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Sample records for site characterization final

  1. Preliminary site characterization - final report

    Energy Technology Data Exchange (ETDEWEB)

    Clark, D.; Smith, L.B.

    1993-12-01

    This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft {open_quotes}Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Site{close_quotes}. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit.

  2. Preliminary site characterization - final report

    International Nuclear Information System (INIS)

    Clark, D.; Smith, L.B.

    1993-12-01

    This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft open-quotes Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Siteclose quotes. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit

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

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-09-09

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

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

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-12-14

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

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

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    2000-01-01

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

  6. [Paleoclimatology studies for Yucca Mountain site characterization]. Final report

    International Nuclear Information System (INIS)

    1996-01-01

    This report consists of two separate papers: Fernley Basin studies; and Influence of sediment supply and climate change on late Quaternary eolian accumulation patterns in the Mojave Desert. The first study involved geologic mapping of late Quaternary sediments and lacustrine features combined with precise control of elevations and descriptions of sediments for each of the major sedimentary units. The second paper documents the response of a major eolian sediment transport system in the east-central Mojave Desert: that which feeds the Kelso Dune field. Information from geomorphic, stratigraphic, and sedimentologic studies of eolian deposits and landforms is combined with luminescence dating of these deposits to develop a chronology of periods of eolian deposition. Both studies are related to site characterization studies of Yucca Mountain and the forecasting of rainfall patterns possible for the high-level radioactive waste repository lifetime

  7. Hydrogeological-Geophysical Methods for Subsurface Site Characterization - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Rubin, Yoram

    2001-01-01

    The goal of this research project is to increase water savings and show better ecological control of natural vegetation by developing hydrogeological-geophysical methods for characterizing the permeability and content of water in soil. The ground penetrating radar (GPR) tool was developed and used as the surface geophysical method for monitoring water content. Initial results using the tool suggest that surface GPR is a viable technique for obtaining precision volumetric water content profile estimates, and that laboratory-derived petrophysical relationships could be applied to field-scale GPR data. A field-scale bacterial transport study was conducted within an uncontaminated sandy Pleistocene aquifer to evaluate the importance of heterogeneity in controlling the transport of bacteria. Geochemical, hydrological, geological, and geophysical data were collected to characterize the site prior to and after chemical and bacterial injection experiments. Study results shows that, even within the fairly uniform shallow marine deposits of the narrow channel focus area, heterogeneity existed that influenced the chemical tracer transport over lateral distances of a few meters and vertical distances of less than a half meter. The interpretation of data suggest that the incorporation of geophysical data with limited hydrological data may provide valuable information about the stratigraphy, log conductivity values, and the spatial correlation structure of log conductivity, which have traditionally been obtainable only by performing extensive and intrusive hydrological sampling.

  8. Final work plan: Expedited Site Characterization of the IES Industries, Inc., Site at Marshalltown, Iowa. Ames Expedited Site Characterization Project, Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-04

    The overall goal of the Ames Laboratory Expedited Site Characterization (ESC) project is to evaluate and promote both innovative and state-of-the-practice site characterization and/or monitoring technologies. This will be accomplished by fielding both types of technologies together in the context of an expedited site characterization. The first site will be at a former manufactured gas plant (FMGP) in Marshalltown, Iowa. The project will field three areas of technology: geophysical, analytical, and data fusion. Geophysical technologies are designed to understand the subsurface geology to help predict fate and transport of the target contaminants. Analytical technologies/methods are designed to detect and quantify the target contaminants. Data fusion technology consists of software systems designed to rapidly integrate or fuse all site information into a conceptual site model that then becomes the decision making tool for the site team to plan subsequent sampling activity. Not all of the contaminants present can be located at the action level. Polynuclear aromatic hydrocarbons (PAHs) are the signature organics associated with the coal tar activities that took place at the site. As a result, PAHs were selected as the target compounds. Screening analytical instruments and nonintrusive geophysical techniques will be fielded to qualitatively map the spatial contaminant distribution. Soil gas surveys, immunoassay testing (IMA), innovative optical techniques, and passive organic sorbent sensors will be deployed along with the geophysical methods. Gas chromatography/mass spectrometry (GC/MS) instruments and a cone penetrometer system equipped with a laser-induced fluorescence (LIF) probe will quantitatively map the action level edges of the PAH plume(s). Samples will be taken both by the cone penetrometer test system (CPT) and the Geoprobe {reg_sign} sampler system.

  9. Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

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

  10. A radionujclides suite selection for site characterization and final status survey in the U.S. NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Peng Fei; Ahn, Seo Young [Pusan National University, Busan (Korea, Republic of); Jeon, Yeo Ryeong; Kim, Yong Min [Catholic University of Daegu, Daegu (Korea, Republic of); Lee, Jong Seh [Hanyang University, Seoul (Korea, Republic of)

    2016-09-15

    For the decommissioning of a nuclear power plant, a site characterization and final status survey require a site-specific suite of radionuclides that could potentially still be present in the site during or after the decontamination processes. The United States Nuclear Regulatory Commission (U.S. NRC) requires a Decommissioning Technical Base Document (DTBD) along with a Site Characterization and Historical Site Assessment (HSA) from the utility for decommissioning to proceed. Both the DTBD and HSA are preliminary components of the Radiological Site Survey investigation process and should be included in the final License Termination Plan (LTP) for site release and reuse consideration from the U.S. NRC and the utility company. This study reviews the United States Nuclear Power Plants (U.S. NPPs) decommissioning cases and is especially focused on the methodologies used for determining a site-specific suite of radionuclides before and during the site characterization and final status surveys. In 2017, Kori-1 will be ready for decommissioning and related preparations are ongoing, this review will help Korea to prepare regulatory guidelines and give technical background for the safe and successful decommissioning of NPPs.

  11. A radionujclides suite selection for site characterization and final status survey in the U.S. NPPs

    International Nuclear Information System (INIS)

    Zhao, Peng Fei; Ahn, Seo Young; Jeon, Yeo Ryeong; Kim, Yong Min; Lee, Jong Seh

    2016-01-01

    For the decommissioning of a nuclear power plant, a site characterization and final status survey require a site-specific suite of radionuclides that could potentially still be present in the site during or after the decontamination processes. The United States Nuclear Regulatory Commission (U.S. NRC) requires a Decommissioning Technical Base Document (DTBD) along with a Site Characterization and Historical Site Assessment (HSA) from the utility for decommissioning to proceed. Both the DTBD and HSA are preliminary components of the Radiological Site Survey investigation process and should be included in the final License Termination Plan (LTP) for site release and reuse consideration from the U.S. NRC and the utility company. This study reviews the United States Nuclear Power Plants (U.S. NPPs) decommissioning cases and is especially focused on the methodologies used for determining a site-specific suite of radionuclides before and during the site characterization and final status surveys. In 2017, Kori-1 will be ready for decommissioning and related preparations are ongoing, this review will help Korea to prepare regulatory guidelines and give technical background for the safe and successful decommissioning of NPPs

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

    International Nuclear Information System (INIS)

    2002-01-01

    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

  13. Site characterization plan:

    International Nuclear Information System (INIS)

    1988-01-01

    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

  14. Site characterization plan:

    International Nuclear Information System (INIS)

    1988-01-01

    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

  15. Collaborative Research: Hydrogeological-Geophysical Methods for Subsurface Site Characterization - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mavko, G.

    2000-01-01

    This research contributes three newly-developed relationships that significantly improve aquifer characterization: (1) a general relationship between total and channel porosities, (2) a general relationship between electrical resistivity and channel porosity, and (3) bounds on the electrical resistivity - seismic velocity relationship.

  16. Site characterization in connection with the low level defense waste management site in Area 5 of the Nevada Test Site, Nye County, Nevada. Final report

    International Nuclear Information System (INIS)

    Case, C.; Davis, J.; French, R.; Raker, S.

    1984-09-01

    The Site Characterization Report for the Defense Low Level Waste Management Site (RWMS) in Area 5 of the Nevada Test Site deals with the FY80-FY84 DRI activities. The areas that have been studied include geology, hydrology, unsaturated flow, soil and soil water chemistry, flood hazard, and economics-demographics. During this time the site characterization effort focussed on the following items as requested by NVO: geological and hydrological limitations to greater depth disposal of radioactive waste; potential for tectonic, seismic or volcanic activity (extent and frequency which these processes significantly affect the ability of the disposal operation to meet performance objectives); the possibility of groundwater intrusion into the waste zone, and its significance; topography of the RWMS with significance to drainage and flood potential (100-year flood plain, coastal high-hazard area or wetland); upstream drainage which may require modification to avoid erosion; population growth and future development; and the presence or absence of economically significant natural resources which, if exploited, would result in failure to meet performance objectives. The items mentioned above are dealt with in the description of activities and results in the body of the report. Extensive references, 32 figures, 20 tables

  17. Site characterization techniques used in environmental restoration activities. Final report of a co-ordinated research project 1995-1999

    International Nuclear Information System (INIS)

    2000-05-01

    The objective of this CRP was to promote the exchange of information on the practical experience gained by the Member States in characterization of radioactively contaminated sites. Special emphasis was placed on the development of methods and techniques for the optimization of radiological characterization. In particular, the scope included: definition of a strategy for site characterization; sampling and measurement techniques; data management, including statistical analysis and deterministic radionuclide migration modelling; and post-cleanup radiological surveys and assurance of compliance with release criteria

  18. TTP AL921102: An integrated geophysics program for non-intrusive characterization of mixed-Waste landfill sites. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hasbrouck, J.C.

    1993-09-01

    This Technical Task conducted for the US Department of Energy Office of Technology Development demonstrates the effectiveness of integrating several surface geophysical techniques to nonintrusively characterize mixed-waste landfill sites. An integrated approach enables an area to be characterized faster and cheaper because repeated access is not necessary and offers data and interpretations not attainable by a single technique. Field demonstrations using the complex galvanic resistivity, spontaneous potential (SP), ground-penetrating radar (GPR), time-domain electromagnetic (TDEM), shear-wave (S-wave) seismic and compressional-wave (P-wave) seismic geophysical techniques were conducted at the Mixed-Waste Landfill Integrated Demonstration (MWLID) test site at the Sandia National Laboratories/New Mexico in Albuquerque. Data were acquired in two areas that have both known and unknown attributes. Although data from numerous profiles were analyzed, three lines were chosen as representative of the landfill site: Line 20E that crosses both the known Chromic Acid and Organics Pits, Line 60E that transectes an essentially barren area, and Line 125E located in an area with unknown subsurface conditions.

  19. Site characterization handbook

    Energy Technology Data Exchange (ETDEWEB)

    1988-06-01

    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.

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

    International Nuclear Information System (INIS)

    Stetzenbach, K.; Farnham, I.

    1996-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Stetzenbach, K.; Farnham, I.

    1996-06-01

    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.

  2. CHARACTERIZING SITE HYDROLOGY (REGION 5)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  3. Northeast Oregon Hatchery Project final siting report. Final report

    International Nuclear Information System (INIS)

    1995-03-01

    This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven 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 were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed

  4. Hanford site waste tank characterization

    International Nuclear Information System (INIS)

    De Lorenzo, D.S.; Simpson, B.C.

    1994-08-01

    This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order

  5. Hanford site waste tank characterization

    Energy Technology Data Exchange (ETDEWEB)

    De Lorenzo, D.S.; Simpson, B.C.

    1994-08-01

    This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order.

  6. Probabilistic Approach to Site Characterization: MIU site, Tono Region, Japan

    Energy Technology Data Exchange (ETDEWEB)

    MCKENNA, SEAN A.

    2001-02-01

    Geostatistical simulation is used to extrapolate data derived from site characterization activities at the MIU site into information describing the three-dimensional distribution of hydraulic conductivity at the site and the uncertainty in the estimates of hydraulic conductivity. This process is demonstrated for six different data sets representing incrementally increasing amounts of characterization data. Short horizontal ranges characterize the spatial variability of both the rock types (facies) and the hydraulic conductivity measurements. For each of the six data sets, 50 geostatistical realizations of the facies and 50 realizations of the hydraulic conductivity are combined to produce 50 final realizations of the hydraulic conductivity distribution. Analysis of these final realizations indicates that the mean hydraulic conductivity value increases with the addition of site characterization data. The average hydraulic conductivity as a function of elevation changes from a uniform profile to a profile showing relatively high hydraulic conductivity values near the top and bottom of the simulation domain. Three-dimensional uncertainty maps show the highest amount of uncertainty in the hydraulic conductivity distribution near the top and bottom of the model. These upper and lower areas of high uncertainty are interpreted to be due to the unconformity at the top of the granitic rocks and the Tsukyoshi fault respectively.

  7. Umatilla Satellite and Release Sites Project : Final Siting Report.

    Energy Technology Data Exchange (ETDEWEB)

    Montgomery, James M.

    1992-04-01

    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 were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

  8. Preliminary Site Characterization Report, Rulsion Site, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

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

  9. SNF Site Characterization Data: C.Jarvis

    Data.gov (United States)

    National Aeronautics and Space Administration — Site characterization parameters (canopy density, litter components, soil characterization: color, moisture, components) for selected sites within the Superior...

  10. Northeast Oregon Hatchery Project, Final Siting Report.

    Energy Technology Data Exchange (ETDEWEB)

    Watson, Montgomery

    1995-03-01

    This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven 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 were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

  11. Final vegetative cover for closed waste sites

    International Nuclear Information System (INIS)

    Cook, J.R.; Salvo, S.K.

    1993-01-01

    Low-level, hazardous, and mixed waste disposal sites normally require some form of plant material to prevent erosion of the final closure cap. Waste disposal sites are closed and capped in a complex scientific manner to minimize water infiltration and percolation into and through the waste material. Turf type grasses are currently being used as an interim vegetative cover for most sites. This coverage allows for required monitoring of the closure cap for settlement and maintenance activities. The purpose of this five year study was to evaluate plant materials for use on wastes sites after the post-closure care period that are quickly and easily established and economically maintained, retard water infiltration, provide maximum year-round evapotranspiration, are ecologically acceptable and do not harm the closure cap. The results of the study suggest that two species of bamboo (Phyllostachys (P.) bissetii and P. rubromarginata) can be utilized to provide long lived, low maintenance, climax vegetation for the waste sites after surveillance and maintenance requirements have ceased

  12. Yucca Mountain Site Characterization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Gertz, C.P.; Bartlett, J.

    1992-01-01

    The purpose of this document is to describe the Yucca Mountain Site Characterization Project (YMP) and establish an approved YMP baseline against which overall YMP progress and management effectiveness shall be measured. For the sake of brevity, this document will be referred to as the Project Plan throughout this document. This Project Plan only addresses activities up to the submittal of the repository license application (LA) to the Nuclear Regulatory Commission (NRC). A new Project Plan will be submitted to establish the technical, cost, and schedule baselines for the final design and construction phase of development extending through the start of repository operations, assuming that the site is determined to be suitable.

  13. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

  14. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC ampersand FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate

  15. Site Characterization Progress Report No.20

    Energy Technology Data Exchange (ETDEWEB)

    DOE

    1999-10-01

    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.

  16. QuickSiteSM, the Argonne expedited site characterization methodology

    International Nuclear Information System (INIS)

    Burton, J.C.; Meyer, W.T.

    1997-09-01

    Expedited site characterization (ESC), developed by Argonne National Laboratory, is an interactive, integrated process emphasizing the use of existing data of sufficient quality, multiple complementary characterization methods, and on-site decision making to optimize site investigations. The Argonne ESC is the basis for the provisional ESC standard of the ASTM (American Society for Testing and Materials). QuickSite SM is the implementation package developed by Argonne to facilitate ESC of sites contaminated with hazardous wastes. At various sites, Argonne has successfully implemented QuickSite SM and demonstrated the technical superiority of the ESC process over traditional methodologies guided by statistics and random-sampling approaches. For example, in a QuickSite SM characterization of a perched aquifer at the Pantex Plant in Texas, past data and geochemical analyses of existing wells were used to develop a model for recharge and contaminant movement. With the model as a guide, closure was achieved with minimal field work

  17. 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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    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)

  18. Site 300 Bat Monitoring Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Drennan, Joe [Garcia and Associates, San Francisco, CA (United States); Tortosa, Justin [Garcia and Associates, San Francisco, CA (United States)

    2016-07-18

    From June 15 to 18, 2015, GANDA biologist Graham Neale assisted in programming and fieldtesting of the bat monitoring equipment. The equipment was deployed in the field on a meteorological (MET) tower within Site 300 on June 18, 2015.

  19. Natural phenomena hazards site characterization criteria

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

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

  20. Hanford Site pollution prevention progress report; FINAL

    International Nuclear Information System (INIS)

    BETSCH, M.D.

