

MONTICELLO NPL SITES  

Office of Legacy Management (LM)

January 1 - March 31, 2008 January 1 - March 31, 2008 DOE Site Manager: Jalena Maestas This report summarizes current project status, activities implemented during January through March 2008, and provides a schedule of planned near term activities, for the Monticello Mill Tailings Site (MMTS) and the Monticello Vicinity Properties (MVP) NPL sites. This report also includes repository and Pond 4 leachate collection data, quarterly site inspection results, and site meteorological monitoring data. The first semi-annual FFA meeting of 2008 was held at UDEQ in Salt Lake City, Utah, March 26 and 27, 2008. Minutes and action items resulting from that meeting will be prepared under separate cover pending review and concurrence by EPA and UDEQ. Draft minutes and action items are scheduled for submittal by May 1, 2008.

315

Related Data Sites  

NLE Websites -- All DOE Office Websites (Extended Search)

Related Data Sites Related Data Sites CDIAC has listed the following Web sites because these sites offer high-quality data sets (not available through CDIAC) from a variety of global-change themes. These links will take you outside of CDIAC, therefore, we are not responsible for the content or intent of these outside links. This list is not intended to be comprehensive, but we do hope you find it useful if you cannot find what you are looking for here at CDIAC. Multi-Agency Sites Global Change Data and Information System (GCDIS) GCDIS is a collection of distributed information systems operated by government agencies involved in global change research. GCDIS provides global change data to scientists and researchers, policy makers, educators, industry, and the public at large and includes multidisciplinary data from

316

Microsoft Word - Protocol for HSS Site Leads.docx  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

sites currently include: * Argonne National Laboratory * East Tennessee Technology Park * Hanford Site Richland Office * Hanford Site Office of River Protection * Idaho National...

317

Progress Report, December 2010: Improved Site Characterization And Storage Prediction Through Stochastic Inversion Of Time-Lapse Geophysical And Geochemical Data  

Science Conference Proceedings (OSTI)

Over the last project six months, our project activities have concentrated on three areas: (1) performing a stochastic inversion of pattern 16 seismic data to deduce reservoir permeability, (2) development of the geochemical inversion strategy and implementation of associated software, and (3) completing the software implementation of TProGS and the geostatistical analysis that provides the information needed when using the software to produce realizations of the Midale reservoir. The report partially the following deliverables: D2: Model development: MCMC tool (synthetic fluid chemistry data); deliverable completed. D4: Model development/verification: MCMC tool (TProGS, field seismic/chemistry data) work product; deliverable requirements partially fulfilled. D5: Field-based single-pattern simulations work product; deliverable requirements partially fulfilled. When completed, our completed stochastic inversion tool will explicitly integrate reactive transport modeling, facies-based geostatistical methods, and a novel stochastic inversion technique to optimize agreement between observed and predicted storage performance. Such optimization will be accomplished through stepwise refinement of: (1) the reservoir model - principally its permeability magnitude and heterogeneity - and (2) geochemical parameters - primarily key mineral volume fractions and kinetic data. We anticipate that these refinements will facilitate significantly improved history matching and forward modeling of CO{sub 2} storage. Our tool uses the Markov Chain Monte Carlo (MCMC) methodology. Deliverable D1, previously submitted as a report titled ''Development of a Stochastic Inversion Tool To Optimize Agreement Between The Observed And Predicted Seismic Response To CO{sub 2} Injection/Migration in the Weyburn-Midale Project'' (Ramirez et al., 2009), described the stochastic inversion approach that will identify reservoir models that optimize agreement between the observed and predicted seismic response. The software that implements this approach has been completed, tested, and used to process seismic data from pattern 16. A previously submitted report titled ''Model verification: synthetic single pattern simulations using seismic reflection data'', Ramirez et al. 2010, partially fulfilled deliverable D3 by summarizing verification activities that evaluate the performance of the seismic software and its ability to recover reservoir model permeabilities using synthetic seismic reflection data. A future progress report will similarly describe summarizing verification activities of the geochemical inversion software, thereby completing deliverable D3. This document includes a chapter that shows and discusses permeability models produced by seismic inversion that used seismic data from pattern 16 in Phase 1A. It partially fulfills deliverable D5: Field-based single-pattern simulations work product. The D5 work product is supposed to summarize the results of applying NUFT/MCMC to refine the reservoir model and geochemical parameters by optimizing observation/prediction agreement for the seismic/geochemical response to CO{sub 2} injection/migration within a single pattern of Phase 1A/1B. A future progress report will show inversion results for the same pattern using geochemical data, thereby completing deliverable D5. This document also contains a chapter that fulfills deliverable D2: Model development: MCMC tool (synthetic fluid chemistry data). The chapter will summarize model development activities required to facilitate application of NUFT/MCMC to optimize agreement between the observed and predicted geochemical response to CO{sub 2} injection/migration. Lastly, this document also contains a chapter that partially fulfills deliverable D4: Model development/verification: MCMC tool (TProGS, field seismic/chemistry data) work product. This work product is supposed to summarize model development activities required for (1) application of TProGS to Weyburn, (2) use of TProGS within the MCMC tool, and (3) application of the MCMC tool to address field seismic and g

Ramirez, A; Mcnab, W; Carle, S; Hao, Y; White, D; Johnson, J

2010-12-17T23:59:59.000Z

318

Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory  

SciTech Connect

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01T23:59:59.000Z

319

Site Map  

NLE Websites -- All DOE Office Websites (Extended Search)

Home » Site Map Home » Site Map Site Map Home About Overview NERSC Mission Contact us Staff Center Leadership Sudip Dosanjh Select Publications Jeff Broughton Katie Antypas John Shalf Francesca Verdier Center Administration James Craw Norma Early Jeff Grounds Betsy MacGowan Zaida McCunney Lynn Rippe Suzanne Stevenson David Tooker Center Communications Jon Bashor Linda Vu Margie Wylie Kathy Kincade Advanced Technologies Group Nicholas Wright Brian Austin Research Projects Matthew Cordery Christopher Daley Analytics Group Peter Nugent David Camp Hank Childs Harinarayan Krishnan Burlen Loring Joerg Meyer Prabhat Oliver Ruebel Daniela Ushizima Gunther Weber Yushu Yao Computational Systems Group Jay Srinivasan James Botts Scott Burrow Tina Butler Nick Cardo Tina Declerck Ilya Malinov David Paul Larry Pezzaglia Iwona Sakrejda