    1999-01-01

    The Richland Operations Office (RL) and Office of River Protection (ORP) are pleased to issue the attached Pollution Prevention Progress Report. We have just met the most aggressive waste reduction and A recycling goals to date and are publishing this report to recognize A the site's progress, and to ensure it will sustain success beyond 1 Fiscal Year 2000. This report was designed to inform the been made by RL and ORP in Waste Minimization (WMin) and Pollution Prevention (P2). RL, ORP and their contractors are committed to protecting the environment, and we reiterate pollution prevention should continue to be at the forefront of the environmental cleanup and research efforts. As you read the attached report, we believe you will see a clear demonstration of RL and ORP's outstanding performance as it has been responsible and accountable to the nation, its employees, and the community in which we live and work. commitment that all employees have for environmental stewardship. The report provides useful information about the U.S. Department of Energy's (DOE'S) environmental policy and programs, and contains countless examples of waste minimization projects. This year was the first year our site received the White House Closing the Circle in the category of Affirmative Procurement. This Award recognizes our site for designing a comprehensive strategy for achieving 100 percent purchases of the U.S.Environmenta1 Protection Agency designated recycled items. DOE-Headquarters also acknowledged the site in 1999 for its public outreach efforts in communicating pollution prevention to Hanford Site employees and the community. Our site is truly a recognized leader in outreach as it has kept this title for two consecutive years. In previous years, we received the White House Closing the Circle Honorable Mention in Affirmative Procurement and several other National DOE Awards. Through partnership with the local community and stakeholders, the site and its contractors have a clear

  1. Double tracks test site characterization report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

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

  2. Shaft siting decision report: Final report

    International Nuclear Information System (INIS)

    1985-11-01

    The purpose of this study is to identify and establish relative guidelines to be used for siting of repository shafts. Weights were determined for the significant factors which impact the selection of shaft locations for a nuclear waste repository in salt. The study identified a total of 45 factors. A panel of experienced mining people utilized the Kepner-Tregoe (K-T) Decision Analysis Process to perform a structured evaluation of each significant shaft siting factor. The evaluation determined that 22 of the factors were absolute constraints and that the other 23 factors were desirable characteristics. The group established the relative weights for each of the 23 desirable characteristics by using a paired comparison method. 49 refs., 2 figs., 5 tabs

  3. 10 CFR 60.15 - Site characterization.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Site characterization. 60.15 Section 60.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Licenses Preapplication Review § 60.15 Site characterization. (a) Prior to submittal of an application for a license to be...

  4. Structuring a cost-effective site characterization

    International Nuclear Information System (INIS)

    Berven, B.A.; Little, C.A.; Swaja, R.E.

    1990-01-01

    Successful chemical and radiological site characterizations are complex activities which require meticulously detailed planning. Each layer of investigation is based upon previously generated information about the site. Baseline historical, physical, geological, and regulatory information is prerequisite for preliminary studies at a site. Preliminary studies then provide samples and measurements which define the identity of potential contaminants and define boundaries around the area to be investigated. The goal of a full site characterization is to accurately determine the extent and magnitude of contaminants and carefully define the site conditions such that the future movements of site contaminants can be assessed for potential exposure to human occupants and/or environmental impacts. Critical to this process is the selection of appropriate measurement and sampling methodology, selection and use of appropriate instrumentation and management/interpretation of site information. Site investigations require optimization between the need of information to maximize the understanding of site conditions and the cost of acquiring that information. 5 refs., 1 tab

  5. Socioeconomic monitoring and mitigation plan for site characterization: Revision 1

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the SMMP is to document compliance with the NWPA. In order to do so, a summary description of site characterization activities based on the consultation draft of the Site Characterization Plan and the final EA is provided. Subsequent chapters identify issues related to the potential for significant adverse impacts and the monitoring plans proposed to determine whether those impacts occur. Should monitoring confirm the potential for significant adverse impact, mitigative maesures will be developed. In the context of site characterization, mitigation is defined as those changes in site characterization activities that serve to avoid or minimize, to the maximum extent practicable, any significant adverse environmental impacts. Proposed site characterization activites involve a variety of surface and subsurface activities including site preparation, access road construction and improvment, exploratory drilling and testing, geophysical surveys, geological mapping, and construction of the exploratory shaft facility. It is not anticipated that any significant adverse socioeconomic impacts will result form any of the proposed site characterization activities. However, the assessment of impacts in the EA, especially impacts related to employment and population growth, was based on assumptions concerning activities and conditions during the site characterization phase

  6. Summary of repository siting models. Final report

    International Nuclear Information System (INIS)

    Thomas, S.D.; Ross, B.; Mercer, J.W.

    1982-07-01

    This report is the first in a series of reports that will provide critical reviews and summaries of computer programs that can be used to analyze the potential performance of a high-level radioactive waste repository. The computer programs identified address the following phenomena: saturated and unsaturated subsurface flow, heat transport, solute transport, surface water runoff, geomechanical interactions, and geochemical interactions. The report identifies 183 computer programs that can be used to analyze a repository site and provides a summary description of 31 computer programs. The summary descriptions can be used: to assist in code evaluation, to facilitate code comparison, to determine applicability of codes to specific problems, to identify code deficiencies, and to provide a screening mechanism for code selection

  7. CHARACTERIZING SITE HYDROLOGY (WORKSHOP MSA PRESENTATION)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  8. Characterizing Site Hydrology (Region 10, Seattle, WA)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  9. CHARACTERIZING SITE HYDROLOGY (REGION 8 WORKSHOP)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  10. International Symposium on Site Characterization for CO2Geological Storage

    Energy Technology Data Exchange (ETDEWEB)

    Tsang, Chin-Fu

    2006-02-23

    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.

  11. Site characterization studies in the NWTS program

    International Nuclear Information System (INIS)

    Shipler, D.; Evans, G.

    1980-01-01

    The US Department of Energy (DOE) has the responsibility to identify sites and construct and operate facilities for the storage or isolation of spent fuel and/or reprocessing radioactive wastes from commercial nuclear power plants. The National Waste Terminal Storage (NWTS) Program has been initiated by the DOE to develop the technology and demonstrate the feasibility of burial and isolation of high level radioactive waste in deep geologic formations. The NTWS Program plan which sets forth the criteria, procedures, and other considerations required to characterize and select a site in a comprehensive stepwise manner is discussed. The plan is not specific to any given geologic medium but serves as a guide for site selection in any geohydrologic system deemed appropriate for consideration for a deep geologic repository. The plan will be used by all NWTS Project Offices in the conduct of their site characterization program. The plan will be updated, as warranted, to reflect technology development, National policies, rulemakings by regulatory agencies, and other changing political, social, and institutional considerations. Site characterization begins with the identification of regions believed to have suitable geologic, hydrologic, and environmental characteristics for repository siting. This is followed by an iterative process of data collection and analysis to identify areas and locations which appear most suitable for further investigations. In addition, screening studies of the DOE's nuclear complexes has led to the selection of the Nevada Test Site and the Hanford Site for further characterization studies. The site characterization process results in a number of candidate sites from which a site will be selected and proposed to the NRC for licensing

  12. Draft reclamation program plan for site characterization

    International Nuclear Information System (INIS)

    1989-08-01

    As part of its obligations under the Nuclear Waste Policy Act, as amended, the US Department of Energy (DOE) has developed an environmental program that is to be implemented during site characterization at the Yucca Mountain site. This site is proposed for the location of the nation's first high-level radioactive waste repository. A program for the reclamation of areas disturbed by site characterization is part of the overall environmental program for that site. This Reclamation Program Plan (RPP) describes the reclamation policy of the DOE for the Yucca Mountain site and presents an overview of the reclamation program. The RPP also provides an overview of the reclamation needs relative to site characterization; a review of legislation and requirements pertinent to reclamation; and a review of previous commitments made by the DOE to certain types of reclamation activities. The objective of the DOE reclamation program at Yucca Mountain is to return land disturbed by site-characterization activities to a stable ecological state with a form and productivity similar to the predisturbance state. The DOE will take all reasonable and necessary steps to achieve this objective. 19 refs., 2 tabs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-03-01

    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

  14. Plans for characterization of salt sites

    Energy Technology Data Exchange (ETDEWEB)

    Heim, G.E.; Matthews, S.C.; Kircher, J.F.; Kennedy, R.K.

    1983-01-01

    This basic salt site characterization program has been designed to provide the data required to support the design, performance assessment, and licensing of each of the principal project elements: the repository, the shafts, and the surface facilities. The work has been sequenced to meet the design and licensing schedule. It is anticipated that additional characterization activities will be performed to address site-specific considerations and to provide additional information to address questions which arise during the evaluation of characterization data. 3 figures, 3 tables.

  15. Yucca Mountain site characterization project: Site atlas 1997. Part 1

    International Nuclear Information System (INIS)

    1997-01-01

    The US Department of Energy (DOE) is conducting site characterization studies at Yucca Mountain, Nevada, to determine if the site is suitable for an underground repository for the permanent disposal of high-level radioactive waste. The Yucca Mountain Project (YMP) Site Atlas is a tool used to cartographically display some of the Geographic Information System (GIS) data in the form of thematic map products. Essentially, the Site Atlas is a compilation of map products that are designed to illustrate the location and extent of site characterization studies. Additionally, the Site Atlas provides maps showing project administrative boundaries and basemaps in the vicinity of the project. The data are current through September 1997. The Atlas is divided into two parts: Part 1 contains GIS maps and supporting characteristic data for geology; stratigraphy; tectonics; volcanism; hydrology; geochemistry; environmental issues; paleontology; repository design; YMP boreholes, trenches, pits, pavements, and exposures; basemap features; and surface-based testing activities, and Part 2 contains 1:6,000- and 1:12,000-scale orthophotography basemaps and orthophotography-based hypsography maps (topographic data). This data is shown at a 50% reduction. The maps and orthophotographs in this Site Atlas are provided to YMP participants as an informational source only and are not for making precise measurements. The Quality Assurance Requirements and Description statement on each map identifies the quality status of the thematic data presented. The Site Atlas is not a comprehensive guide; it does not include all scientific features or studies undertaken for the YMP. The features presented are a small subset of the total work being conducted for the project

  16. Site characterization in fractured crystalline rock

    International Nuclear Information System (INIS)

    Andersson, Peter; Andersson, J.E.; Gustafsson, E.; Nordqvist, R.; Voss, C.

    1993-03-01

    This report concerns a study which is part of the SKI performance assessment project SITE-94. SITE-94 is a performance assessment of a hypothetical repository at a real site. The main objective of the project is to determine how site specific data should be assimilated into the performance assessment process and to evaluate how uncertainties inherent in site characterization will influence performance assessment results. Other important elements of SITE-94 are the development of a practical and defensible methodology for defining, constructing and analyzing scenarios, the development of approaches for treatment of uncertainties, evaluation of canister integrity, and the development and application of an appropriate Quality Assurance plan for Performance Assessments. (111 refs.)

  17. North Central Regional Geologic Characterization Report. Executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final North Central Regional Geologic Characterization Report (RGCR) is issued primarily for public information purposes and provides a general overview of the report. The complete RGCR presents available regional geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the states within the North Central Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening

  18. Northeastern Regional Environmental Characterization Report. Executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final Northeastern Regional Environmental Characterization Report (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Connecticut, Maine, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont. For each of the states within the Northeastern Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  19. North Central regional environmental characterization report: executive summary - final

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final North Central Regional Environmental Characterization Report (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the States within the North Central Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  20. Southeastern Regional Environmental Characterization Report: executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final ''Southeastern Regional Environmental Characterization Report'' (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository or high-level nuclear waste in crystalline rock in central Maryland; noncoastal Virginia, North Carolina, and South Carolina; and northern Georgia. For each of the states within the Southeastern Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  1. Northeastern Regional Geologic Characterization Report: executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final Northeastern Regional Geologic Characterization Report (RGCR) is issued primarily for public information purposes and provides a general overview of the report. The complete RGCR presents available regional geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Connecticut, Maine, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont. For each of the states within the Northeastern Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening. 5 refs., 3 figs

  2. Biological tracer for waste site characterization

    International Nuclear Information System (INIS)

    Strong-Gunderson, J.

    1995-01-01

    Remediating hazardous waste sites requires detailed site characterization. In groundwater remediation, characterizing the flow paths and velocity is a major objective. Various tracers have been used for measuring groundwater velocity and transport of contaminants, colloidal particles, and bacteria and nutrients. The conventional techniques use dissolved solutes, dyes. and gases to estimate subsurface transport pathways. These tracers can provide information on transport and diffusion into the matrix, but their estimates for groundwater flow through fractured regions are very conservative. Also, they do not have the same transport characteristics as bacteria and suspended colloid tracers, both of which must be characterized for effective in-place remediation. Bioremediation requires understanding bacterial transport and nutrient distribution throughout the acquifer, knowledge of contaminants s mobile colloidal particles is just essential

  3. Site selection - siting of the final repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    2011-03-01

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  4. Site selection - siting of the final repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  5. Expedited site characterization. Innovative technology summary report

    International Nuclear Information System (INIS)

    1998-12-01

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

  6. Site characterization plan: Gulf Coast salt domes

    International Nuclear Information System (INIS)

    1983-12-01

    The National Waste Terminal Storage (NWTS) program of the US Department of Energy (DOE) is responsible for developing technology and providing facilities for safe, environmentally acceptable, permanent disposal of high-level nuclear waste. The Office of Nuclear Waste Isolation has been intensively investigating Gulf Coast Salt Dome Basin salt domes and bedded salt in Texas and Utah since 1978. In the Gulf Coast, the application of screening criteria in the region phase led to selection of eight domes for further study in the location phase. Further screening in the area phase identified four domes for more intensive study in the location phase: Oakwood Dome, Texas; Vacherie Dome, Louisiana; and Richton Dome and Cypress Creek Dome, Mississippi. For each dome, this Site Characterization Plan identifies specific hydrologic, geologic, tectonic, geochemical, and environmental key issues that are related to the DOE/NWTS screening criteria or affect the feasibility of constructing an exploratory shaft. The Site Characterization Plan outlines studies need to: (1) resolve issues sufficiently to allow one or more salt domes to be selected and compared to bedded salt sites in order to determine a prime salt site for an exploratory shaft; (2) conduct issue-related studies to provide a higher level of confidence that the preferred salt dome site is viable for construction of an exploratory shaft; and (3) provide a vehicle for state input to issues. Extensive references, 7 figures, 20 tables

  7. Site characterization report for the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1982-11-01

    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

  8. Final Technical Report: Characterizing Emerging Technologies.

    Energy Technology Data Exchange (ETDEWEB)

    King, Bruce Hardison [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hansen, Clifford [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gonzalez, Sigifredo [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    The Characterizing Emerging Technologies project focuses on developing, improving and validating characterization methods for PV modules, inverters and embedded power electronics. Characterization methods and associated analysis techniques are at the heart of technology assessments and accurate component and system modeling. Outputs of the project include measurement and analysis procedures that industry can use to accurately model performance of PV system components, in order to better distinguish and understand the performance differences between competing products (module and inverters) and new component designs and technologies (e.g., new PV cell designs, inverter topologies, etc.).

  9. SWiFT site atmospheric characterization

    Energy Technology Data Exchange (ETDEWEB)

    Kelley, Christopher Lee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ennis, Brandon Lee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Historical meteorological tall tower data are analyzed from the Texas Tech University 200 m tower to characterize the atmospheric trends of the Scaled Wind Farm Technologies (SWiFT) site. In this report the data are analyzed to reveal bulk atmospheric trends, temporal trends and correlations of atmospheric variables. Through this analysis for the SWiFT turbines the site International Electrotechnical Commission (IEC) classification is determined to be class III-C. Averages and distributions of atmospheric variables are shown, revealing large fluctuations and the importance of understanding the actual site trends as opposed to simply using averages. The site is significantly directional with the average wind speed from the south, and particularly so in summer and fall. Site temporal trends are analyzed from both seasonal (time of the year) to daily (hour of the day) perspectives. Atmospheric stability is seen to vary most with time of day and less with time of year. Turbulence intensity is highly correlated with stability, and typical daytime unstable conditions see double the level of turbulence intensity versus that experienced during the average stable night. Shear, veer and atmospheric stability correlations are shown, where shear and veer are both highest for stable atmospheric conditions. An analysis of the Texas Tech University tower anemometer measurements is performed which reveals the extent of the tower shadow effects and sonic tilt misalignment.