320

February 28, 2006, Department letter reporting completion of NNSA portion of Commitment 23 in the 2004-1 implementation plan, Oversight of Complex, High-Hazard Nuclear Operations, which requires the development of site office action plans to improve the consistency and reliability of work planning and work control at the activity level, including the incorporation of Integrated Safety Management core functions  

NLE Websites -- All DOE Office Websites (Extended Search)

Washington, DC 20585 Washington, DC 20585 February 28, 2006 OFFICE O F THE ADMINISTRATOR The Honorable A. J. Eggenberger Ch a i rm an Defensc Nuclear Facilities Safety Board 625 Indiana Avenue, NW., Suite 700 Washington, D.C. 20004-2901 Dear Mr. Chairman: On Julie 10, 2005, Secretary Bodnian submitted the Department's Iiizplenzentution Plun to Itizpt-ove Oversight qf'Nucleur Operutions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2004- I , Oversight qf Complex, High-Hrrzurd Nucleur Openrtiotzs. Section 5.3 of the Implementation Plan (IP) addresses Revitalizing Integruted SU/i-'ty Munagernent Implementution, and Subsection 5.3.2 addresses Work Plunning mil Work Control ut the Activity Level. Commitment 23 of the 1P requires development of site office action plans to improve the consistency and reliability of work

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Waste Isolation Pilot Plant Annual Site Environmental Report for 2012  

SciTech Connect

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

None

2013-09-01T23:59:59.000Z

322

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006  

Science Conference Proceedings (OSTI)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

2006-06-01T23:59:59.000Z

323

Remedial action and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Attachment 2, Geology report: Appendix B, Preliminary final  

SciTech Connect

Detailed investigations of geologic, geomorphic, and seismic conditions at the Burro Canyon site were conducted by the US Department of Energy (DOE) as a disposal site for the tailings at two processing sites near the Slick Rock, Colorado, post office. The purposes of these studies are basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies (e.g., analyses of hydrologic and liquefaction hazards) used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65-km radius of the site, provided the basis for seismic design parameters.

Not Available

1994-03-01T23:59:59.000Z

324

A data base for low-level radioactive waste disposal sites  

SciTech Connect

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.

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

1989-07-01T23:59:59.000Z

325

Closure Report for Housekeeping Category Corrective Action Unit 387: Spill Sites and Releases, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

This Closure Report documents the closure activities conducted for CAU 387: Spill Sites and Releases. Closure activities were performed in two phases. Phase I activities consisted of collecting waste characterization samples of soil at appropriate sites. The results were used to determine how waste generated during closure activities would be handled and disposed (i.e., as nonhazardous sanitary or hazardous waste). Phase 2 activities consisted of closing each CAS by removing debris and/or soil, disposing of the generated waste, and verifying that each site was clean-closed by visual inspection and/or collecting soil verification samples for laboratory analysis. Additionally, seven sites were closed with no further action after concurrence with Nevada Division of Environmental Protection (NDEP). Four other sites were moved into different CAUs in Appendix III of the FFACO because the housekeeping process was not adequate to close them. Copies of the analytical results for the site verification samples are included in Appendix A. Copies of the Sectored Housekeeping Site Closure Verification Forms for each of the 16 CAS are included in Appendix B.

T. M. Fitzmaurice

2001-10-01T23:59:59.000Z

326

Groundwater maps of the Hanford site, June 1995  

Science Conference Proceedings (OSTI)

The Groundwater Maps of the Hanford Site, June 1995 is a continuation of a series of reports (see Serkowski et al. 1995) that document the configuration of the water table aquifer beneath the Hanford Site (Figure 1). This series presents the results of the semiannual water level measurement program and the water table maps generated from these measurements. The reports document the changes in the groundwater level at the Hanford Site during the transition from nuclear material production to environmental restoration and remediation. In addition, these reports provide water level data to support the various site characterization and groundwater monitoring programs currently in progress on the Hanford Site. Groundwater Maps of the Hanford Site is prepared for the U.S. Department of Energy by the Hanford Site Operations and Engineering Contractor, Westinghouse Hanford Company (WHC). This document fulfills reporting requirements specified in WHC-CM-7-5, Section 8.0 ``Water Quality`` and described in the environmental monitoring plan for the Hanford Site. (DOE-RL 1993a) This document highlights the three major operations areas (the 100, 200 and 300/1100 Areas) where wastes were discharged to the soil. Each area includes a summary discussion of the data, a well index map, and a contoured map of the water table surface. Appendix A contains all of the data collected for this program.

Sweeney, M.D.

1996-03-15T23:59:59.000Z

327

Characterization of Fernald Silo 3 Waste  

Science Conference Proceedings (OSTI)

This report summarizes characterization results for uranium residues from the Fernald Environmental Management Project (FEMP) Operable Unit (OU-4). These residues are currently stored in a one-million-gallon concrete silo, Silo 3, at the DOE Fernald Site, Ohio. Characterization of the Silo 3 waste is the first part of a three part study requested by Rocky Mountain Remedial Services (RMRS) through a Work for others Agreement, WFO-00-007, between the Westinghouse Savannah River Company (WSRC) and RMRS. Parts 2 and 3 of this effort include bench- and pilot-scale testing.

Langton, C.A.

2001-04-04T23:59:59.000Z

328

Remedial actions of nuclear safety shot sites: Double Tracks and Clean Slates  

SciTech Connect

Remedial actions of plutonium (Pu)-contaminated soils are in the preliminary stages of development at the Nevada Test Site (NTS). Interim clean-up actions were completed at the Double Tracks and Clean Slate 1 safety shot sites in 1996 and 1997, respectively. Soil at both sites, with a total transuranic activity greater than 20 picoCuries per gram (pCi/g), was excavated and shipped to the NTS for disposal. Characterization and assessment efforts were initiated at the Double Tracks site in 1995, and the clean-up of this site as an interim action was completed in 1996. Clean-up of this site consisted of taking site-specific data and applying rationale for dose and risk calculations in selecting parameter values for the interim corrective action level. The remediation process included excavating and stockpiling the contaminated soil and loading the soil into supersacks with approximately 1,513 cubic meters (53,500 cubic feet) being shipped to the NTS for disposal. In 1997, remediation began on the Clean Slate 1 site on which characterization had already been completed using a very similar approach; however, the site incorporated lessons learned, cost efficiencies, and significant improvements to the process. This paper focuses on those factors and the progress that has been made in cleaning up the sites. The application of a technically reasonable remediation method, as well as the cost factors that supported transport and disposal of the low-level waste in bulk are discussed.

Sanchez, M. [Dept. of Energy, Las Vegas, NV (United States); Shotton, M.; Lyons, C. [Bechtel Nevada Inc., Las Vegas, NV (United States)

1998-03-01T23:59:59.000Z

329

Site C  

Office of Legacy Management (LM)

' ' u. s. A r my Corps or Engineers Kurfal.. Ilisfr ifl om« 1776 N1 . ~lI rll Sfred , lIu fflll" , New v ur k. 14207 Site C loseout Report for th e Ashland I (Includlng Seaway Arca D), Ashland 2 and Rattlesnake Creek FUS RAP Sites To nawanda . New Yor k F ina l - Octo ber 2006 Formerl y Ut ilized Sites Remedi al Actiun Program Dt:CLAlUlfiO lO OF RF ~ I'O""" A <:n o .. ('oMnLflOI'O '" 1 S-~1 1 A "n· nvnn: S Ill: C'lO'iU 'U l RtrUlIT f OR A SlIu x u l (I "ICLU I ING S t:A" ·,H A RU D j, AS H I .A ~O 2 A."n RAnU:M'AKf eRU" ~ rn~ I!d'on at A.hland 1 (Ind udonl Seaway Area DJ. Ashland 2 and kan~snak c Creek is Wi,...... 1c in acwr.hnu willi ~ Rcconl or Oecisim (ROD) . igned 00> April 20. 1998 and l'.1pbIWlOII <;If

330

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: 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. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report.

NSTec Environmental Restoration

2007-07-01T23:59:59.000Z

331

Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site  

SciTech Connect

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

NSTec Environmental Management

2008-09-01T23:59:59.000Z

332

Characterization - Programmaster.org  

Science Conference Proceedings (OSTI)

Feb 17, 2010 ... Our continuing studies involve characterization of neutron-irradiated specimens, including 12YWT and MA957 irradiated in HFIR to 9 dpa at ...

333

1994 Site Environmental Report  

SciTech Connect

The 1994 Site Environmental Report summarizes environmental activities at Lawrence Berkeley Laboratory (LBL) for the calendar year (CY) 1994. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the Laboratory`s environmental management programs when measured against regulatory standards and DOE requirements. The report also discusses significant highlight and planning efforts of these programs. The format and content of the report are consistent with the requirements of the US Department of Energy (DOE) Order 5400.1, General Environmental Protection Program.

NONE

1995-05-01T23:59:59.000Z

334

SITEWIDE CATEGORICAL EXCLUSION FOR SITE CHARACfERlZATION AND ENVIRONMENTAL MONITORING, PACIFIC NORTHWEST NATIONAL  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SITEWIDE CATEGORICAL EXCLUSION FOR SITE CHARACfERlZATION AND ENVIRONMENTAL MONITORING, PACIFIC NORTHWEST NATIONAL LABORATORY SITE, RICHLAND, WASHINGTON Proposed ActioD: The U.S. Department of Energy (DOE) Pacific Northwest Site Office (PNSO) proposes to conduct site characterization and environmental monitoring activities. LocadoD of AcdoD: The proposed action would occur on and near the Pacific Northwest National Laboratory (PNNL) Site and at other sites in the State of Washington. DeserlpdoD 01 the Proposed AedoD: The proposed action would include a variety of non-intrusive and intrusive characteri2ation and monitoring activities conducted in support of purposes such as environmental surveillance, remediation. research, construction. and sampling.

335

Berkeley Lab: Educational Sites  

NLE Websites -- All DOE Office Websites (Extended Search)

Educational Sites Educational Sites The Center for Science & Engineering Education (CSEE) Berkeley Lab's Center for Science & Engineering Education (CSEE) carries out the Department of Energy's education mission to train the next generation of scientists, as well as helping them to gain an understanding of the relationships among frontier science, technology, and society. CSEE supports science literacy in the community and nationally through a broad range of programs from elementary school to undergraduate and graduate education, including internships, mentoring, school workshops and summer research programs for teachers. Through its broad range of programs, CSEE serves as the center for Berkeley Lab's science education efforts, developing partnerships with schools, government agencies, and non-profit

336

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

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

GREAGER, T.M.

2000-12-01T23:59:59.000Z

337

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

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

GREAGER, T.M.

2000-12-06T23:59:59.000Z

338

Strategic Petroleum Reserve site environmental report for calendar year 1997  

SciTech Connect

The purpose of this Site Environmental Report (SER) is to characterize site environmental management performance, confirm compliance with environmental standards and requirements, and highlight significant programs and efforts for the US Department of Energy (DOE) Strategic Petroleum Reserve (SPR). The SER, provided annually in accordance with DOE order 5400.1, serves the public by summarizing monitoring data collected to assess how the SPR impacts the environment. The SER provides a balanced synopsis of non-radiological monitoring and regulatory compliance data and affirms that the SPR has been operating within acceptable regulatory limits. Included in this report is a describe of each site`s environment, an overview of the SPR environmental program, and a recapitulation of special environmental activities and events associated with each SPR site during 1997. Two of these highlights include decommissioning of the Weeks Island site, involving the disposition of 11.6 million m{sup 3} (73 million barrels) of crude oil inventory, as well as the degasification of over 12.6 million m{sup 3} (79.3 million barrels) of crude oil inventory at the Big Hill and Bryan Mound facilities.