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  11. A teleoperated system for remote site characterization

    Energy Technology Data Exchange (ETDEWEB)

    Sandness, G.A. [Pacific Northwest Lab., Richland, WA (United States); Richardson, B.S. [Oak Ridge National Lab., TN (United States); Pence, J. [Lawrence Livermore National Lab., CA (United States)

    1993-08-01

    The detection and characterization of buried objects and materials is an important first step in the restoration of burial sites containing chemical and radioactive waste materials at Department of Energy (DOE) and Department of Defense (DOD) facilities. To address the need to minimize the exposure of on-site personnel to the hazards associated with such sites, the DOE Office of Technology Development and the US Army Environmental Center have jointly supported the development of the Remote Characterization System (RCS). One of the main components of the RCS is a small remotely driven survey vehicle that can transport various combinations of geophysical and radiological sensors. Currently implemented sensors include ground-penetrating radar, magnetometers, an electromagnetic induction sensor, and a sodium iodide radiation detector. The survey vehicle was constructed predominantly of non-metallic materials to minimize its effect on the operation of its geophysical sensors. The system operator controls the vehicle from a remote, truck-mounted, base station. Video images are transmitted to the base station by an radio link to give the operator necessary visual information. Vehicle control commands, tracking information, and sensor data are transmitted between the survey vehicle and the base station by means of a radio ethernet link. Precise vehicle tracking coordinates are provided by a differential Global Positioning System (GPS). The sensors are environmentally protected, internally cooled, and interchangeable based on mission requirements. To date, the RCS has been successfully tested at the Oak Ridge National Laboratory and the Idaho National Engineering Laboratory.

  12. Miscellaneous chemical basin expedited site characterization report

    International Nuclear Information System (INIS)

    Riha, B.D.; Pemberton, B.E.; Rossabi, J.

    1996-12-01

    A total of twenty nine cone penetrometer test (CPT) pushes in three weeks were conducted for vadose zone characterization of the Miscellaneous Chemical Basin (MCB) waste unit at the Savannah River Site. The shallow, unlined basin received liquid chemical wastes over an 18 year period beginning in 1956. This characterization was initiated to determine the vertical and lateral extent of contamination in the vadose zone and to install vadose zone wells for remediation by barometric pumping or active vapor extraction to help prevent further contamination of groundwater. The CPT locations within the waste site were selected based on results from previous shallow soil gas surveys, groundwater contamination data, and the suspected basin center. Geophysical data and soil gas samples were collected at twenty five locations and twenty five vadose zone wells were installed. The wells were screened to target the clay zones and areas of higher soil gas concentrations. The well construction diagrams are provided in Appendix B. Baro-Ball trademark valves for enhanced barometric pumping were installed on each well upon completion to immediately begin the remediation treatability study at the site

  13. A teleoperated system for remote site characterization

    International Nuclear Information System (INIS)

    Sandness, G.A.; Richardson, B.S.; Pence, J.

    1993-08-01

    The detection and characterization of buried objects and materials is an important first step in the restoration of burial sites containing chemical and radioactive waste materials at Department of Energy (DOE) and Department of Defense (DOD) facilities. To address the need to minimize the exposure of on-site personnel to the hazards associated with such sites, the DOE Office of Technology Development and the US Army Environmental Center have jointly supported the development of the Remote Characterization System (RCS). One of the main components of the RCS is a small remotely driven survey vehicle that can transport various combinations of geophysical and radiological sensors. Currently implemented sensors include ground-penetrating radar, magnetometers, an electromagnetic induction sensor, and a sodium iodide radiation detector. The survey vehicle was constructed predominantly of non-metallic materials to minimize its effect on the operation of its geophysical sensors. The system operator controls the vehicle from a remote, truck-mounted, base station. Video images are transmitted to the base station by an radio link to give the operator necessary visual information. Vehicle control commands, tracking information, and sensor data are transmitted between the survey vehicle and the base station by means of a radio ethernet link. Precise vehicle tracking coordinates are provided by a differential Global Positioning System (GPS). The sensors are environmentally protected, internally cooled, and interchangeable based on mission requirements. To date, the RCS has been successfully tested at the Oak Ridge National Laboratory and the Idaho National Engineering Laboratory

  14. Characterization of active sites in zeolite catalysts

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-11-01

    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.

  15. Restructured site characterization program at Yucca Mountain

    International Nuclear Information System (INIS)

    Dyer, J.R.; Vawter, R.G.

    1995-01-01

    During 1994 and the early part of 1995, the US Department of Energy's Yucca Mountain Site Characterization Office (YMSCO) and its parent organization, the Office of Civilian Radioactive Waste Management (OCRWM) underwent a significant restructuring. Senior Department officials provided the leadership to reorient the management, technical, programmatic, and public interaction approach to the US High Level Radioactive Waste Disposal Program. The restructuring involved reorganizing the federal staff, conducting meaningful strategic planning, improving the management system, rationalizing contractor responsibilities, focusing upon major products, and increasing stakeholder involvement. The restructured program has prioritized technical and scientific activities toward meeting major regulatory milestones in a timely and cost-effective manner. This approach has raised concern among elements of technical, scientific, and oversight bodies that suitability and licensing decisions could be made without obtaining sufficient technical information for this first-of-its-kind endeavor. Other organizations, such as congressional committees, industrial groups, and rate payers believe characterization goals can be met in a timely manner and within the limitation of available funds. To balance these contrasting views in its decision making process, OCRWM management has made a special effort to communicate its strategy to oversight bodies, the scientific community and other stakeholders and to use external independent peer review as a key means of demonstrating scientific credibility. Site characterization of Yucca Mountain in Nevada is one of the key elements of the restructured program

  16. LANL environmental restoration site ranking system: System description. Final report

    International Nuclear Information System (INIS)

    Merkhofer, L.; Kann, A.; Voth, M.

    1992-01-01

    The basic structure of the LANL Environmental Restoration (ER) Site Ranking System and its use are described in this document. A related document, Instructions for Generating Inputs for the LANL ER Site Ranking System, contains detailed descriptions of the methods by which necessary inputs for the system will be generated. LANL has long recognized the need to provide a consistent basis for comparing the risks and other adverse consequences associated with the various waste problems at the Lab. The LANL ER Site Ranking System is being developed to help address this need. The specific purpose of the system is to help improve, defend, and explain prioritization decisions at the Potential Release Site (PRS) and Operable Unit (OU) level. The precise relationship of the Site Ranking System to the planning and overall budget processes is yet to be determined, as the system is still evolving. Generally speaking, the Site Ranking System will be used as a decision aid. That is, the system will be used to aid in the planning and budgetary decision-making process. It will never be used alone to make decisions. Like all models, the system can provide only a partial and approximate accounting of the factors important to budget and planning decisions. Decision makers at LANL will have to consider factors outside of the formal system when making final choices. Some of these other factors are regulatory requirements, DOE policy, and public concern. The main value of the site ranking system, therefore, is not the precise numbers it generates, but rather the general insights it provides

  17. LANL environmental restoration site ranking system: System description. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Merkhofer, L.; Kann, A.; Voth, M. [Applied Decision Analysis, Inc., Menlo Park, CA (United States)

    1992-10-13

    The basic structure of the LANL Environmental Restoration (ER) Site Ranking System and its use are described in this document. A related document, Instructions for Generating Inputs for the LANL ER Site Ranking System, contains detailed descriptions of the methods by which necessary inputs for the system will be generated. LANL has long recognized the need to provide a consistent basis for comparing the risks and other adverse consequences associated with the various waste problems at the Lab. The LANL ER Site Ranking System is being developed to help address this need. The specific purpose of the system is to help improve, defend, and explain prioritization decisions at the Potential Release Site (PRS) and Operable Unit (OU) level. The precise relationship of the Site Ranking System to the planning and overall budget processes is yet to be determined, as the system is still evolving. Generally speaking, the Site Ranking System will be used as a decision aid. That is, the system will be used to aid in the planning and budgetary decision-making process. It will never be used alone to make decisions. Like all models, the system can provide only a partial and approximate accounting of the factors important to budget and planning decisions. Decision makers at LANL will have to consider factors outside of the formal system when making final choices. Some of these other factors are regulatory requirements, DOE policy, and public concern. The main value of the site ranking system, therefore, is not the precise numbers it generates, but rather the general insights it provides.

  18. Hydrologic site characterization - the UMTRA project approach

    International Nuclear Information System (INIS)

    Binkman, J.E.; Hoopes, J.R.

    1985-01-01

    The United States Environmental Protection Agency (EPA) Standards (40 CFR 192) require site characterization of the hydrogeologic regime at and around each Uranium Mill Tailings Remedial Action (UMTRA) Project site. Also, ''judgements on the possible need for remedial or protective actions for groundwater aquifers should be guided by relevant considerations described in EPA's hazardous waste management system (47 CFR 32274).'' To address those two sets of rules and regulations, a generic approach is being developed. Fourteen primary issues were determined. These issues can be grouped into those that can be determined by documentation of available information and present conditions, those that require extensive field investigations and those that require some form of predictive modeling. To address the various issues requires an integrated effort of hydrogeologists, environmental engineers or scientists and health physicists. In this paper, the approach to the resolution of these fourteen issues is described briefly

  19. Physical sampling for site and waste characterization

    International Nuclear Information System (INIS)

    Bonnough, T.L.

    1994-01-01

    Physical sampling plays a basic role in site and waste characterization program effort. The term ''physical sampling'' used here means collecting tangible, physical samples of soil, water, air, waste streams, or other materials. The industry defines the term ''physical sampling'' broadly to include measurements of physical conditions such as temperature, wind conditions, and pH which are also often taken in a sample collection effort. Most environmental compliance actions are supported by the results of taking, recording, and analyzing physical samples and the measuring of physical conditions taken in association with sample collecting

  20. Measurement program to characterize the wind at a potential WECS site

    Energy Technology Data Exchange (ETDEWEB)

    Verholek, M.G.

    1978-03-01

    An onsite meteorological measurement program to characterize the wind at a potential wind turbine installation site is described. The basic informational requirements have been postulated, the analysis described, and an appropriate measurement program has been devised. This phase of siting measurements provides the information for the final installation decision process--which WECS to put at which site.

  1. Industrial Sites Project Establishment of Final Action Levels

    International Nuclear Information System (INIS)

    Boehlecke, Robert F.

    2006-01-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) oversees numerous sites on the Nevada Test Site (NTS) and other locations in the State of Nevada that have been impacted by activities related to the development and testing of nuclear devices and by other activities. NNSA/NSO is responsible for protecting members of the public, including site workers, from harmful exposure to both chemical and radiological contaminants at these sites as they remediate these sites. The Nevada Division of Environmental Protection (NDEP) is the primary state agency responsible for protection of human health and the environment with respect to chemical and radiological wastes. In 1996 the DOE, U.S. Department of Defense, and the State of Nevada entered into an agreement known as the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996). Appendix VI to the FFACO describes the strategy employed to plan, implement, and complete environmental corrective action activities at NTS and other locations in the state of Nevada. One of the categories of corrective action units (CAUs) is Industrial Sites, which consists of approximately 1,150 locations that may require some level of investigation and corrective action. To evaluate the need for the extent of corrective action at a particular site, NNSA/NSO assesses the potential impacts to receptors by comparing measurements of contaminant concentrations to risk-based (chemical) and dose-based (radionuclide) standards (action levels). Preliminary action levels (PALs) are established as part of the data quality objective (DQO) process, and are presented in one or more FFACO documents generated as part of the corrective action process. This document formally defines and clarifies the NDEP-approved process NNSA/NSO Industrial Sites Project uses to fulfill the requirements of the FFACO and state regulations. This process establishes final action levels (FALs) based on the risk

  2. Seismic site characterization for nuclear structures and power plants

    International Nuclear Information System (INIS)

    Boominathan, A.

    2004-01-01

    Seismic site characterization is carried out for the construction of nuclear structures and power plants in earthquake-prone areas to establish the occurrence of severe seismic hazards such as tectonic rupture, surface faulting, large scale liquefaction, sliding and seismic settlement which may alter the overall stability of the site. Seismic characterization is required to finalize the design earthquake parameters including choosing input seismic data. As a part of the investigation, measurements of relevant dynamic parameters both in laboratory and in situ have been made for carrying out dynamic soil structure interaction analysis, for determination of dynamic deformation, seismic settlement and dynamic response spectrum of the site, and for calculating dynamic earth pressure acting on retaining structures. We discuss here the seismic investigation components and methods, measurement of P- and S- wave velocities in the field and estimation of important dynamic parameters such as maximum shear modulus, modulus reduction curve, damping ratio, seismic site classification, predominant site period, liquefaction analysis through case studies for nuclear structures at Kalpakkam and Kudankulam and power plant structures at New Delhi and Konaseema. (author)

  3. Tools for characterizing biomembranes : final LDRD report.

    Energy Technology Data Exchange (ETDEWEB)

    Alam, Todd Michael; Stevens, Mark; Holland, Gregory P.; McIntyre, Sarah K.

    2007-10-01

    A suite of experimental nuclear magnetic resonance (NMR) spectroscopy tools were developed to investigate lipid structure and dynamics in model membrane systems. By utilizing both multinuclear and multidimensional NMR experiments a range of different intra- and inter-molecular contacts were probed within the membranes. Examples on pure single component lipid membranes and on the canonical raft forming mixture of DOPC/SM/Chol are presented. A unique gel phase pretransition in SM was also identified and characterized using these NMR techniques. In addition molecular dynamics into the hydrogen bonding network unique to sphingomyelin containing membranes were evaluated as a function of temperature, and are discussed.

  4. New site characterization and monitoring technology

    Science.gov (United States)

    Nielsen, Bruce J.; Gillispie, Gregory D.; Bohne, David A.; Lindstrom, David R.

    1995-10-01

    The cost of characterizing and monitoring U.S. government hazardous waste sites could exceed $500 billion utilizing traditional methods and technology. New sensor technologies are being developed to meet the nation's environmental remediation and compliance programs. In 1993, the U.S. Air Force Armstrong Laboratory and Loral Defense System, Eagan (formerly a division of Unisys Corporation) signed a Cooperative Research and Development Agreement (CRDA) to commercialize fiber optic laser-induced fluorescence technology that had been developed with U.S. Air Force funding a North Dakota State University (NDSU). A consortium consisting of the CRDA partners (USAF and Loral), Dakota Technologies Inc., and NDSU submitted a proposal to the advanced Research Projects Agency, Technology Reinvestment Project and won an award to fund the commercialization. The result, the Rapid Optical Screening Tool or ROST is a state-of-the-art laser spectroscopy system for analysis of aromatic hydrocarbon-contaminated soil and groundwater. With ROST, environmental investigators are able to find, classify, and map the distribution of many hazardous chemicals in the field instead of waiting for reports to come back from the analytical laboratory. The research and development program leading to prototype laser spectrometers is summarized along with results from laboratory and field demonstrations illustrating system performance and benefits for site characterization. The technology has recently been demonstrated in Europe in Germany, the Netherlands, France an several sites in the United Kingdom having light, medium, and heavy aromatic hydrocarbon contamination from fuel spills and refinery or chemical plant operations. The use of the ROST system to find hydrocarbon contamination is now being offered as a service by Loral Corporation.

  5. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  6. Technical data management at the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Statler, J.; Newbury, C.M.; Heitland, G.W.

    1992-01-01

    The Department of Energy/Office of Civilian Radioactive waste Management (DOE/OCRWM) is responsible for the characterization of Yucca Mountain, Nevada, to determine its potential as a site of a high-level radioactive waste repository. The characterization of Yucca Mountain encompasses many diverse investigations, both onsite and in laboratories across the country. Investigations are being conducted of the geology, hydrology, mineralogy, paleoclimate, geotechnical properties, and archeology of the area, to name a few. Effective program management requires that data from site investigations be processed, interpreted and disseminated in a timely manner to support model development and validation, repository design, and performance assessment. The Program must also meet regulatory requirements for making the technical data accessible to a variety of external users throughout the life of the Project. Finally, the DOE/OCRWM must make available the data or its description and access location available for use in support of the license application and supporting documentation. To accomplish these objectives, scientific and engineering data, generated by site characterization activities, and technical data, generated by environmental and socioeconomic impact assessment activities, must be systematically identified, cataloged, stored and disseminated in a controlled manner

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

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

    International Nuclear Information System (INIS)

    1988-01-01

    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

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

    International Nuclear Information System (INIS)

    1988-01-01

    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

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  15. Radiological characterization and challenges at decommissioning sites

    International Nuclear Information System (INIS)

    Moore, Scott

    2002-01-01

    -1700 provides the review methodology that NRC staff follows when reviewing License Termination Plans submitted by decommissioning reactors. NRC has developed and implemented a dose-based cleanup standard. In addition, a comprehensive suite of guidance documents has been developed, enabling application of the new regulations to the characterization and cleanup of radioactively contaminated sites. As NRC and its licensees gain experience, we look forward to applying these new performance-based standards and implementing methodologies to their fullest potential in current and yet to be discovered decommissioning challenges

  16. A new site characterization and monitoring technology

    International Nuclear Information System (INIS)

    Nielsen, B.J.; Bohne, D.A.; Lindstrom, D.R.