NONE

1998-11-01T23:59:59.000Z

339

Results of Detailed Hydrologic Characterization Tests - Fiscal Year 2000  

Science Conference Proceedings (OSTI)

This report provides the resluts of detailed hydrologic characterization tests conducted within eleven Hanford Site wells during fiscal year 2000. Detailed characterization tests performed included groundwater-flow characterization; barometric response evaluation; slug tests; single-well tracer tests; constant-rate pumping tests; and in-well, vertical flow tests. Hydraulic property estimates obtained from the detailed hydrologic tests include transmissivity; hydraulic conductivity; specific yield; effective porosity; in-well, lateral flow velocity; aquifer-flow velocity; vertical distribution of hydraulic conductivity (within the well-screen section); and in-well, verticla flow velocity. In addition, local groundwater-flow characteristics (i.e., hydraulic gradient and flow direction) were determined for four sites where detailed well testing was performed.

Spane, Frank A.; Thorne, Paul D.; Newcomer, Darrell R.

2001-05-15T23:59:59.000Z

340

Results of Detailed Hydrologic Characterization Tests - Fiscal Year 1999  

Science Conference Proceedings (OSTI)

This report provides the results of detailed hydrologic characterization tests conducted within newly constructed Hanford Site wells during FY 1999. Detailed characterization tests performed during FY 1999 included: groundwater flow characterization, barometric response evaluation, slug tests, single-well tracer tests, constant-rate pumping tests, and in-well vertical flow tests. Hydraulic property estimates obtained from the detailed hydrologic tests include: transmissivity, hydraulic conductivity, specific yield, effective porosity, in-well lateral flow velocity, aquifer flow velocity, vertical distribution of hydraulic conductivity (within the well-screen section) and in-well vertical flow velocity. In addition, local groundwater flow characteristics (i.e., hydraulic gradient and flow direction) were determined for four sites where detailed well testing was performed.

Spane, Frank A.; Thorne, Paul D.; Newcomer, Darrell R.

2001-01-19T23:59:59.000Z

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Science Accelerator content now includes multimedia  

Office of Scientific and Technical Information (OSTI)

Science Accelerator content now includes multimedia Science Accelerator has expanded its suite of collections to include ScienceCinema, which contains videos produced by the U.S....

342

HANFORD SITE ASSETS AND ATTRIBUTES  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HANFORD SITE ASSETS AND ATTRIBUTES HANFORD SITE ASSETS AND ATTRIBUTES The Hanford Site provides the opportunity for long-term sustainable energy and industry development. The area boasts a specialized workforce that is highly educated and well-established; is rich in resources including land, infrastructure, low-cost energy, and available workforce; more scientists and engineers per capita than any other area in the Pacific Northwest; and is an optimum location for the development of sustainable energy solutions. Land The Hanford Site is one of the largest remaining land mega-sites available in the United States. * The 586-square-mile Hanford Site includes 39,000 acres designated for industrial use (9,000 acres for R&D). * The Comprehensive Land-Use Plan Environmental Impact Statement allows for a planning process

343

Lawrence Berkeley National Laboratory 1995 site environmental report  

Science Conference Proceedings (OSTI)

The 1995 Site Environmental Report summarizes environmental activities at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL) for the 1995 calendar year. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the environmental management programs. The report also discusses significant highlights and plans of these programs. Topics discussed include: environmental monitoring, environmental compliance programs, air quality, water quality, ground water protection, sanitary sewer monitoring, soil and sediment quality, vegetation and foodstuffs monitoring, and special studies which include preoperational monitoring of building 85 and 1995 sampling results, radiological dose assessment, and quality assessment.

Balgobin, D.; Javandel, I.; Lackner, G.; Smith, C.; Thorson, P.; Tran, H.

1996-07-01T23:59:59.000Z

344

Evaluation of Suitability of Selected Set of Coal Plant Sites for Repowering with Small Modular Reactors  

SciTech Connect

This report summarizes the approach that ORNL developed for screening a sample set of small coal stations for possible repowering with SMRs; the methodology employed, including spatial modeling; and initial results for these sample plants. The objective in conducting this type of siting evaluation is to demonstrate the capability to characterize specific sample coal plant sites to identify any particular issues associated with repowering existing coal stations with SMRs using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

Belles, Randy [ORNL; Copinger, Donald A [ORNL; Mays, Gary T [ORNL; Omitaomu, Olufemi A [ORNL; Poore III, Willis P [ORNL

2013-03-01T23:59:59.000Z

345

Petroleum Gasoline & Distillate Needs Including the Energy ...  

U.S. Energy Information Administration (EIA)

Petroleum Gasoline & Distillate Needs Including the Energy Independence and Security Act (EISA) Impacts

346

Petroleum Gasoline & Distillate Needs Including the Energy ...  

U.S. Energy Information Administration (EIA)

Home > Petroleum > Analysis > Petroleum Gasoline & Distillate Needs Including the Energy Independence and Security Act (EISA) ...

347

Sequential evaluation of the potential geologic repository site at Yucca Mountain, Nevada, USA  

SciTech Connect

This paper discusses the changes that are planned for the characterization program at Yucca Mountain due to budget changes. Yucca Mountain is the only site being studied in the US for a geologic repository. Funding for the site characterization program at Yucca Mountain program was cut by roughly one half from the 1994 projected budget to complete three major milestones. These project milestones included: (1) a time-phased determination of site suitability, and if a positive finding, (2) completion of an Environmental Impact Statement, and (3) preparation of a License Application to the US NRC to authorize repository construction. In reaction, Yucca Mountain Site Characterization Project has shifted from parallel development of these milestones to a sequenced approach with the site suitability evaluation being replaced with a management assessment. Changes to the regulatory structure for the disposal program are under consideration by DOE and the NRC. The possibility for NRC and Doe to develop a site-specific regulatory structure follows from the National Energy Policy Act of 1992 that authorized the US EPA to develop a site specific environmental standard for Yucca Mountain.