    1995-01-01

    New sensor technologies are being developed to meet the nation's environmental remediation and compliance programs. In 1993, the US Air Force Armstrong Laboratory and Loral Defense System, Eagan (formerly a division of Unisys Corporation) signed a Cooperative Research and Development Agreement (CRDA) to commercialize fiber optic laser-induced fluorescence technology that had been developed with US Air Force funding at North Dakota State University (NDSU). A consortium consisting of the CRDA partners (USAF and Loral), Dakota Technologies, Inc., and NDSU submitted a proposal to the Advanced Research Projects Agency, Technology Reinvestment Project and won an award to fund the commercialization. The result, the Rapid Optical Screening Tool or ROST is a state-of-the-art laser spectroscopy system for analysis of aromatic hydrocarbon-contaminated soil and groundwater. With ROST, environmental investigators are able to find, classify, and map the distribution of many hazardous chemicals in the field instead of waiting for reports to come back from analytical laboratory. The research and development program leading to prototype laser spectrometers is summarized along with results from laboratory and field demonstrations illustrating system performance and benefits for site characterization. The technology has recently been demonstrated in Europe in Germany, the Netherlands, France and several sites in the United Kingdom having light, medium, and heavy aromatic hydrocarbon contamination from fuel spills and refinery or chemical plant operations

  17. Final covering of the Ronneburg uranium mining site

    International Nuclear Information System (INIS)

    Hoepfner, Uwe

    2007-01-01

    The rehabilitation of WISMUT's former Ronneburg uranium mining site involves backfilling of waste rock to the Lichtenberg open pit. The relocation project comprises about 110 million m 3 of sulphide-bearing and AMD-generating waste rock which makes it the most important and most cost-intensive single surface restoration project conducted by WISMUT at the Ronneburg site. The backfilled waste rock has to be covered on an area of about 220 ha to control water infiltration and gas diffusion. Design planning for the final cover placement which began in 2004 had to be based on a comprehensive cost-benefit analysis as well on field tests of alternative cover options which are in compliance with legal requirements. An intensive testing program concerning the vadose zone of soil covers has therefore been started in 2000. The paper presents an overview of the monitoring program and the results of the vadose zone measurements. The water of soil covers have to be predicted for extended evaluation periods. Therefore water balance simulations of single layer covers (storage and evaporation concept) taking current and future soil and climate conditions into account are performed with the HYDRUS 2D code. (author)

  18. Characterization of new sites for news NPPs: Cooling Systems

    International Nuclear Information System (INIS)

    Copete, M.; Ortega, S.; Vaquero, J. C.; Cervantes, E.

    2010-01-01

    The increase of power consumption because of the lifestyle of the current society has implied the called renaissance of nuclear power. This situation has encouraged utilities to make new investments in studies, analyses and assessments of future new nuclear power plants. As part of these studies, the characterization or process of conveying information about new sites for new nuclear power plants is strongly considered nowadays. This one encompasses diverse analyses (geology, seismology, weather conditions, flooding, population, and so on) being one of the most important, the study about cooling system requirements. This study is based on diverse tasks: studies about the existing technologies of cooling (wet towers, hybrid towers), development of a thermal model for each component involved in the cooling process, availability of site conditions data and, to perform finally operating windows.

  19. Site characterization plan: Public Handbook, Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    1989-01-01

    The Yucca Mountain site in Nevada has been designated by the Nuclear Waste Policy Act of 1982, as amended, for detailed study as the candidate site for the first US geologic repository for spent nuclear fuel and high-level radioactive waste. The detailed study --- called ''site characterization'' --- will be conducted by the Department of Energy (DOE) to determine the suitability of the site for a repository and, if the site is suitable, to obtain from the Nuclear Regulatory Commission authorization to construct the repository. As part of the site characterization study, DOE has prepared a Site Characterization Plan (SCP) for the Yucca Mountain site. The Site Characterization Plan is a nine-volume document, approximately 6300 pages in length, which describes the activities that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. Part 1 of this Handbook explains what site characterization is and how the Site Characterization Plan (Plan) relates to it. Part 2 tells how to locate subjects covered in the Plan. Another major purpose of this Handbook is to identify opportunities for public involement in the review of the Site Characterization Plan. DOE wants to be sure that the public has adequate opportunities to learn about the Plan and review the results of the subsequent technical studies. 14 refs

  20. Site characterization report for the basalt waste isolation project. Volume III

    International Nuclear Information System (INIS)

    1982-11-01

    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 3 contains chapters 13 through 19: site issues and plans; geoengineering and repository design issues and plans; waste package and site geochemistry issues and plans; performance-assessment issues and plans; site characterization program; quality assurance; and identification of alternate sites

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

    International Nuclear Information System (INIS)

    1989-08-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-08-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-06-01

    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.

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

    International Nuclear Information System (INIS)

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

    2006-01-01

    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

  5. Site characterization of the West Chestnut Ridge site

    International Nuclear Information System (INIS)

    Ketelle, R.H.; Huff, D.D.

    1984-09-01

    This report summarizes the results of investigations performed to date on the West Chestnut Ridge Site, on the Department of Energy (DOE) Oak Ridge Reservation. The investigations performed include geomorphic observations, areal geologic mapping, surficial soil mapping, subsurface investigations, soil geochemical and mineralogical analyses, geohydrologic testing, groundwater fluctuation monitoring, and surface water discharge and precipitation monitoring. 33 references, 32 figures, 24 tables

  6. Site characterization of the West Chestnut Ridge site

    Energy Technology Data Exchange (ETDEWEB)

    Ketelle, R H; Huff, D D

    1984-09-01

    This report summarizes the results of investigations performed to date on the West Chestnut Ridge Site, on the Department of Energy (DOE) Oak Ridge Reservation. The investigations performed include geomorphic observations, areal geologic mapping, surficial soil mapping, subsurface investigations, soil geochemical and mineralogical analyses, geohydrologic testing, groundwater fluctuation monitoring, and surface water discharge and precipitation monitoring. 33 references, 32 figures, 24 tables.

  7. Final work plan : environmental site investigation at Sylvan Grove, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2012-07-15

    what future CCC/USDA actions may be necessary, with the ultimate goal of achieving classification of the Sylvan Grove site at no further action status. The proposed activities are to be performed on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory, a nonprofit, multidisciplinary research center operated by the UChicago Argonne, LLC, for the U.S. Department of Energy. Argonne provides technical assistance to the CCC/USDA concerning environmental site characterization and remediation at former grain storage facilities. Argonne issued a Master Work Plan (Argonne 2002) that has been approved by the KDHE. The Master Work Plan describes the general scope of all investigations at former CCC/USDA facilities in Kansas and provides guidance for these investigations. That document should be consulted for the complete details of plans for work associated with the former CCC/USDA facility at Sylvan Grove.

  8. Site characterization for hybrid system construction

    Energy Technology Data Exchange (ETDEWEB)

    Saldana, R.; Miranda, U.; Medrano, M. C. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1997-12-31

    The basic reason to use alternative systems for electricity generation, in most cases, is the lack of electricity services, such as isolated rural communities which are located far away from the electric distribution line, and the cost of its extension is too expensive, while decentralized power systems can be an economic and appropriate solution to providing these services. Up to now there are several technological options for rural electrification using PV modules, wind plants, water-power plants, anaerobic digesters, or a combination of some of them, according to the availability of energetic resources. The applications include centralized or decentralized systems, autonomous or hybrid systems, isolated or interconnected to the electric line, etc. A particular hybrid system design can be done considering two general aspects, first it is necessary to know the electric consumption that will be supplied, taking into account present and future necessities and how local energetic resources are present in a selected site. Finally, also it is necessary to carry out an economic analysis to determine the cost of kilowatt-hour generated using local energetic resources and compare it with the cost of electricity produced by conventional power systems. [Espanol] La razon principal para el uso de sistemas alternativos de generacion de electricidad, en la mayoria de los casos, es la falta de servicios de electricidad, tal como en las comunidades rurales aisladas localizadas lejos de linea de distribucion electrica, donde el costo de su extension es demasiado caro, mientras que los sistemas descentralizados de energia pueden ser una solucion economica y adecuada para proporcionar estos servicios. Hasta ahora existen varias opciones tecnologicas para la electrificacion rural usando modulos fotovoltaicos, aerogeneradores, plantas hidroelectricas, digestores anaerobicos o una combinacion de algunos de ellos, de acuerdo con la disponibilidad de los recursos energeticos. Las

  9. Evaluation of a committed fusion site. Final report

    International Nuclear Information System (INIS)

    1979-07-01

    This report is divided into five technical sections. Section 2 is a summary. In Section 3, which covers device and site analyses the major characteristics of devices that might be placed at the site, as envisioned by major fusion laboratories, are described; the characteristics of a site (baseline site) which would accommodate these devices are defined; and various approaches to a committed site meeting the baseline site requirements are discussed. Section 4 describes the scenarios selected to represent possible site development outcomes; these scenarios are evaluated with respect to comparative cost and schedule effects. Section 5 presents a brief evaluation of the effects fusion-fission hybrids might have on the committed site. Major conclusions and recommendations are discussed in Section 6

  10. Atmospheric Line of Site Experiment (ALOSE) Final Campaign Summary

    Energy Technology Data Exchange (ETDEWEB)

    Smith, W. [Atmospheric Radiation Measurement (ARM) Climate Research Facility, Washington, DC (United States); Green, S. [Atmospheric Radiation Measurement (ARM) Climate Research Facility, Washington, DC (United States); Howard, M. [Atmospheric Radiation Measurement (ARM) Climate Research Facility, Washington, DC (United States); Yesalusky, M. [Atmospheric Radiation Measurement (ARM) Climate Research Facility, Washington, DC (United States); Modlin, N. [Atmospheric Radiation Measurement (ARM) Climate Research Facility, Washington, DC (United States)

    2016-03-01

    The Atmospheric Line of Site Experiment (ALOSE) was a project to produce best-estimate atmospheric state measurements at the: 1. DOE Atmospheric Radiation Measurement (ARM) Clouds and Radiation Test-bed (CART) site located in Lamont, Oklahoma (11–14 December 2012) 2. Poker Flat Alaska Research Range (PFRR) located in Poker Flat, Alaska (19–26 February 2013) 3. DOE ARM CART site located in Lamont, Oklahoma (24–28 April 2013) 4. DOE ARM CART site located in Lamont, Oklahoma (9–15 July 2013) 5. DOE ARM Tropical Western Pacific (TWP) site located in Darwin, Australia (27 September–3 October 2013).

  11. 10 CFR 60.16 - Site characterization plan required.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Site characterization plan required. 60.16 Section 60.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Licenses Preapplication Review § 60.16 Site characterization plan required. Before proceeding to...

  12. Site characterization activities at Stripa and other Swedish projects

    International Nuclear Information System (INIS)

    Ahlstroehm, P.E.

    1991-01-01

    The Swedish research programme concerning spent nuclear fuel disposal aims for submitting a siting license application around the year 2000. An important step towards that goal will be the detailed characterization of at least two potential sites in late 1990s. In preparation for such characterization several research projects are conducted. One is the international Stripa Project that includes a site characterization and validation project for a small size granite rock body. The Stripa work also includes further development of instrumentation and measurement techniques. Another project is the Finnsjoen Fracture Zone Project, which is characterizing a subhorizontal zone at depths from 100 to 350 meters. The third project is the new Swedish Hard Rock Laboratory planned at the site of the Oskarshamn nuclear power plant. The preinvestigations and construction of this laboratory include major efforts in development, application and validation of site characterization methodology. (author) 6 figs., 9 refs

  13. Developing Hydrogeological Site Characterization Strategies based on Human Health Risk

    Science.gov (United States)

    de Barros, F.; Rubin, Y.; Maxwell, R. M.

    2013-12-01

    In order to provide better sustainable groundwater quality management and minimize the impact of contamination in humans, improved understanding and quantification of the interaction between hydrogeological models, geological site information and human health are needed. Considering the joint influence of these components in the overall human health risk assessment and the corresponding sources of uncertainty aid decision makers to better allocate resources in data acquisition campaigns. This is important to (1) achieve remediation goals in a cost-effective manner, (2) protect human health and (3) keep water supplies clean in order to keep with quality standards. Such task is challenging since a full characterization of the subsurface is unfeasible due to financial and technological constraints. In addition, human exposure and physiological response to contamination are subject to uncertainty and variability. Normally, sampling strategies are developed with the goal of reducing uncertainty, but less often they are developed in the context of their impacts on the overall system uncertainty. Therefore, quantifying the impact from each of these components (hydrogeological, behavioral and physiological) in final human health risk prediction can provide guidance for decision makers to best allocate resources towards minimal prediction uncertainty. In this presentation, a multi-component human health risk-based framework is presented which allows decision makers to set priorities through an information entropy-based visualization tool. Results highlight the role of characteristic length-scales characterizing flow and transport in determining data needs within an integrated hydrogeological-health framework. Conditions where uncertainty reduction in human health risk predictions may benefit from better understanding of the health component, as opposed to a more detailed hydrogeological characterization, are also discussed. Finally, results illustrate how different dose

  14. Application of in situ measurement for site remediation and final status survey of decommissioning KRR site

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sang Bum; Nam, Jong Soo; Choi, Yong Suk; Seo, Bum Kyoung; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-06-15

    In situ gamma spectrometry has been used to measure environmental radiation, assumptions are usually made about the depth distribution of the radionuclides of interest in the soil. The main limitation of in situ gamma spectrometry lies in determining the depth distribution of radionuclides. The objective of this study is to develop a method for subsurface characterization by in situ measurement. The peak to valley method based on the ratio of counting rate between the photoelectric peak and Compton region was applied to identify the depth distribution. The peak to valley method could be applied to establish the relation between the spectrally derived coefficients (Q) with relaxation mass per unit area (β) for various depth distribution in soil. The in situ measurement results were verified by MCNP simulation and calculated correlation equation. In order to compare the depth distributions and contamination levels in decommissioning KRR site, in situ measurement and sampling results were compared. The in situ measurement results and MCNP simulation results show a good correlation for laboratory measurement. The simulation relationship between Q and source burial for the source layers have exponential relationship for a variety depth distributions. We applied the peak to valley method to contaminated decommissioning KRR site to determine a depth distribution and initial activity without sampling. The observed results has a good correlation, relative error between in situ measurement with sampling result is around 7% for depth distribution and 4% for initial activity. In this study, the vertical activity distribution and initial activity of {sup 137}Cs could be identifying directly through in situ measurement. Therefore, the peak to valley method demonstrated good potential for assessment of the residual radioactivity for site remediation in decommissioning and contaminated site.

  15. Siting guidelines for utility application of wind turbines. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Pennell, W.T.

    1983-01-01

    Utility-oriented guidelines are described for identifying viable sites for wind turbines. Topics and procedures are also discussed that are important in carrying out a wind turbine siting program. These topics include: a description of the Department of Energy wind resource atlases; procedures for predicting wind turbine performance at potential sites; methods for analyzing wind turbine economics; procedures for estimating installation and maintenance costs; methods for anlayzing the distribution of wind resources over an area; and instrumentation for documenting wind behavior at potential sites. The procedure described is applicable to small and large utilities. Although the procedure was developed as a site-selection tool, it can also be used by a utility who wishes to estimate the potential for wind turbine penetration into its future generation mix.

  16. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

    International Nuclear Information System (INIS)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions

  17. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  18. Remedial action selection report Maybell, Colorado, site. Final report

    International Nuclear Information System (INIS)

    1996-12-01

    The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The site is 2.5 mi (4 km) northeast of the Yampa River on relatively flat terrain broken by low, flat-topped mesas. U.S. Highway 40 runs east-west 2 mi (3.2 km) south of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. The site is situated between Johnson Wash to the east and Rob Pit Mine to the west. Numerous reclaimed and unreclaimed mines are in the immediate vicinity. Aerial photographs (included at the end of this executive summary) show evidence of mining activity around the Maybell site. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [ml]) and contains 2.8 million cubic yards (yd 3 ) (2.1 million cubic meters [m 3 ]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd 3 (15,000 m 3 ) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd 3 (420,000 m 3 ). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd 3 (2.58 million m 3 )

  19. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static

  20. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static.

  1. How to Characterize a Potential Site for CO2 Storage with Sparse Data Coverage – a Danish Onshore Site Case

    Directory of Open Access Journals (Sweden)

    Nielsen Carsten Møller

    2015-04-01

    Full Text Available The paper demonstrates how a potential site for CO2 storage can be evaluated up to a sufficient level of characterization for compiling a storage permit application, even if the site is only sparsely explored. The focus of the paper is on a risk driven characterization procedure. In the initial state of a site characterization process with sparse data coverage, the regional geological and stratigraphic understanding of the area of interest can help strengthen a first model construction for predictive modeling. Static and dynamic modeling in combination with a comprehensive risk assessment can guide the different elements needed to be evaluated for fulfilling a permit application. Several essential parameters must be evaluated; the storage capacity for the site must be acceptable for the project life of the operation, the trap configuration must be efficient to secure long term containment, the injectivity must be sufficient to secure a longstanding stable operation and finally a satisfactory and operational measuring strategy must be designed. The characterization procedure is demonstrated for a deep onshore aquifer in the northern part of Denmark, the Vedsted site. The site is an anticlinal structural closure in an Upper Triassic – Lower Jurassic sandstone formation at 1 800-1 900 m depth.

  2. Ambient air monitoring to support HLW repository site characterization

    International Nuclear Information System (INIS)

    Fransioli, P.M.; Dixon, W.R.

    1993-01-01

    Site characterization at the Yucca Mountain site includes an ambient air quality and meteorological monitoring program to provide information for environmental and site characterization issues. The program is designed to provide data for four basic purposes: Atmospheric dispersion calculations to estimate impacts of possible airborne releases of radiological material; Engineering design and extreme weather event characterization; Local climate studies for environmental impact analyses and climate characterization; and, Air quality permits required for site characterization work. The program is compiling a database that will provide the basis for analyses and reporting related to the purposes of the program. Except for reporting particulate matter and limited meteorological data to the State of Nevada for an air quality permit condition, the data have yet to be formally analyzed and reported

  3. Seismic characterization of the NPP Krsko site

    International Nuclear Information System (INIS)

    Obreza, J.

    2000-01-01

    The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-11-01

    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.

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

    International Nuclear Information System (INIS)

    1982-11-01

    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

  6. Energy conserving site design case study: Shenandoah, Georgia. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    The case study examines the means by which energy conservation can be achieved at an aggregate community level by using proper planning and analytical techniques for a new town, Shenandoah, Georgia, located twenty-five miles southwest of Atlanta's Hartsfield International Airport. A potentially implementable energy conservation community plan is achieved by a study team examining the land use options, siting characteristics of each building type, alternate infrastructure plans, possible decentralized energy options, and central utility schemes to determine how community energy conservation can be achieved by use of pre-construction planning. The concept for the development of mixed land uses as a passively sited, energy conserving community is based on a plan (Level 1 Plan) that uses the natural site characteristics, maximizes on passive energy siting requirement, and allows flexibility for the changing needs of the developers. The Level 2 Plan is identical with Level 1 plan plus a series of decentraized systems that have been added to the residential units: the single-family detached, the apartments, and the townhouses. Level 3 Plan is similar to the Level 1 Plan except that higher density dwellings have been moved to areas adjacent to central site. The total energy savings for each plan relative to the conventional plan are indicated. (MCW)

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

    International Nuclear Information System (INIS)

    1988-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

    1992-01-01

    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.``

  10. Characterization of the Hanford Site and environs

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. (ed.)

    1991-03-01

    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.

  11. Characterizing the future site for PROSPECT

    Science.gov (United States)

    Hackett, Brennan; Huffron, Blaine; Romero, Elisa; Matta, James; Galindo-Uribarri, Alfredo

    2016-09-01

    The discovery of neutrino oscillations commenced exploration of a rich field of science at the intersection of nuclear, particle and astrophysics. This brought a number of interesting questions related to the neutrinos to the forefront of scientific literature. PROSPECT, the Precision Reactor Oscillation and Spectrum Experiment, aims to help answer some of those questions by precisely measuring the antineutrino flux and energy spectrum 7-9 meters from the highly enriched 235U reactor core at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR) with the goal to probe much of the best fit sterile neutrino parameter space. To better probe the sterile neutrino best fit region it is important to minimize the systematic uncertainties, requiring a detailed characterization of the background radiation field. Here we present DANG (the Detector Array to measure Neutron and Gamma radiation), an array deployed at HFIR to characterize spatial and time variations of the emitted background radiation. The array scans the entire proposed volume of the future PROSPECT location, providing a 3-d map of the background. Additionally, the array allows the study of the time evolution of HFIR correlated background to better understand how the reactor's prompt and activation radiation changes as function of the reactor cycle. Both a discussion of the construction and operation of the array will be given as well as a look at first results.

  12. Nevada Test Site tortoise population monitoring study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, J.M.; Zander, K.K.

    1994-12-01

    A Tortoise Population Monitoring Study was initiated to determine and monitor the density of desert tortoises (Gopherus agassizii) on the Nevada Test Site. Quadrat sampling was conducted following methodology described in the Draft Desert Tortoise Recovery Plan (FWS, 1993). So few tortoises were found that densities could not be calculated. Based on estimates of capture probabilities and densities from other studies, it was determined that 1-km{sup 2} (0.4 mi{sup 2}) plots did not contain enough tortoises for estimating densities with the Recovery Plan methods. It was recommended that additional surveys on the Nevada Test Site using those methods not be conducted. Any future efforts to monitor desert tortoise densities should start by identifying other possible methods, determining their relative power to detect changes, and estimating their cost.

  13. Active sites in char gasification: Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Wojtowicz, M.; Lilly, W.D.; Perkins, M.T.; Hradil, G.; Calo, J.M.; Suuberg, E.M.

    1987-09-01

    Among the key variables in the design of gasifiers and combustors is the reactivity of the chars which must be gasified or combusted. Significant loss of unburned char is unacceptable in virtually any process; the provision of sufficient residence time for complete conversion is essential. A very wide range of reactivities are observed, depending upon the nature of the char in a process. The current work focuses on furthering the understanding of gasification reactivities of chars. It has been well established that the reactivity of char to gasification generally depends upon three principal factors: (1) the concentration of ''active sites'' in the char; (2) mass transfer within the char; and (3) the type and concentration of catalytic impurities in the char. The present study primarily addresses the first factor. The subject of this research is the origin, nature, and fate of active sites in chars derived from parent hydrocarbons with coal-like structure. The nature and number of the active sites and their reactivity towards oxygen are examined in ''model'' chars derived from phenol-formaldehyde type resins. How the active sites are lost by the process of thermal annealing during heat treatment of chars are studied, and actual rate for the annealing process is derived. Since intrinsic char reactivities are of primary interest in the present study, a fair amount of attention was given to the model char synthesis and handling so that the effect of catalytic impurities and oxygen-containing functional groups in the chemical structure of the material were minimized, if not completely eliminated. The project would not be considered complete without comparing characteristic features of synthetic chars with kinetic behavior exhibited by natural chars, including coal chars.

  14. Yucca Mountain Site characterization project bibliography, January--June 1991

    International Nuclear Information System (INIS)

    1992-06-01

    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 Science and Technology Database from January 1, 1990, through December 31, 1991

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

    Energy Technology Data Exchange (ETDEWEB)

    Shade, J.W.

    1997-09-01

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

  16. Site Characterization and Monitoring Technical Support Center FY16 Report

    Science.gov (United States)

    SCMTSC’s primary goal is to provide technical assistance to regional programs on complex hazardous waste site characterization issues. This annual report illustrates the range and extent of projects that SCMTSC supported in FY 2016. Our principal audiences are site project manage...

  17. Characterization of the Abydos landing site of Philae on comet 67P/Churyumov-Gerasimenko

    Science.gov (United States)

    Lamy, P.; Faury, G.; Jorda, L.; Romeuf, D.; Capanna, C.; El-Maarry, M. R.; Gaskell, R.; Groussin, O.; Nebouy, D.

    2017-09-01

    Characterization of the final Abydos landing site of Philae on the nucleus of comet 67P/Churyumov-Gerasimenko based on twelve campaigns of imaging with the OSIRIS-NAC camera. The characterization is based on anaglyphs, a digital terrain model at a spatial scale of 40 cm and color maps. We present the regional setting of Abydos and define geological units. Abydos is essentially an alcove at the foot of a scarp composed of heavily fractured consolidated materials.

  18. Avian radioecology on a nuclear power station site. Final report

    International Nuclear Information System (INIS)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of 131 I and 137 Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods

  19. Final Reclamation Report: Basalt Waste Isolation Project exploratory shaft site

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, C.A.; Rickard, W.H. Jr.

    1990-06-01

    The restoration of areas disturbed by activities of the Basalt Waste Isolation Project (BWIP) constitutes a unique operation at the US Department of Energy's (DOE) Hanford Site, both from the standpoint of restoration objectives and the time frame for accomplishing these objectives. The BWIP reclamation program comprises three separate projects: borehole reclamation, Near Surface Test Facility (NSTF) reclamation, and Exploratory Shaft Facility (ESF) reclamation. The main focus of this report is on determining the success of the revegetation effort 1 year after work was completed. This report also provides a brief overview of the ESF reclamation program. 21 refs., 7 figs., 14 tabs.

  20. Avian radioecology on a nuclear power station site. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of /sup 131/I and /sup 137/Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods.

  1. Protecting subcontractor personnel during hazardous waste site characterization

    International Nuclear Information System (INIS)

    Lankford, B.R.

    1987-01-01

    This paper covers Industrial Hygiene involvement in the Site Characterization Program, focusing on the field oversight responsibilities. It discusses the different types and levels of protective equipment, gives an example of the type of situation that can arise from field characterization efforts, and gives a brief summary of health protection program elements. 3 figs., 3 tabs

  2. Protecting subcontractor personnel during hazardous waste site characterization

    Energy Technology Data Exchange (ETDEWEB)

    Lankford, B.R.

    1987-01-01

    This paper covers Industrial Hygiene involvement in the Site Characterization Program, focusing on the field oversight responsibilities. It discusses the different types and levels of protective equipment, gives an example of the type of situation that can arise from field characterization efforts, and gives a brief summary of health protection program elements. 3 figs., 3 tabs.

  3. Measurement techniques for radiological characterization of contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    Loos, M.

    1996-09-18

    Once the decision is taken to characterize a contaminated site, appropriate measurement techniques must be selected. The choice will depend on the available information, on the nature and extent of the contamination, as well as on available resources (staff and budget). Some techniques are described on the basis of examples of characterization projects (e.g. Olen area in Belgium).

  4. Reservoir characterization of Pennsylvanian sandstone reservoirs. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kelkar, M.

    1995-02-01

    This final report summarizes the progress during the three years of a project on Reservoir Characterization of Pennsylvanian Sandstone Reservoirs. The report is divided into three sections: (i) reservoir description; (ii) scale-up procedures; (iii) outcrop investigation. The first section describes the methods by which a reservoir can be described in three dimensions. The next step in reservoir description is to scale up reservoir properties for flow simulation. The second section addresses the issue of scale-up of reservoir properties once the spatial descriptions of properties are created. The last section describes the investigation of an outcrop.

  5. Adaptive sampling program support for expedited site characterization

    International Nuclear Information System (INIS)

    Johnson, R.

    1993-01-01

    Expedited site characterizations offer substantial savings in time and money when assessing hazardous waste sites. Key to some of these savings is the ability to adapt a sampling program to the ''real-time'' data generated by an expedited site characterization. This paper presents a two-prong approach to supporting adaptive sampling programs: a specialized object-oriented database/geographical information system for data fusion, management and display; and combined Bayesian/geostatistical methods for contamination extent estimation and sample location selection

  6. Final Site Closure Report for Site ST71, Elmendorf Air Force Base, Alaska

    National Research Council Canada - National Science Library

    1996-01-01

    ...., JP-4 jet fuel, diesel fuel, gasoline, or heating oil). Three-year-long bioventing pilot tests have recently been concluded at four fuel-contaminated Elmendorf AFB sites, including Site ST71 (Building 31-338...

  7. Savannah River Site Waste Management Final Environmental Impact Statement Addendum

    International Nuclear Information System (INIS)

    1995-07-01

    The purpose of this environmental impact statement is to help DOE decide how to manage over the next 30 years liquid high-level radioactive, low-level radioactive, mixed, hazardous, and transuranic wastes generated during 40 years of past operations and on-going activities (including management of wastes received from offsite) at Savannah River Site (SRS) in southwestern South Carolina. The wastes are currently stored at SRS. DOE seeks to dispose of the wastes in a cost-effective manner that protects human health and the environment. In this document, DOE assesses the cumulative environmental impacts of storing, treating, and disposing of the wastes, examines the impacts of alternatives, and identifies measures available to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socio-economic, and the health and safety of onsite workers and the public are included in the assessment

  8. Final report : site reclassification investigation for Courtland, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Dennis, C. B.; Environmental Science Division

    2006-01-31

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), formerly operated a grain storage facility in Courtland, Kansas. Prior to 1986, commercial grain fumigants containing carbon tetrachloride were commonly used by the CCC/USDA and the grain industry to preserve stored grain. In 1999, the Kansas Department of Health and Environment (KDHE) identified the former CCC/USDA operation as the likely source of carbon tetrachloride found in groundwater east of the former CCC/USDA facility in Courtland. Sampling by the KDHE in April 1998 had found carbon tetrachloride in the Garman residence lawn and garden well at a concentration of 2.1 {micro}g/L and in the Hoard residence lawn and garden well at a concentration of 0.5 {micro}g/L. Subsequent soil and groundwater sampling by the KDHE at the former CCC/USDA facility found no indication of a continuing source, and subsequent sampling of the affected wells showed generally declining contaminant levels. At the request of the KDHE and the CCC/USDA, Argonne National Laboratory prepared a Work Plan for Groundwater Sampling for Potential Site Reclassification, Courtland, Kansas (Argonne 2004). The objective of the proposed work was to conduct a single groundwater monitoring event and collect information necessary to update the status of the previously detected groundwater contamination, in support of an evaluation of appropriate actions for reclassification of the status of this site from active to resolved, under the Intergovernmental Agreement between the KDHE and the USDA's Farm Service Agency (FSA). The reclassification would be in accordance with the KDHE's Reclassification Plan (Policy No. BERRS-024, online at http://www.kdhe.state.ks.us/pdf/ber/scp/reclass.pdf). The KDHE approved the Work Plan on August 8, 2005. Sampling was conducted on September 7, 2005.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-03-01

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

  10. Characterization recommendations for waste sites at the Savannah River Plant

    International Nuclear Information System (INIS)

    Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

    1987-11-01

    One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil

  11. Characterization recommendations for waste sites at the Savannah River Plant

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

    1987-11-01

    One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil.

  12. Designing chemical soil characterization programs for mixed waste sites

    International Nuclear Information System (INIS)

    Meyers, K.A. Jr.

    1989-01-01

    The Weldon Spring Site Remedial Action Project is a remedial action effort funded by the U.S. Department of Energy. The Weldon Spring Site, a former uranium processing facility, is located in east-central Missouri on a portion of a former ordnance works facility which produced trinitrotoluene during World War II. As a result of both uranium and ordnance production, the soils have become both radiologically and chemically contaminated. As a part of site characterization efforts in support of the environmental documentation process, a chemical soil characterization program was developed. This program consisted of biased and unbiased sampling program which maximized areal coverage, provided a statistically sound data base and maintained cost effectiveness. This paper discusses how the general rationale and processes used at the Weldon Spring Site can be applied to other mixed and hazardous waste sites

  13. Environmental Regulatory Compliance Plan for site: Draft characterization of the Yucca Mountain site:Draft

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the EMMP is to document compliance with the NWPA. To do so, a summary description of site characterization activites is provided, based on the consultation draft of the SCP. Subsequent chpaters identify those technical areas having the potential to be impacted by site characterization activities and the monitoring plans proposed to identify whether those impacts acutally occur. Should monitoring confirm the potential for significant adverse impact, mitigative measures will be developed. In the context of site characterization, mitigation is defined as those changes in site characterization activities that serve to avoid or minimize, to the maximum extent practicle, any significant adverse environmental impacts. Although site characterization activies involve both surface and subsurface activities, it is the surface-based aspect of site characterization that is addressed in detailed by the EMMP. The schedule and duration of these activities is given in the consultation draft of the SCP. A breif summary of all proposed activities is given in the EMMP. 10 refs., 8 figs

  14. Hydrogen production from small hyropower sites. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    A synergistic relationship was not found to exist between low-head hydropower and electrolytic hydrogen production. The storageability of hydrogen was expected to mitigate problems of hydrogen generation variability associated with the use of low-head hydropower as the power source. The expense of gaseous hydrogen storage equipment effectively eliminates storage as a means to decouple hydrogen demand and power/hydrogen production. From the opposite perspective, the availability of a low and stable cost of power from low-head hydro was expected to improve the competitiveness of electrolysis. In actuality, the results indicated that hydroelectric power from small dams would be comparatively expensive by current grid power standards (mid-1979). Electrolysis, in the capacity range considered here, is less sensitive to the cost of the power than originally presumed. Other costs including depreciation and capital related charges are more significant. Due to power generation variability, sole reliance on low-head hydropower to provide electricity to the cells would reduce the utilization of the hydrogen production investment, resulting in an increase in unit production costs. These factors were paramount in the Air Products recommendation to discontinue the study before continuing to more detailed stages of analysis, including an analysis of a site specific facility and the construction of a demonstration facility. Another major factor was the unavailability of a pipeline hydrogen supply situation which, because of lower distribution and capital costs, could have been commercially viable. An unfavorable judgment on the combined facility should not be misinterpreted and extended to the component systems. Although a detailed analysis of the individual prospects for electrolysis and low-head hydropower was beyond the study scope, the reader will realize, as the study is reviewed, that each is worthy of individual consideration.