Bjerstedt, T.W.

1996-12-31T23:59:59.000Z

348

Annual Site Environmental Report: 2006  

SciTech Connect

This report provides information about environmental programs during the calendar year (CY) of 2006 at the Stanford Linear Accelerator Center (SLAC), Menlo Park, California. Activities that span the calendar year; i.e., stormwater monitoring covering the winter season of 2006/2007 (October 2006 through May 2007), are also included. Production of an annual site environmental report (ASER) is a requirement established by the United States Department of Energy (DOE) for all management and operating (M&O) contractors throughout the DOE complex. SLAC is a federally-funded research and development center with Stanford University as the M&O contractor. SLAC continued to follow the path to self-declare an environmental management system under DOE Order 450.1, 'Environmental Protection Program' and effectively applied environmental management in meeting the site's integrated safety and environmental management system goals. For normal daily activities, all SLAC managers and supervisors are responsible for ensuring that proper procedures are followed so that Worker safety and health are protected; The environment is protected; and Compliance is ensured. Throughout 2006, SLAC focused on these activities through the SLAC management systems. These systems were also the way SLAC approached implementing 'greening of the government' initiatives such as Executive Order 13148. The management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. The SLAC Office of Assurance was created during 2006 in response to DOE Order 226.1. During 2006, there were no reportable releases to the environment from SLAC operations, and there were no Notice of Violations issued to SLAC from any of the regulatory agencies that oversee SLAC. In addition, many improvements in waste minimization, recycling, stormwater drain system, groundwater restoration, and SLAC's chemical management system (CMS) were continued during 2006 to better manage chemical use. Program-specific details are discussed below. SLAC operates its air quality management program in compliance with its established permit conditions. The Bay Area Air Quality Management District (BAAQMD) did not conduct a facility inspection of SLAC during 2006, though it did visit the site on four different occasions. The BAAQMD did compliment SLAC for the overall configuration of SLAC's gasoline dispensing facility and of SLAC's asbestos/demolition notification program during two of the visits. DOE awarded SLAC the 2006 Best in Class for Pollution Prevention and Environmental Stewardship Accomplishment in recognition of SLAC's CMS program which manages the procurement and use of chemicals. As an example of the efficiency of the CMS, SLAC reviewed its use of gases and associated tanks and phased out numerous gas tanks that were no longer needed or were not acceptable for long-term storage, in turn, reducing SLAC's on-site chemical inventory. As part of SLAC's waste minimization and management efforts, more than one thousand tons of municipal solid waste was recycled by SLAC during 2006. SLAC operates its industrial and sanitary wastewater management program in compliance with established permit conditions. During 2006, SLAC obtained a new facility-wide wastewater discharge permit which replaced four separate permits that were previously issued to SLAC. In 2006, no radiological incidents occurred that increased radiation levels or released radioactivity to the environment. In addition to managing its radioactive wastes safely and responsibly, SLAC worked to reduce the amount of waste generated. SLAC has implemented programs and systems to ensure compliance with all radiological requirements related to the environment. The Environmental Restoration Program continued work on site characterization and evaluation of remedial alternatives at four sites with volatile organic compounds in groundwater and several areas with polychlorinated biphenyls and low concentrations of lead in soil. SLAC is regulated under a site cleanup requirements order (board or

Nuckolls, H.; /SLAC

2008-02-22T23:59:59.000Z

349

Division Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Dioxide Reduction Catalysts Carbon Dioxide Reduction Catalysts Our research program is directed toward developing and understanding metal complexes that catalyze reactions relevant to renewable energy, particularly those that reduce carbon dioxide to fuels or fuel precursors. Carbon dioxide reduction catalysts are important targets because they could enable "recycling" of hydrocarbon fuels, thus lowering their carbon footprint. Our research addresses two key challenges in this area. First, we aim to improve the lifetimes, activity, and selectivity of homogeneous catalysts by incorporating them into porous heterogeneous frameworks derived from structurally persistent organic polymers. These frameworks allow isolation of the catalytic centers, which inhibits reaction pathways that lead to catalyst decomposition, and enable the spatially controlled deployment of ancillary functional groups that bind and concentrate substrate near the active site and/or assist with its activation. Second, we are developing homogeneous dual-catalyst systems and assemblies that couple CO2 reduction catalysis to a parallel catalytic reaction that provides the reducing equivalents. We are especially interested in proton-coupled electron-transfer reactions involving activation of H2 and of organic dehydrogenation substrates, wherein the proton pathway also participates in the conversion of CO2 to CO. In both of these research thrusts we are studying catalysts that may be activated under thermal, electrochemical, or photochemical conditions.

350

Nevada Test Site Environmental Report 2008 Attachment A: Site Description  

SciTech Connect

This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Cathy A. Wills

2009-09-01T23:59:59.000Z

351

Site environmental report for 2002.  

SciTech Connect

Sandia National Laboratories, California (SNL/CA) is a government-owned/contractor-operated laboratory. Sandia Corporation, a Lockheed Martin Company, operates the laboratory for the Department of Energy's (DOE) National Nuclear Security Administration. The DOE, Sandia Site Office oversees operations at the site, using Sandia Corporation as a management and operating contractor. This Site Environmental Report for 2002 was prepared in accordance with DOE Order 231.1. The report provides a summary of environmental monitoring information and compliance activities that occurred at SNL/CA during calendar year 2002. General site and environmental program information is also included.

Larsen, Barbara L.

2003-06-01T23:59:59.000Z

352

Including Croplands in a Global Biosphere Model: Methodology and Evaluation at Specific Sites  

Science Conference Proceedings (OSTI)

There is a strong international demand for quantitative estimates of both carbon sources/sinks, and water availability at the land surface at various spatial scales (regional to global). These estimates can be derived (and usually are) from ...