  15. Final Monitoring Plan for Site Closure at Inman, Kansas

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-01

    Inman, Kansas, is a rural town located in southwest McPherson County, in sections 8, 9, 16, and 17, Township 21 South, Range 4 West (Figure 1.1). There are 1,377 people in 513 households, as of the census of 2010. The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA), operated a grain storage facility at the southern edge of the city of Inman, Kansas, from 1954 to 1965. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In 1997, trace to low levels of carbon tetrachloride (below the maximum contamination level [MCL] of 5.0 μg/L) were detected in three private wells near the former grain storage facility at Inman, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. No public water supply wells were identified within 1 mi of the town by the KDHE in 1998. Carbon tetrachloride is the contaminant of primary concern at sites associated with grain storage operations. To determine whether the former CCC/USDA facility at Inman is a potential contaminant source and its possible relationship to the carbon tetrachloride contamination in groundwater, the CCC/USDA agreed to conduct a multi-phase investigation at Inman. The investigation was performed by the Environmental Science Division of Argonne National Laboratory in accordance with the Intergovernmental Agreement between the KDHE and the Farm Service Agency of the USDA.

  16. Remote experimental site concept development, LDRD final report

    International Nuclear Information System (INIS)

    Casper, T.A.; Meyer, W.; Butner, D.

    1995-01-01

    Scientific research is now often conducted on large and expensive experiments that utilize collaborative efforts on a national or international scale to explore physics and engineering issues. This is particularly true for the current US magnetic fusion energy program where collaboration on existing facilities has increased in importance and will form the basis for future efforts. As fusion energy research approaches reactor conditions, the trend is towards fewer large and expensive experimental facilities, leaving many major institutions without local experiments. Since the expertise of various groups is a valuable resource, it is important to integrate these teams into an overall scientific program. To sustain continued involvement in experiments, scientists are now often required to travel frequently, or to move their families, to the new large facilities. This problem is common to many other different fields of scientific research. The next-generation tokamaks, such as the Tokamak Physics Experiment (TPX) or the International Thermonuclear Experimental Reactor (ITER), will operate in steady-state or long pulse mode and produce fluxes of fusion reaction products sufficient to activate the surrounding structures. As a direct consequence, remote operation requiring robotics and video monitoring will become necessary, with only brief and limited access to the vessel area allowed. Even the on-site control room, data acquisition facilities, and work areas will be remotely located from the experiment, isolated by large biological barriers, and connected with fiber-optics. Current planning for the ITER experiment includes a network of control room facilities to be located in the countries of the four major international partners; USA, Russian Federation, Japan, and the European Community

  17. TOMOGRAPHIC SITE CHARACTERIZATION USING CPT, ERT, AND GPR

    Energy Technology Data Exchange (ETDEWEB)

    Rexford M. Morey; Susanne M. Conklin; Stephen P. Farrington, P.E.; James D. Shinn II, P.E.

    1999-07-01

    The US 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 for site characterization. Applied Research Associates, Inc. is developing two new sensor packages for site characterization and monitoring. The two new methods are: (1) Electrical Resistivity Tomography (ERT); and (2) Ground Penetrating Radar (GPR) Tomography. These sensor systems are now integrated with the 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 for both ERT and GPR borehole tomographic subsurface imaging. These two imaging techniques can be used for environmental site characterization and monitoring have numerous and diverse applications within site cleanup and waste management operations.

  18. Environmental waste site characterization utilizing aerial photographs and satellite imagery: Three sites in New Mexico, USA

    Energy Technology Data Exchange (ETDEWEB)

    Van Eeckhout, E.; Pope, P.; Becker, N.; Wells, B. [Los Alamos National Lab., NM (United States); Lewis, A.; David, N. [Environmental Research Inst. of Michigan, Santa Fe, NM (United States)

    1996-04-01

    The proper handling and characterization of past hazardous waste sites is becoming more and more important as world population extends into areas previously deemed undesirable. Historical photographs, past records, current aerial satellite imagery can play an important role in characterizing these sites. These data provide clear insight into defining problem areas which can be surface samples for further detail. Three such areas are discussed in this paper: (1) nuclear wastes buried in trenches at Los Alamos National Laboratory, (2) surface dumping at one site at Los Alamos National Laboratory, and (3) the historical development of a municipal landfill near Las Cruces, New Mexico.

  19. Final report : Hanover environmental site investigation, 2009-2010.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Science Division)

    2011-06-07

    associated with potential exposure to contaminated groundwater at Hanover. No drinking water wells are known to exist in Hanover, and the drinking water supply comes from RWD No.1 at Lanham, Kansas, located 6.5 mi north of Hanover. Limited potential risk was identified due to exposure to indoor air contaminated with carbon tetrachloride, but this risk has been mitigated, thereby removing this threat to human health. Radon is prevalent in the community, at concentrations exceeding the level at which the EPA recommends additional measures (testing and/or mitigation). The recommended testing and mitigation (if needed) are the responsibility of the homeowners. In the current condition in which no private wells are used for drinking water in the affected area, no unacceptable human health risk from carbon tetrachloride is associated with the identified impacted media at the Hanover site.

  20. Site-conditions map for Portugal based on VS measurements: methodology and final model

    Science.gov (United States)

    Vilanova, Susana; Narciso, João; Carvalho, João; Lopes, Isabel; Quinta Ferreira, Mario; Moura, Rui; Borges, José; Nemser, Eliza; Pinto, carlos

    2017-04-01

    In this paper we present a statistically significant site-condition model for Portugal based on shear-wave velocity (VS) data and surface geology. We also evaluate the performance of commonly used Vs30 proxies based on exogenous data and analyze the implications of using those proxies for calculating site amplification in seismic hazard assessment. The dataset contains 161 Vs profiles acquired in Portugal in the context of research projects, technical reports, academic thesis and academic papers. The methodologies involved in characterizing the Vs structure at the sites in the database include seismic refraction, multichannel analysis of seismic waves and refraction microtremor. Invasive measurements were performed in selected locations in order to compare the Vs profiles obtained from both invasive and non-invasive techniques. In general there was good agreement in the subsurface structure of Vs30 obtained from the different methodologies. The database flat-file includes information on Vs30, surface geology at 1:50.000 and 1:500.000 scales, elevation and topographic slope and based on SRTM30 topographic dataset. The procedure used to develop the site-conditions map is based on a three-step process that includes defining a preliminary set of geological units based on the literature, performing statistical tests to assess whether or not the differences in the distributions of Vs30 are statistically significant, and merging of the geological units accordingly. The dataset was, to some extent, affected by clustering and/or preferential sampling and therefore a declustering algorithm was applied. The final model includes three geological units: 1) Igneous, metamorphic and old (Paleogene and Mesozoic) sedimentary rocks; 2) Neogene and Pleistocene formations, and 3) Holocene formations. The evaluation of proxies indicates that although geological analogues and topographic slope are in general unbiased, the latter shows significant bias for particular geological units and

  1. Probabilistic approaches for geotechnical site characterization and slope stability analysis

    CERN Document Server

    Cao, Zijun; Li, Dianqing

    2017-01-01

    This is the first book to revisit geotechnical site characterization from a probabilistic point of view and provide rational tools to probabilistically characterize geotechnical properties and underground stratigraphy using limited information obtained from a specific site. This book not only provides new probabilistic approaches for geotechnical site characterization and slope stability analysis, but also tackles the difficulties in practical implementation of these approaches. In addition, this book also develops efficient Monte Carlo simulation approaches for slope stability analysis and implements these approaches in a commonly available spreadsheet environment. These approaches and the software package are readily available to geotechnical practitioners and alleviate them from reliability computational algorithms. The readers will find useful information for a non-specialist to determine project-specific statistics of geotechnical properties and to perform probabilistic analysis of slope stability.

  2. Site characterization data from the Area 5 science boreholes, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Blout, D.O.; Hammermeister, P.; Zukosky, K.A.

    1995-02-01

    The Science Borehole Project consists of eight boreholes that were drilled (from 45.7 m [150 ft] to 83.8 m [275 ft] depth) in Area 5 of the Nevada Test Site, Nye County, Nevada, on behalf of the US Department of Energy. These boreholes are part of the Area 5 Site Characterization Program developed to meet data needs associated with regulatory requirements applicable to the disposal of low-level and mixed waste at this site. This series of boreholes was specifically designed to characterize parameters controlling near-surface gas transport and to monitor changes in these and liquid flow-related parameters over time. These boreholes are located along the four sides of the approximately 2.6-km 2 (1-mi 2 ) Area 5 Radioactive Waste Management Site to provide reasonable spatial coverage for sampling and characterization. Laboratory testing results of samples taken from core and drill cuttings are reported

  3. Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

    International Nuclear Information System (INIS)

    1987-03-01

    The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

  4. Tomographic Site Characterization Using CPT, ERT, and GPR

    Energy Technology Data Exchange (ETDEWEB)

    Rexford M. Morey

    1997-05-23

    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.

  5. Site Characterization Work Plan for Gasbuggy, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NV

    2000-12-14

    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

  6. Soil characterization methods for unsaturated low-level waste sites

    International Nuclear Information System (INIS)

    Wierenga, P.J.; Young, M.H.; Hills, R.G.

    1993-01-01

    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

  7. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-01-01

    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.

  8. Northeastern Regional environmental characterization report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Maine, New Hampshire, Vermont, northeastern and southeastern New York, Massachusetts, Rhode Island, Connecticut, northern New Jersey, and eastern Pennsylvania. For each of the States within the Northeastern Region, information is provided on those environmental disqualifying factors and regional screening variables to be used in region-to-area screening. These environmental factors and variables include existing and proposed Federal-protected lands, components of National Forest Lands, proximity to Federal-protected lands, existing State-protected lands, proximity to State-protected lands, population density and distribution, proximity to highly populated areas, or to 1-mile-square areas with 1000 or more persons, National and State forest lands, designated critical habitats for threatened and endangered species, surface water bodies, and wetlands. In addition, supplementary descriptive information providing a general characterization of the region is presented, as is information on environmental parameters that will be of use at later phases of screening. Also included is a discussion of the relationship between the US Department of Energy Siting Guidelines (10 CFR 960) and those environmental disqualifying factors and regional screening variables to be used in the region-to-area screening process

  9. Southeastern Regional Environmental Characterization Report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in central Maryland; noncoastal Virginia, North Carolina, and South Carolina; and northern Georgia. For each of the States within the Southeastern Region, information is provided on those environmental disqualifying factors and regional screening variables to be used in region-to-area screening. These environmental factors and variables include existing and proposd Federal-protected lands, components of National Forest Lands, proximity to Federal-protected lands, existing State-protected lands, proximity to State-protected lands, population density and distribution, proximity to highly populated areas, or to 1-mile-square areas with 1000 or more persons, national and State forest lands, designated critical habitats for threatened and endangered species, surface water bodies, and wetlands. In addition, supplementary descriptive information providing a general characterization of the region is presented, as is information on environmental parameters that will be of use at later phases of screening. Also included is a discussion of the relationship between the US Department of Energy Siting Guidelines (10 CFR 960) and those environmental disqualifying factors and regional screening variables to be used in the region-to-area screening process

  10. North Central Regional environmental characterization report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the states within the North Central Region, information is provided on those environmental disqualifying factors and regional screening variables to be used in region-to-area screening. These environmental factors and variables include existing and proposed Federal-protected lands, proximity to Federal-protected lands, components of national forest lands, existing state-protected lands, proximity to state-protected lands, population density and distribution, proximity to highly populated areas or to 1-mile square areas with 1000 or more persons, national and state forest lands, designated critical habitats for threatened and endangered spcies, surface water bodies, and wetlands. In addition, supplementary descriptive information providing a general characterization of the region is presented, as is information on environmental parameters that will be of use at later phases of screening. Also included is a discussion of the relationship between the US Department of Energy Siting Guidelines (10CFR 960) and those environmental disqualifying factors and regional screening variables to be used in the region-to-area screening process

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

    International Nuclear Information System (INIS)

    Cushing, C.E.

    1992-12-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. (ed.)

    1992-12-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. [ed.

    1992-12-01

    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.

  14. 77 FR 16558 - General Management Plan/Final Environmental Impact Statement, Hampton National Historic Site...

    Science.gov (United States)

    2012-03-21

    ... Management Plan/Final Environmental Impact Statement, Hampton National Historic Site, Maryland AGENCY...) announces the availability of the Final Environmental Impact Statement for the General Management Plan.../Baltimore County Library, 320 York Avenue, Towson, Maryland 21204. Baltimore County Tourism Office and...

  15. 10 CFR 60.17 - Contents of site characterization plan.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Contents of site characterization plan. 60.17 Section 60.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN... section 112(a) of the Nuclear Waste Policy Act of 1982, to be used to determine the suitability of such...

  16. Leachate characterization of active and closed dump sites in Port ...

    African Journals Online (AJOL)

    This study characterizes the leachate quality of both active and closed dump sites in Port Harcourt City. Leachates were sampled from the base of the dum psites and analysed, pH, dissolved oxygen (DO), electrical conductivity and total dissolved solids were determined on the samples in-situ. While chloride, sulphate ...

  17. Analysis Of The Tank 6F Final Characterization Samples-2012

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  18. Analysis of the Tank 6F Final Characterization Samples-2012

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2013-01-31

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm- 243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  19. ANALYSIS OF THE TANK 6F FINAL CHARACTERIZATION SAMPLES-2012

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.; Shine, G.

    2012-06-28

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  20. An object-oriented approach to site characterization decision support

    International Nuclear Information System (INIS)

    Johnson, R.

    1995-01-01

    Effective decision support for site characterization is key to determining the nature and extent of contamination and the associated human and environmental risks. Site characterization data, however, present particular problems to technical analysts and decision-makers. Such data are four dimensional, incorporating temporal and spatial components. Their sheer volume can be daunting -- sites with hundreds of monitoring wells and thousands of samples sent for laboratory analyses are not uncommon. Data are derived from a variety of sources including laboratory analyses, non-intrusive geophysical surveys, historical information, bore logs, in-field estimates of key physical parameters such as aquifer transmissivity, soil moisture content, depth-to-water table, etc. Ultimately, decisions have to be made based on data that are always incomplete, often confusing, inaccurate, or inappropriate, and occasionally wrong. In response to this challenge, two approaches to environmental decision support have arisen, Data Quality Objectives (DQOS) and the Observational Approach (OA). DQOs establish criteria for data collection by clearly defining the decisions that need to be made, the uncertainty that can be tolerated, and the type and amount of data that needs to be collected to satisfy the uncertainty requirements. In practice, DQOs are typically based on statistical measures. The OA accepts the fact that the process of characterizing and remediating contaminated sites is always uncertain. Decision-making with the OA is based on what is known about a site, with contingencies developed for potential future deviations from the original assumptions about contamination nature, extent, and risks posed

  1. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington Site. Main report and Appendices A through D

    International Nuclear Information System (INIS)

    1983-03-01

    On November 12, 1982, the US Department of Energy submitted to the US Nuclear Regulatory Commission the Site Characterization Report for the Basalt Waste Isolation Project (DOE/RL 82-3). The Basalt Waste Isolation Project is located on DOE's Hanford Reservation in the State of Washington. NUREG-0960 contains the detailed analysis, by the NRC staff, of the site characterization report. Supporting technical material is contained in Appendices A through W

  2. Environmental monitoring and mitigation plan for site characterization: Revision 1

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of the EMMP is: to identify, in consultation with the affected states and Indian tribes, potentially significant adverse environmental impacts that could result from site characterization activities, to describe data collection methods that will be used to monitor any such identified impacts, and procedures for mitigating them. Chapter 2 of the EMMP provides an overview of the background and scope of the document. Chapter 3 of the EMMP provides a description of site characterization phase activities planned to assess the geologic condition of the site and construct the exploratory shafts and surface support facilities. The rationale for developing environmental monitoring studies is presented in Chapeter 4. Chapter 5 contains descriptions of the environmental monitoring and mitigation procedures whenever they are applicable. Additionally, in Chapter 6, the EMMP includes a procedure for modifying the monitoring and mitigation program and an approach for reporting monitoring results to interested parties. 21 figs., 10 tabs

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

    Energy Technology Data Exchange (ETDEWEB)

    McPherson, Brian; Matthews, Vince

    2013-09-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Nevada Geotechnical Sciences

    2005-06-01

    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.

  6. Characterization Report Operational Closure Covers for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    International Nuclear Information System (INIS)

    Bechtel Nevada Geotechnical Sciences

    2005-01-01

    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

  7. Advances in characterizing ubiquitylation sites by mass spectrometry

    DEFF Research Database (Denmark)

    Sylvestersen, K.B.; Young, C.; Nielsen, M.L.