Sébastien Gervois; Nathalie de Noblet-Ducoudré; Nicolas Viovy; Philippe Ciais; Nadine Brisson; Bernard Seguin; Alain Perrier

2004-12-01T23:59:59.000Z

353

Photo Library of the Nevada Site Office (Includes historical archive of nuclear testing images)  

DOE Data Explorer (OSTI)

See also the Historical Film Library at http://www.nv.doe.gov/library/films/testfilms.aspx and the Current Film Library at http://www.nv.doe.gov/library/films/current.aspx. Current films can be viewed online, but only short clips of the historical films are viewable. They can be ordered via an online request form for a very small shipping and handling fee.

354

Savannah River Site Environmental Report for 2003  

SciTech Connect

The ''Savannah River Site Environmental Report for 2003'' (WSRC-TR-2004-00015) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; and (4) assess the impact of SRS operations on the public and the environment. This year's report reflects a continuing effort (begun in 2001) to streamline the document and thereby increase its cost effectiveness--without omitting valuable technical data. To that end each author will continue to work toward presenting results in summary fashion, focusing on historical trends. Complete data tables again are included on the CD inside the back cover of the report. The CD also features an electronic version of the report; an appendix of site, environmental sampling location, dose, and groundwater maps; and complete 2003 reports from a number of other SRS organizations.

A. MAMATEY

2003-01-01T23:59:59.000Z

355

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 2, Geology report: Final report  

Science Conference Proceedings (OSTI)

Detailed investigations of geologic, geomorphic, and seismic conditions at the Landfill disposal site were conducted. The purpose of these studies was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65-kilometer (km) (40-mile) radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps. Review of historical and instrumental earthquake data. Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area. Photogeologic interpretations of existing conventional aerial photographs. Ground reconnaissance and mapping of the site region.

Not Available

1992-10-01T23:59:59.000Z

356

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 2, Geology report. Revised final report  

Science Conference Proceedings (OSTI)

Detailed investigations of geologic, geomorphic, and seismic conditions at the Bodo Canyon disposal site were conducted. The purpose of these investigations was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65 kilometer radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps; Review of historical and instrumental earthquake data; Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area; Photogeologic interpretations of existing conventional aerial photographs; and, Ground reconnaissance and mapping of the site region.

Not Available

1991-12-01T23:59:59.000Z

357

Analysis of the Monitoring Network at the Salmon, Mississippi, Site  

SciTech Connect

The Salmon site in southern Mississippi was the location of two underground nuclear tests and two methane-oxygen gas explosion tests conducted in the Tatum Salt Dome at a depth of 2,715 feet below ground surface. The U.S. Atomic Energy Commission (a predecessor agency of the U.S. Department of Energy [DOE]) and the U.S. Department of Defense jointly conducted the tests between 1964 and 1970. The testing operations resulted in surface contamination at multiple locations on the site and contamination of shallow aquifers. No radionuclides from the nuclear tests were released to the surface or to groundwater, although radionuclide-contaminated drill cuttings were brought to the surface during re-entry drilling. Drilling operations generated the largest single volume of waste materials, including radionuclide-contaminated drill cuttings and drilling fluids. Nonradioactive wastes were also generated as part of the testing operations. Site cleanup and decommissioning began in 1971 and officially ended in 1972. DOE conducted additional site characterization between 1992 and 1999. The historical investigations have provided a reasonable understanding of current surface and shallow subsurface conditions at the site, although some additional investigation is desirable. For example, additional hydrologic data would improve confidence in assigning groundwater gradients and flow directions in the aquifers. The U.S. Environmental Protection Agency monitored groundwater at the site as part of its Long-Term Hydrologic Monitoring Program from 1972 through 2007, when DOE's Office of Legacy Management (LM) assumed responsibility for site monitoring. The current monitoring network consists of 28 monitoring wells and 11 surface water locations. Multiple aquifers which underlie the site are monitored. The current analyte list includes metals, radionuclides, and volatile organic compounds (VOCs).

None

2013-08-01T23:59:59.000Z

358

Weldon Spring Site Environmental Report for calendar year 1994  

SciTech Connect

This report for Calendar Year 1994 has been prepared to provide information about the public safety and environmental protection programs conducted by the Weldon Spring Site Remedial Action Project (WSSRAP). The Weldon Spring site is located in southern St. Charles County, Missouri, approximately 48 km (30 mi) west of St. Louis. The site consists of two main areas, the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. The chemical plant, raffinate pits, and quarry are located on Missouri State Route 94, southwest of US Route 40/61. The objectives of the Site Environmental Report are to present a summary of data from the environmental monitoring program, to characterize trends and environmental conditions at the site, and to confirm compliance with environmental and health protection standards and requirements. The report also presents the status of remedial activities and the results of monitoring these activities to assess their impacts on the public and environment. This report includes monitoring data from routine radiological and nonradiological sampling activities. These data include estimates of dose to the public from the Weldon Spring site, estimates of effluent releases, and trends in groundwater contaminant levels. Additionally, applicable compliance requirements, quality assurance programs, and special studies conducted in 1994 to support environmental protection programs are discussed. Dose estimates presented in this report are based on hypothetical exposure scenarios of public use of areas near the site. In addition, release estimates have been calculated on the basis of 1994 National Pollutant Discharge Elimination System (NPDES) and air monitoring data. Effluent discharges from the site under routine NPDES and National Emission Standards for Hazardous Air Pollutants (NESHAPS) monitoring were below permitted levels.

NONE

1995-05-01T23:59:59.000Z

359

Application of UAVs at the Savannah River Site  

SciTech Connect

Small, unmanned aerial vehicles (UAVs) equipped with sensors for physical, chemical, and radiochemical measurements of remote environments have been tested at the Savannah River Site (SRS). A miniature helicopter was used as an aerial platform for testing a variety of sensors with outputs integrated with the flight control system for real-time data acquisition and evaluation. The sensors included a precision magnetometer, two broad band infra-red radiometers, a 1-inch by 1-inch Nal(TI) scintillation detector, and an on-board color video camera. Included in the avionics package was an ultrasonic altimeter, a precision barometer, and a portable Global Positioning System. Two separate demonstration locations at SRS were flown that had been previously characterized by careful sampling and analyses and by aerial surveys at high altitudes. The Steed Pond demonstration site contains elevated levels of uranium in the soil and pond silt due to runoff from one of the site`s uranium fuel and target production areas. The soil at the other site is contaminated with oil bearing materials and contains some buried objects. The results and limitations of the UAV surveys are presented and improvements for future measurements are discussed.

Hofstetter, K.J.; Pendergast, M.M.

1996-08-01T23:59:59.000Z

360

Redesigned ORNL DAAC Web Site  

NLE Websites -- All DOE Office Websites (Extended Search)

released a major revision to its Web site on Thursday, released a major revision to its Web site on Thursday, May 27, 2010. The new site includes many enhancements aimed at helping users locate and obtain data products and services. The simplified menu bar allows users to navigate quickly to products and services of interest and to access data through a variety of tools. The DAAC's Web site address remains unchanged (http://daac.ornl.gov), and as always, our products and services are available free of charge. Please note that your user account information will work on the new Web site. The Sign-in and Registration pages have a different look and will accept your email address as the User Name and retain your current password. If you have any problems accessing, signing-in, or registering with our new Web site, please contact our User Services Office, at +1 (865) 241-3952, or

Note: This page contains sample records for the topic "including site characterization" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Closure Sites | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Closure Sites Closure Sites Closure Sites View a list of the compliance agreements for the many EM closure sites, such as Mound and Rocky Flats, below. Associated summaries are also included. Pinellas Remediation Agreement Pinellas Remediation Agreement Summary Maxey Flats Consent Decree -Part 1, April 18, 1996 Maxey Flats Consent Decree -Part 2, April 18, 1996 Maxey Flats Consent Decree April 18, 1996 Summary Monticello Mill site Federal Facility Agreement, December 22, 1988 Monticello Mill site Federal Facility Agreement, December 22, 1988 Summary Battelle Columbus Laboratories Director's Final Findings and Orders, October 4, 1995 Battelle Columbus Laboratories Director's Final Findings and Orders, October 4, 1995 Summary Fernald Environmental Management Project Consent Agreement and Final Order,

362

CERCLA - Site Selector  

NLE Websites -- All DOE Office Websites (Extended Search)

(LEHR) Fernald Preserve Monticello Site Mound Site - Miamisburg Closure Project Rocky Flats Site Weldon Spring Search the Administrative Record The White House USA.gov E-Gov...

363

ORNL DAAC Site Map  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Map ORNL DAAC Site Map About Us About ORNL DAAC Who We Are User Working Group Biogeochemical Dynamics Data Citation Policy News Newsletters Workshops Site Map Products...

364

Savannah River Site  

NLE Websites -- All DOE Office Websites (Extended Search)

River Site Savannah River Site Savannah River Site (SRS) has mission responsibilities in nuclear weapons stockpile stewardship by ensuring the safe and reliable management of...

365

CERCLA - Site Selector  

Office of Legacy Management (LM)

Monticello Site Mound Site - Miamisburg Closure Project Rocky Flats Site Weldon Spring Search the Administrative Record The White House USA.gov E-Gov Information Quality FOIA...

366

Expedited Site Characterization Geophysics: Geophysical Methods and Tools for Site Characterization  

E-Print Network (OSTI)

DOE Office of Environmental Management, or electromagneticOffice of Technology Development, Environmental Restoration and Waste Management,

Goldstein, N.E.

2009-01-01T23:59:59.000Z

367

STATE: HI PROJECT Subtask 2.1 Maui Site: National Marine Renewable Energy Center in Hawaii  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 Maui Site: National Marine Renewable Energy Center in Hawaii 1 Maui Site: National Marine Renewable Energy Center in Hawaii TITLE: Funding Opportunity Announcement Number Procurement Instrument Number NEPA Control Number CID Number DE-PS36-08G098030 DE-FG36-08G018180 GFO-09-013-001 G018180 Based on my review of the information concerning the pro posed action, as NEPA CompHance Officer (authorized under DOE Order 451.1A), I have made the foHowing determination: Cx, EA, EIS APPENDIX AND NUMBER: Description: 83.1 Onsite and offsite site characterization and environmental monitoring, including siting, construction (or modification), operation, and dismantlement or closing (abandonment) of qharacterization and monitoring devices and siting, construction, and associated operation of a small-scale laboratory building or renovation of a room in an existing building

368

Nevada Test Site Environmental Report 2005, Attachment A - Site Description  

SciTech Connect

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Cathy A. Wills

2006-10-01T23:59:59.000Z

369

Division Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Novel Synthetic Methods for Homogeneous and Heterogeneous Catalysts Novel Synthetic Methods for Homogeneous and Heterogeneous Catalysts Our research is directed at developing novel synthetic methods for homogeneous and heterogeneous catalysts. To that end, we are particularly interested in developing well-defined and predictive synthetic routes to pure metals, semiconductors, and insulators. Current projects include the vapor-phase synthesis of photon-harvesting materials and the controlled synthesis of supported first-row transition metal nanoparticles for catalysis. synthetic methods for homogeneous catalysts Our vapor-phase synthesis program is directed at synthesizing higher-order (3 or more elemental components), kinetically stable materials for photon-harvesting (PH) applications such as photocatalysis and photovoltaics. The versatility of solution phase chemical synthesis has yet to be achieved in advanced inorganic materials. The few higher order PH absorber materials which have been reported display unique combinations of thermodynamic stability and kinetic accessibility. We are interested in moving off the phase diagrams to synthesize novel materials with improved photon harvesting abilities for catalysis.

370

Results of Detailed Hydrologic Characterization Tests - Fiscal Year 2003  

SciTech Connect

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

Spane, Frank A.; Newcomer, Darrell R.