    2013-01-01

    The attachment of one or more ubiquitin moieties to proteins plays a central regulatory mechanism in eukaryotic cells. Protein ubiquitylation regulates numerous cellular processes, including protein degradation, signal transduction, DNA repair and cell division. The characterization of ubiquityla......The attachment of one or more ubiquitin moieties to proteins plays a central regulatory mechanism in eukaryotic cells. Protein ubiquitylation regulates numerous cellular processes, including protein degradation, signal transduction, DNA repair and cell division. The characterization...... of ubiquitylation is a two-fold challenge that involves the mapping of ubiquitylation sites and the determination of ubiquitin chain topology. This review focuses on the technical advances in the mass spectrometry-based characterization of ubiquitylation sites, which have recently involved the large...

  8. Characterization of Rous sarcoma virus polyadenylation site use in vitro

    International Nuclear Information System (INIS)

    Maciolek, Nicole L.; McNally, Mark T.

    2008-01-01

    Polyadenylation of Rous sarcoma virus (RSV) RNA is inefficient, as approximately 15% of RSV RNAs represent read-through transcripts that use a downstream cellular polyadenylation site (poly(A) site). Read-through transcription has implications for the virus and the host since it is associated with oncogene capture and tumor induction. To explore the basis of inefficient RSV RNA 3'-end formation, we characterized RSV polyadenylation in vitro using HeLa cell nuclear extracts and HEK293 whole cell extracts. RSV polyadenylation substrates composed of the natural 3' end of viral RNA and various lengths of upstream sequence showed little or no polyadenylation, indicating that the RSV poly(A) site is suboptimal. Efficiently used poly(A) sites often have identifiable upstream and downstream elements (USEs and DSEs) in close proximity to the conserved AAUAAA signal. The sequences upstream and downstream of the RSV poly(A) site deviate from those found in efficiently used poly(A) sites, which may explain inefficient RSV polyadenylation. To assess the quality of the RSV USEs and DSEs, the well-characterized SV40 late USEs and/or DSEs were substituted for the RSV elements and vice versa, which showed that the USEs and DSEs from RSV are suboptimal but functional. CstF interacted poorly with the RSV polyadenylation substrate, and the inactivity of the RSV poly(A) site was at least in part due to poor CstF binding since tethering CstF to the RSV substrate activated polyadenylation. Our data are consistent with poor polyadenylation factor binding sites in both the USE and DSE as the basis for inefficient use of the RSV poly(A) site and point to the importance of additional elements within RSV RNA in promoting 3' end formation

  9. Acquisition of Single Crystal Growth and Characterization Equipment. Final report

    International Nuclear Information System (INIS)

    Maple, M. Brian; Zocco, Diego A.

    2008-01-01

    Final Report for DOE Grant No. DE-FG02-04ER46178 'Acquisition of Single Crystal Growth and Characterization Equipment'. There is growing concern in the condensed matter community that the need for quality crystal growth and materials preparation laboratories is not being met in the United States. It has been suggested that there are too many researchers performing measurements on too few materials. As a result, many user facilities are not being used optimally. The number of proficient crystal growers is too small. In addition, insufficient attention is being paid to the enterprise of finding new and interesting materials, which is the driving force behind much of condensed matter research and, ultimately, technology. While a detailed assessment of this situation is clearly needed, enough evidence of a problem already exists to compel a general consensus that the situation must be addressed promptly. This final report describes the work carried out during the last four years in our group, in which a state-of-the-art single crystal growth and characterization facility was established for the study of novel oxides and intermetallic compounds of rare earth, actinide and transition metal elements. Research emphasis is on the physics of superconducting (SC), magnetic, heavy fermion (HF), non-Fermi liquid (NFL) and other types of strongly correlated electron phenomena in bulk single crystals. Properties of these materials are being studied as a function of concentration of chemical constituents, temperature, pressure, and magnetic field, which provide information about the electronic, lattice, and magnetic excitations at the root of various strongly correlated electron phenomena. Most importantly, the facility makes possible the investigation of material properties that can only be achieved in high quality bulk single crystals, including magnetic and transport phenomena, studies of the effects of disorder, properties in the clean limit, and spectroscopic and scattering

  10. Characterization of biogas bibliography measures on sites; Caracterisation des Biogaz bibliographie mesures sur sites

    Energy Technology Data Exchange (ETDEWEB)

    Poulleau, J.

    2002-10-15

    The aim of this study is to define the pollutants emissions related to the combustion of biogas of different sources: motors, furnaces, flares...The project is presented in three parts: a bibliographic study on the chemical characterization of the biogas, a first series of measures on production sites and a second series of measures on a site of valorization and destruction of biogas. (A.L.B.)

  11. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

    2012-02-26

    The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. DOE must continue to maintain constructive relationships with the U

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-09-01

    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.

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

    International Nuclear Information System (INIS)

    Cushing, C.E.; Baker, D.A.; Chamness, M.A.

    1994-08-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-08-01

    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.

  15. Characterization of radioactively contaminated sites for remediation purposes

    International Nuclear Information System (INIS)

    1998-05-01

    Characterization of the contaminated site is essential before embarking on a programme for its remediation and ultimate restoration. Reliable and suitable data must be obtained regarding the distribution and physical, chemical and nuclear properties of all radioactive contaminants. Characterization data is necessary for assessing the associated radiation risks and is used in support of the required engineering design and project planning for the environmental restoration. In addition, continuing characterization can provide information regarding efficiency of the cleanup methods and influence possible redirection of work efforts. Similarly, at the end of the remediation phase, characterization and ongoing monitoring can be used to demonstrate completion and success of the cleanup process. The suggested methodology represents a contribution attempting to solve the issue of preremediation characterization in a general manner. However, a number of difficulties might make this methodology unsuitable for general application across the diverse social, environmental and political systems in the IAEA Member States. This TECDOC covers the methodologies used to characterize radioactively contaminated sites for the purpose of remediating the potential sources of radiation exposure and assessing the hazards to human health and the environment

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-08-01

    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.

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

    International Nuclear Information System (INIS)

    Neitzel, D.A.; Bjornstad, B.N.; Fosmire, C.J.

    1997-08-01

    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

  18. Southern Great Plains Ice Nuclei Characterization Experiment Final Campaign Summary

    Energy Technology Data Exchange (ETDEWEB)

    DeMott, PJ [Colorado State University; Suski, KJ [Colorado State University; Hill, TCJ [Colorado State University; Levin, EJT [Colorado State University

    2015-03-01

    The first ever ice nucleating particle (INP) measurements to be collected at the Southern Great Plains site were made during a period from late April to June 2014, as a trial for possible longer-term measurements at the site. These measurements will also be used to lay the foundation for understanding and parameterizing (for cloud resolving modeling) the sources of these climatically important aerosols as well as to augment the existing database containing this knowledge. Siting the measurements during the spring was intended to capture INP sources in or to this region from plant, soil, dust transported over long distances, biomass burning, and pollution aerosols at a time when they may influence warm-season convective clouds and precipitation. Data have been archived of real-time measurements of INP number concentrations as a function of processing conditions (temperature and relative humidity) during 18 days of sampling that spanned two distinctly different weather situations: a warm, dry and windy period with regional dust and biomass burning influences in early May, and a cooler period of frequent precipitation during early June. Precipitation delayed winter wheat harvesting, preventing intended sampling during that perturbation on atmospheric aerosols. INP concentrations were highest and most variable at all temperatures in the dry period, where we attribute the INP activity primarily to soil dust emissions. Additional offline INP analyses are underway to extend the characterization of INP to cover the entire mixed phase cloud regime from -5°C to -35°C during the full study. Initial comparisons between methods on four days show good agreement and excellent future promise. The additional offline immersion freezing data will be archived as soon as completed under separate funding. Analyses of additional specialized studies for specific attribution of INP to biological and smoke sources are continuing via the National Science Foundation and National Aeronautics

  19. Coordinated site characterization and performance assessment - an iterative approach for the site evaluation

    International Nuclear Information System (INIS)

    Papp, T.; Ericsson, L.O.; Thegerstroem, C.; Almen, K.E.

    1995-01-01

    SKB planning for siting a deep repository involves feasibility studies in 5-10 municipalities surface based characterization and drilling on two candidate sites and detailed characterization of one site including a shaft to proposed repository depth. The selection of a site or the detailed layout of the repository defines characteristics that might influence safety in a broad sense. There is a strong ling between the safety, technical (engineering) and functional aspects. The site selection will be based on general geoscientific information, i.e. mechanical stability, ground-water chemistry, slow ground-water movements and complicating factors like high potential for mineralization. The general layout of the repository in the actual geological structure of the site must be done with regard to a number of guidelines, e.g. to hydraulically separate the parts of the repository containing the spent nuclear fuel from those for other types of long lived waste and to separate the two stages of the spent fuel repository so they can be handled separately in the licensing process. When the various parts of the repository have been tentatively located the consequence of the multiple barrier principle is that the layout of the various parts should be made with the aim to utilize the available natural barrier system at the site as well as possible. (authors). 2 refs., 3 figs., 2 tabs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-08-01

    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.

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

    International Nuclear Information System (INIS)

    Neitzel, D.A.; Bjornstad, B.N.; Fosmire, C.J.; Fowler, R.A.

    1996-08-01

    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

  2. The Rocky Flats Environmental Technology Site beryllium characterization project

    International Nuclear Information System (INIS)

    Morrell, D.M.; Miller, J.R.; Allen, D.F.

    1999-01-01

    A site beryllium characterization project was completed at the Rocky Flats Environmental Technology Site (RFETS) in 1997. Information from historical reviews, previous sampling surveys, and a new sampling survey were used to establish a more comprehensive understanding of the locations and levels of beryllium contamination in 35 buildings. A feature of the sampling strategy was to test if process knowledge was a good predictor of where beryllium contamination could be found. Results revealed that this technique was effective at identifying where surface contamination levels might exceed the RFETS smear control level but that it was not effective in identifying where low concentrations of beryllium might be found

  3. Site study plan for borehole search and characterization, Deaf Smith County Site, Texas: Revision 1

    International Nuclear Information System (INIS)

    1987-01-01

    This site study plan describes the Borehole Search and Characterization field activities to be conducted during the early stages of Site Characterization at the Deaf Smith County site, Texas. The field program has been designed to provide data useful in addressing information/data needs resulting from Federal/State/Local regulatory requirements and repository program requirements. Air and ground surveys, an extensive literature search, and landowner interviews will be conducted to locate wells within and adjacent to the proposed nuclear waste repository site in Deaf Smith County. Initially, the study will center around the planned Exploratory Shaft Facilities location and will expand outward from that location. Findings from this study may lead to preparation of a new site study plan to search suspected borehole locations, and excavate or reenter known boreholes for additional characterization or remedial action. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. The Technical Field Services Contractor (TFSC) is responsible for conducting the field program. Data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that appropriate documentation is maintained. 13 refs., 6 figs., 3 tabs

  4. A proposed descriptive methodology for environmental geologic (envirogeologic) site characterization

    International Nuclear Information System (INIS)

    Schwarz, D.L.; Snyder, W.S.

    1994-01-01

    We propose a descriptive methodology for use in environmental geologic (envirogeologic) site characterization. The method uses traditional sedimentologic descriptions augmented by environmental data needs, and facies analysis. Most other environmental methodologies for soil and sediment characterization use soil engineering and engineering geology techniques that classify by texture and engineering properties. This technique is inadequate for envirogeologic characterization of sediments. In part, this inadequacy is due to differences in the grain-size between the Unified soil Classification and the Udden-Wentworth scales. Use of the soil grain-size classification could easily cause confusion when attempting to relate descriptions based on this classification to our basic understanding of sedimentary depositional systems. The proposed envirogeologic method uses descriptive parameters to characterize a sediment sample, suggests specific tests on samples for adequate characterization, and provides a guidelines for subsurface facies analysis, based on data retrieved from shallow boreholes, that will allow better predictive models to be developed. This methodology should allow for both a more complete site assessment, and provide sufficient data for selection of the appropriate remediation technology, including bioremediation. 50 refs

  5. Variables in different ecosystems, suitable to describe at site characterization for a repository

    International Nuclear Information System (INIS)

    Lindborg, T.; Kautsky, U.

    2000-10-01

    This report is a first step to create a documentation of the ecosystems close to the surface, that will be a part of the site characterization program. The variables list all the information that can be collected from a site. Local conditions and methodology development will influence the final choice of parameters and need for information collection. The variables are divided into the groups: Man, Climate, Physical geography, Biota and Hydrology and has been rated according to their expected importance for different application areas

  6. Perspectives on innovative characterization and remediation technologies for contaminated sites

    International Nuclear Information System (INIS)

    Kovalick, W.W. Jr.

    2002-01-01

    Contaminated soil and groundwater have been the subject of legislative attention in the U.S. for about 20 years. Major strides in implementing cleanup programs have been accomplished. From complex abandoned hazardous waste sites to underground petroleum storage tanks to (more recently) Brownfields redevelopment, much assessment and remediation work have been carried out. This paper describes some of the data on the kinds of contamination, media, and technologies deployed to deal with problems at these sites. In addition, it highlights technology partnerships that have evolved to demonstrate and verify site measurement and clean-up technologies and to assure a more robust set of clean-up options. Finally, the advent of the Internet has increased access to a considerable body of publicly available information on the cost and performance of these technologies that might be of interest. (author)

  7. Analysis Of The Tank 5F Final Characterization Samples-2011

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L. N.; Diprete, D.; Coleman, C. J.; Hay, M. S.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  8. ANALYSIS OF THE TANK 5F FINAL CHARACTERIZATION SAMPLES-2011

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

    2012-08-03

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  9. Nevada Test Site site treatment plan. Final annual update. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    A Site Treatment Plan (STP) is required for facilities at which the US Department of Energy Nevada Operations Office (DOE/NV) generates or stores mixed waste (MW), defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act (RCRA) and a radioactive material subject to the Atomic Energy Act. This STP was written to identify specific treatment facilities for treating DOE/NV generated MW and provides proposed implementation schedules. This STP was approved by the Nevada Division of Environmental Protection (NDEP) and provided the basis for the negotiation and issuance of the FFCAct Consent Order (CO) dated March 6, 1996. The FFCAct CO sets forth stringent regulatory requirements to comply with the implementation of the STP

  10. Yucca Mountain Site characterization project bibliography, January--June 1991

    International Nuclear Information System (INIS)

    Lorenz, J.J.; Stephan, P.M.

    1991-09-01

    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 1991 through June 1991. 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

  11. Yucca Mountain Site Characterization Project bibliography, January--June 1992

    International Nuclear Information System (INIS)

    1992-01-01

    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, 1993, through June 30, 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

  12. Software quality assurance on the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Matras, J.R.

    1993-01-01

    The Yucca Mountain Site Characterization Project (YMP) has been involved over the years in the continuing struggle with establishing acceptable Software Quality Assurance (SQA) requirements for the development, modification, and acquisition of computer programs used to support the Mined Geologic Disposal System. These computer programs will be used to produce or manipulate data used directly in site characterization, design, analysis, performance assessment, and operation of repository structures, systems, and components. Scientists and engineers working on the project have claimed that the SQA requirements adopted by the project are too restrictive to allow them to perform their work. This paper will identify the source of the original SQA requirements adopted by the project. It will delineate the approach used by the project to identify concerns voiced by project engineers and scientists regarding the original SQA requirements. It will conclude with a discussion of methods used to address these problems in the rewrite of the original SQA requirements

  13. Yucca Mountain Site Characterization Project Bibliography, July--December 1990

    International Nuclear Information System (INIS)

    1991-05-01

    Following a reorganization of the Office of Civilian Radioactive Waste Management, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountains 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 July 1990 through December 1990. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers and articles are included in the sponsoring organizations 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

  14. Yucca Mountain Site characterization project bibliography, January--June 1992

    International Nuclear Information System (INIS)

    1992-09-01

    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 June 30, 1992. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor resorts, 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

  15. Ground-water protection standards for inactive uranium tailings sites (40 CFR 192): Background information for final rule. Final report

    International Nuclear Information System (INIS)

    1989-03-01

    The Final Background Information Document summarizes the information and data considered by the Agency in developing the ground-water protection standards. The report presents a brief description of the Title II ground water standard and how it can be used to develop the Title I rulemaking. A description of the 24 designated uranium-tailings sites and their current status in the DOE remedial-action program is included as well as a detailed analysis of the available data on the ground water in the vicinity of 14 of the 24 sites. It also describes different methods that can be used for the restoration of ground water and the costs of using these restoration methods

  16. Characterization of a potential radiation-sensitive fragile site

    International Nuclear Information System (INIS)

    Jordan, R.; Oroskar, A.A.; Sedita, B.A.