2004-09-13T23:59:59.000Z

371

Site Environmental Report for 2002, Volume 1  

Science Conference Proceedings (OSTI)

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1. The ''Site Environmental Report for 2002'' summarizes Berkeley Lab's compliance with environmental standards and requirements, characterizes environmental management efforts through surveillance and monitoring activities, and highlights significant programs and efforts for calendar year 2002. Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as ''Berkeley Lab,'' ''the Laboratory,'' ''Lawrence Berkeley National Laboratory,'' and ''LBNL.'' The report is separated into two volumes. Volume I contains a general overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from the monitoring programs. This year, the ''Site Environmental Report'' was distributed on a CD in PDF format that includes Volume I, Volume II, and related documents. The report is also available on the Web at http://www.lbl.gov/ehs/esg/. The report follows the Laboratory's policy of using the International System of Units (SI), also known as the metric system of measurements. Whenever possible, results are additionally reported using the more conventional (non-SI) system of measurements because this system is referenced by some current regulatory standards and is more familiar to some readers. The tables included at the end of the Glossary are intended to help readers understand the various prefixes used with SI units of measurement and convert these units from one system to the other.

Pauer, Ron

2003-07-01T23:59:59.000Z

372

Historical Time Line and Information About the Hanford Site  

SciTech Connect

Historical time line of the Hanford Site spanning from 1940 through 1997, including photographs and other information regarding the town sites and living conditions.

Briggs Jr, David

2001-03-07T23:59:59.000Z

373

Human Health and Ecological Risk Assessment Work Plan Mud Pit Release Sites, Amchitka Island, Alaska  

SciTech Connect

This Work Plan describes the approach that will be used to conduct human health and ecological risk assessments for Amchitka Island, Alaska, which was utilized as an underground nuclear test site between 1965 and 1971. During this period, the U.S. Atomic Energy Commission (now the U.S. Department of Energy) conducted two nuclear tests (known as Long Shot and Milrow) and assisted the U.S. Department of Defense with a third test (known as Cannikin). Amchitka Island is approximately 42 miles long and located 1,340 miles west-southwest of Anchorage, Alaska, in the western end of the Aleutian Island archipelago in a group of islands known as the Rat Islands. Historically including deep drilling operations required large volumes of drilling mud, a considerable amount of which was left on the island in exposed mud pits after testing was completed. Therefore, there is a need for drilling mud pit remediation and risk assessment of historical mud pit releases. The scope of this work plan is to document the environmental objectives and the proposed technical site investigation strategies that will be utilized for the site characterization of the constituents in soil, surface water, and sediment at these former testing sites. Its goal is the collection of data in sufficient quantity and quality to determine current site conditions, support a risk assessment for the site surfaces, and evaluate what further remedial action is required to achieve permanent closure of these three sites that will protect both human health and the environment. Suspected compounds of potential ecological concern for investigative analysis at these sites include diesel-range organics, polyaromatic hydrocarbons, polychlorinated biphenyls, volatile organic compounds, and chromium. The results of these characterizations and risk assessments will be used to evaluate corrective action alternatives to include no further action, the implementation of institutional controls, capping on site, or off-sit e disposal of contaminated waste. The results of this evaluation will be presented in a subsequent corrective action decision document.

DOE /NV

2001-03-12T23:59:59.000Z

374

1999 SITE ENVIRONMENTAL REPORT  

SciTech Connect

Throughout the scientific community, Brookhaven National Laboratory (BNL) is renowned for its leading-edge research in physics, medicine, chemistry, biology, materials, and the environment. BNL is committed to supporting its world-class scientific research with an internationally recognized environmental protection program. The 1999 Site Environmental Report (SER) summarizes the status of the Laboratory's environmental programs and performance, including the steady progress towards cleaning up the site and fully integrating environmental stewardship into all facets of the Laboratory's mission. BNL is located on 5,265 acres of pine barrens in Suffolk County in the center of Long Island, New York. The Laboratory is situated above a sole source aquifer at the headwaters of the Peconic River; therefore, protecting ground and surface water quality is a special concern. Approximately 3,600 acres of the site are undeveloped and serve as habitat for a wide variety of animals and plants, including one New York State endangered species, the tiger salamander, and two New York State threatened species, the banded sunfish and the stiff goldenrod. Monitoring, preserving, and restoring these ecological resources is a high priority for the Laboratory.

ENGEL-COX,J.; ZIMMERMAN,E.; LEE,R.; WILLIAMS,J.; GREEN,T.; PAQUETTE,D.; HOODA,B.; SCARPITTA,S.; GENZER,P.; ET AL

2000-09-01T23:59:59.000Z

375

Site Environmental Report for 1999 - Volume 1  

Science Conference Proceedings (OSTI)

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1. The Site Environmental Report for 1999 is intended to summarize Berkeley Lab's compliance with environmental standards and requirements, characterize environmental management efforts through surveillance and monitoring activities, and highlight significant programs and efforts for calendar year 1999. The report is separated into two volumes. Volume I contains a general overview of the Laboratory, the status of environmental programs, and summary results from surveillance and monitoring activities. Each chapter in Volume I begins with an outline of the sections that follow, including any tables or figures found in the chapter. Readers should use section numbers (e.g., {section}1.5) as navigational tools to find topics of interest in either the printed or the electronic version of the report. Volume II contains the individual data results from monitoring programs.

Ruggieri, M.

2000-08-12T23:59:59.000Z

376

Environmental assessment: Deaf Smith County site, Texas  

SciTech Connect

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

1986-05-01T23:59:59.000Z

377

Umatilla Satellite and Release Sites Project : Final Siting Report.  

DOE Green Energy (OSTI)

This report presents the results of site analysis for the Umatilla Satellite and Release Sites Project. The purpose of this project is to provide engineering services for the siting and conceptual design of satellite and release facilities for the Umatilla Basin hatchery program. The Umatilla Basin hatchery program consists of artificial production facilities for salmon and steelhead to enhance production in the Umatilla River as defined in the Umatilla master plan approved in 1989 by the Northwest Power Planning Council. Facilities identified in the master plan include adult salmon broodstock holding and spawning facilities, facilities for recovery, acclimation, and/or extended rearing of salmon juveniles, and development of river sites for release of hatchery salmon and steelhead. The historic and current distribution of fall chinook, summer chinook, and coho salmon and steelhead trout was summarized for the Umatilla River basin. Current and future production and release objectives were reviewed. Twenty seven sites were evaluated for the potential and development of facilities. Engineering and environmental attributes of the sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites wer