    1995-01-01

    We have been characterizing a Chinese hamster ovary cell line, CHO-K1 10T5, into which a gpt-containing retroviral shuttle vector has been stably integrated. This normally stable locus in CHO-K1 10T5 cells is very sensitive to deletion mutation following ionizing radiation exposure and shows an LET response with an RBE of 3 for α particles. Almost all of the gpt mutants are total gene deletions. The gpt gene has been localized to chromosome 5q15, within 100-1000 kb of a large region of interstitial telomere repeats. In addition, sequences showing homology to telomere repeat sequences have been identified at the integration site both 5' and 3' to the gpt gene locus. The integration site has been cloned and is presently being sequenced. Preliminary data suggest that there is a hotspot for breakage and/or recombination 5' of the integration site. We hypothesize that (1) the gpt vector has integrated into a region containing telomere repeat sequences, (2) this region of the genome is a radiation-sensitive fragile site, and (3) the radiation sensitivity of this site is due to the telomere sequences, which act by either serving as a site for further telomerase action and chromosome terminilization, or by providing repeat structures to facilitate radiation-induced recombination

  17. Site characterization in densely fractured dolomite: Comparison of methods

    Science.gov (United States)

    Muldoon, M.; Bradbury, K.R.

    2005-01-01

    One of the challenges in characterizing fractured-rock aquifers is determining whether the equivalent porous medium approximation is valid at the problem scale. Detailed hydrogeologic characterization completed at a small study site in a densely fractured dolomite has yielded an extensive data set that was used to evaluate the utility of the continuum and discrete-fracture approaches to aquifer characterization. There are two near-vertical sets of fractures at the site; near-horizontal bedding-plane partings constitute a third fracture set. Eighteen boreholes, including five coreholes, were drilled to a depth of ???10.6 m. Borehole geophysical logs revealed several laterally extensive horizontal fractures and dissolution zones. Flowmeter and short-interval packer testing identified which of these features were hydraulically important. A monitoring system, consisting of short-interval piezometers and multilevel samplers, was designed to monitor four horizontal fractures and two dissolution zones. The resulting network consisted of >70 sampling points and allowed detailed monitoring of head distributions in three dimensions. Comparison of distributions of hydraulic head - and hydraulic conductivity determined by these two approaches suggests that even in a densely fractured-carbonate aquifer, a characterization approach using traditional long-interval monitoring wells is inadequate to characterize ground water movement for the purposes of regulatory monitoring or site remediation. In addition, traditional multiwell pumping tests yield an average or bulk hydraulic conductivity that is not adequate for predicting rapid ground water travel times through the fracture network, and the pumping test response does not appear to be an adequate tool for assessing whether the porous medium approximation is valid. Copyright ?? 2005 National Ground Water Association.

  18. Selection and cultivation of final vegetative cover for closed waste sites at the Savannah River Site, SC

    International Nuclear Information System (INIS)

    Cook, J.R.; Salvo, S.K.

    1992-01-01

    Low-level, hazardous, and mixed waste disposal sites normally require some form of plant material to prevent erosion of the final closure cap. Waste disposal sites are closed and capped in a complex scientific manner to minimize water infiltration and percolation into and through the waste material. Turf type grasses are currently being used as a vegetative cover for most sites. Consequently, the sites require periodic mowing and other expensive annual maintenance practices. The purpose of this five year study was to evaluate alternative plant material for use on wastes sites that is quickly and easily established and economically maintained, retards water infiltration, provides maximum year-round evapotranspiration, is ecologically acceptable and does not harm the closure cap. The results of the study are described in this report and suggest that two species of bamboo (Phyllostachys bissetii and P. rubromarainata) can be utilized to provide long lived, low maintenance, climax vegetation for the waste sites. These large species of bamboo will also reduce the probability of intrusion by humans, animals and deeply rooted plant species

  19. A method for evaluating the effectiveness of site characterization measurements

    International Nuclear Information System (INIS)

    Ditmars, J.D.

    1987-01-01

    A quantitative approach for evaluating the effectiveness of site characterization measurement activities is developed and illustrated with an example application to hypothetical measurement schemes at a potential geologic repository site for radioactive waste. The method is a general one and could also be applied at sites for underground disposal of hazardous chemicals. The approach presumes that measurements will be undertaken to support predictions of the performance of some aspect of a constructed facility or natural system. It requires a quantitative performance objective, such as groundwater travel time or contaminant concentration, against which to compare predictions of performance. The approach recognizes that such predictions are uncertain because the measurements upon which they are based are uncertain. The effectiveness of measurement activities is quantified by a confidence index, β, that reflects the number of standard deviations separating the best estimate of performance from the predetermined performance objective. Measurements that reduce the uncertainty in predictions lead to increased values of β. 5 refs., 4 figs

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-31

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

  1. Revised analysis of in-migrating workers during site characterization

    International Nuclear Information System (INIS)

    1987-10-01

    The Deaf Smith Environmental Assessment's analysis of in-migrating workers and community service impacts was predicated on the assumption that a peak of approximately 480 workers would be needed on location to conduct site characterization activities. This analysis assumed that DOE's prime contractor(s) would have a limited staff in the area; the majority of the workers would be on site for the construction of the exploratory shaft and to conduct geologic and environmental studies. Since the time when the Environmental Assessment was prepared, the prime contractors [Battelle-ISSC and the Technical Field Service Contractor (TFSC)] were requested to move their offices to the site area. Therefore, many more administrative and technical workers would be expected to relocate in the Deaf Smith County regions. A change in the expected number of in-migrants could also change the expected nature of community service impacts. It is the purpose of this analysis to evaluate the site characterization workforce and thresholds for local community services. 22 refs., 24 tabs

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-31

    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.

  3. Yucca Mountain Site Characterization Project Technical Data Catalog (quarterly supplement)

    International Nuclear Information System (INIS)

    1993-01-01

    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. 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 December 31, 1992, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1993

  4. Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    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.

  5. System analysis approach to verification of site characterization parameters

    International Nuclear Information System (INIS)

    Romine, D.T.

    1987-01-01

    Early in the transition of the Basalt Waste Isolation Project (BWIP) from a preliminary geologic investigation to a part of a major system acquisition program, the following project needs were recognized: (1) site-specific system functional requirements, i.e., the capabilities a deep geologic basalt system must provide to ensure long-term isolation of wastes, (2) complete list of design variables and site characteristics (information and data needs) that could affect system capabilities; and (3) relative importance, availability, and uncertainty of these information and data needs. The first project need was satisfied by a conventional functional analysis. The second was answered by a unique extension of that functional analysis. The results of these two efforts have been released in the BWIP System Functional Analysis (SFA) Document. The third need is presently under study. With the advent of a formalized issue resolution strategy (IRS) process as the basis for the BWIP site characterization program, a subset of the SFA information and data needs was used to verify (a) that no significant variable was omitted from consideration in the IRS process, (b) the necessity of IRS site characterization parameters, and (c) the sufficiency of each issue-related set of IRS parameters to address that issue. An example of a SFA branch is discussed

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-01-14

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NV

    2001-02-13

    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

  8. Characterization of reference and site specific human acids

    International Nuclear Information System (INIS)

    Kim, J.I.; Buckau, G.

    1988-01-01

    As a part of the interlaboratory exercise for the complexation of humic acid and colloid generation (COCO-Club activities) in the CEC project MIRAGE-II, the characterization of humic acids have been carried out, as for their elemental compositions, inorganic impurities, spectroscopic properties, size distributions and proton exchange capacities. The commercial humic acid (Na salt) from Aldrich Co. is purified to a protonated form and used as a reference material, and the humic acid extracted from one of Gorleben groundwaters is also purified to a protonated form and taken as a site specific material. These two humic acids, together with the original Na salt from Aldrich Co., are included for the characterization exercise. The results of characterization provide a basic knowledge that supports the forthcoming study of complexation of humic acids with actinides and fission products in their migration processes in the geosphere. (orig.)

  9. Characterization of reference and site specific humic acids

    International Nuclear Information System (INIS)

    Kim, J.I.; Buckau, G.

    1988-11-01

    As a contribution to the interlaboratory exercise for the complexation of humic acid and colloid generation (COCO-Club activities) in the CEC project MIRAGE-II, the characterization of selected humic acids have been carried out at TU Muenchen, regarding their elemental compositions, inorganic impurities, spectroscopic properties, size distributions and proton exchange capacities. The commercial humic acid (Na salt) from Aldrich Co. is purified to a protonated form and used as reference material. Furthermore two humic acids extracted from groundwaters from Gorleben (FRG) and Boom Clay (B) are purified to protonated forms and taken as site specific materials. These three humic acids, together with the original Na salt from Aldrich Co., are included in the present characterization exercise. The results of characterization provide basic knowledge supporting the forthcoming study of complexation of actinides and fission products with humic acid and their migration processes in the geosphere. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    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.

  11. Site characterization plan overview: Yucca Mountain site, Nevada Reserch and Development Area, Nevada

    International Nuclear Information System (INIS)

    1988-12-01

    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

  12. Treatment and final disposal of nuclear waste. Siting of a deep repository

    International Nuclear Information System (INIS)

    1992-09-01

    Systems and facilities in the program for demonstration deposition of nuclear waste are presented. The siting process is described, from the general studies to the ultimate goal, where a permit to start demonstration deposition has been obtained. National and foreign experiences of siting issues are accounted for. Finally, the structure and plan for work for 1993-98 are outlined. 46 refs, 15 figs, 5 tabs

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

    International Nuclear Information System (INIS)

    1994-02-01

    The Special Projects Section (SPS) of Reynolds Electrical ampersand 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

  14. Radiological characterization: from in situ measurement to the final parcel characterization

    International Nuclear Information System (INIS)

    Toubon, H.

    2009-01-01

    In this abstract of his contribution, after having outlined the main objectives of nuclear measurements during decontamination operations occurring for example during dismantling operations, the author states he will define the apparatus detection principles, present some typical applications of nuclear measurements and define the required means. He also states he will make a distinction between portable means (for upstream investigations and operation follow-on: neutron or gamma counters, spectrometers) and fixed systems (for process control and final characterization of parcels: gamma counter, tomography)

  15. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado: Final report

    International Nuclear Information System (INIS)

    1990-02-01

    This radiologic characterization of tho two inactive uranium millsites at Rifle, Colorado, was conducted by Bendix Field Engineering Corporation (Bendix) for the US Department of Energy (DOE), Grand Junction Projects Office, in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor, Jacobs Engineering Group, Inc. (Jacobs). The purpose of this project is to define the extent of radioactive contamination at the Rifle sites that exceeds US Environmental Protection Agency, (EPA) standards for UMTRA sites. The data presented in this report are required for characterization of the areas adjacent to the tailings piles and for the subsequent design of cleanup activities. An orientation visit to the study area was conducted on 31 July--1 August 1984, in conjunction with Jacobs, to determine the approximate extent of contaminated area surrounding tho piles. During that visit, survey control points were located and baselines were defined from which survey grids would later be established; drilling requirements were assessed; and radiologic and geochemical data were collected for use in planning the radiologic fieldwork. The information gained from this visit was used by Jacobs, with cooperation by Bendix, to determine the scope of work required for the radiologic characterization of the Rifle sites. Fieldwork at Rifle was conducted from 1 October through 16 November 1984

  16. FY 93 site characterization status report and data package for the carbon tetrachloride site

    Energy Technology Data Exchange (ETDEWEB)

    Rohay, V.J. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-09-28

    This report provides the status and accomplishments from fiscal year site characterization activities conducted as part of the 200 West Area Carbon Tetrachloride Expedited Response Action and the Volatile Organic Compounds - Arid Integrated Demonstration. The report includes or references all available raw data collected as part of these tasks. During fiscal year 1993, the 200 West Area Carbon Tetrachloride Expedited Response Action and the Volatile Organic Compounds - Arid Integrated Demonstration programs focused on the carbon tetrachloride plume in the unsaturated zone underlying the 200 West Area at the Hanford Site in southeast Washington.

  17. Baseline and premining geochemical characterization of mined sites

    Science.gov (United States)

    Nordstrom, D. Kirk

    2015-01-01

    A rational goal for environmental restoration of new, active, or inactive mine sites would be ‘natural background’ or the environmental conditions that existed before any mining activities or other related anthropogenic activities. In a strictly technical sense, there is no such thing as natural background (or entirely non-anthropogenic) existing today because there is no part of the planet earth that has not had at least some chemical disturbance from anthropogenic activities. Hence, the terms ‘baseline’ and ‘pre-mining’ are preferred to describe these conditions. Baseline conditions are those that existed at the time of the characterization which could be pre-mining, during mining, or post-mining. Protocols for geochemically characterizing pre-mining conditions are not well-documented for sites already mined but there are two approaches that seem most direct and least ambiguous. One is characterization of analog sites along with judicious application of geochemical modeling. The other is reactive-transport modeling (based on careful synoptic sampling with tracer-injection) and subtracting inputs from known mining and mineral processing. Several examples of acidic drainage are described from around the world documenting the range of water compositions produced from pyrite oxidation in the absence of mining. These analog sites provide insight to the processes forming mineralized waters in areas untouched by mining. Natural analog water-chemistry data is compared with the higher metal concentrations, metal fluxes, and weathering rates found in mined areas in the few places where comparisons are possible. The differences are generally 1–3 orders of magnitude higher for acid mine drainage.

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

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. (ed.)

    1991-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. [ed.

    1991-12-01

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

  20. Site characterization plan overview: reference repository location, Hanford Site, Washington: Consultation draft: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    As part of the process for siting the nation's first geologic repository for radioactive waste, the Department of Energy (DOE) is preparing a site characterization plan for the Hanford site in Benton County, Washington. As a step in the preparation of that plan, the DOE has provided, for information and review, a consultation draft of the plan to the State of Washington, the affected Indian Tribes - the Confederated Tribes of the Umatilla Indian Reservation, the Nez Perce Indian Tribe, and the Yakima Indian Nation - and the US Nuclear Regulatory Commission. The Hanford site is one of three sites that the DOE currently plans to characterize;the other sites are the Deaf Smith County site in Texas and the Yucca Mountain site in Nevada. After site characterization has been completed and its results evaluated, the DOE will identify from among the three characterized sites the site that is preferred for the repository. The overview presented here consists of brief summaries of important topics covered in the consulation 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 breif descriptions of the dispoal system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Hanford site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons 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

  1. Statistical Methods and Tools for Uxo Characterization (SERDP Final Technical Report)

    Energy Technology Data Exchange (ETDEWEB)

    Pulsipher, Brent A.; Gilbert, Richard O.; Wilson, John E.; Hassig, Nancy L.; Carlson, Deborah K.; O' Brien, Robert F.; Bates, Derrick J.; Sandness, Gerald A.; Anderson, Kevin K.

    2004-11-15

    The Strategic Environmental Research and Development Program (SERDP) issued a statement of need for FY01 titled Statistical Sampling for Unexploded Ordnance (UXO) Site Characterization that solicited proposals to develop statistically valid sampling protocols for cost-effective, practical, and reliable investigation of sites contaminated with UXO; protocols that could be validated through subsequent field demonstrations. The SERDP goal was the development of a sampling strategy for which a fraction of the site is initially surveyed by geophysical detectors to confidently identify clean areas and subsections (target areas, TAs) that had elevated densities of anomalous geophysical detector readings that could indicate the presence of UXO. More detailed surveys could then be conducted to search the identified TAs for UXO. SERDP funded three projects: those proposed by the Pacific Northwest National Laboratory (PNNL) (SERDP Project No. UXO 1199), Sandia National Laboratory (SNL), and Oak Ridge National Laboratory (ORNL). The projects were closely coordinated to minimize duplication of effort and facilitate use of shared algorithms where feasible. This final report for PNNL Project 1199 describes the methods developed by PNNL to address SERDP's statement-of-need for the development of statistically-based geophysical survey methods for sites where 100% surveys are unattainable or cost prohibitive.

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

    International Nuclear Information System (INIS)

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

    2007-01-01

    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 and 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 and D activities, (3) reduces the number of required regulatory documents, and (4) in some cases, compresses schedules for achieving a stakeholder-approved end-state

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-06-11

    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.

  4. Geotechnical and geomechanical parameters required for characterization of sites

    International Nuclear Information System (INIS)

    Daniel, D.E.

    1982-01-01

    Characterization of disposal sites will involve geotechnical investigations and measurement of dozens of geomechanical parameters. The required investigations may be performed in stages, beginning with a preliminary study, or in a single evaluation. The geotechnical investigation will deal with the actual disposal site and the immediate area surrounding the site, and may include more detailed evaluation of the waste, disposal pits, and waste handling or processing structures. With respect to the actual site, the investigation is likely to focus on evaluating: (1) the types of subsurface soils or rocks present; (2) stability of the site; (3) potential for erosion; (4) ground water conditions; and (5) sources for construction materials. A variety of tests, some routine and some requiring state-of-the-art techniques, would be needed to measure parameters related to strength, compressibility, and permeability. The important mechanical properties of the waste (average density, compressibility, and potential for generation of gas) may be measured or, in some cases, estimated from experience. Detailed characterization will also be needed to evaluate stability of the walls of disposal pits, earthen covers over pits, any liner for the pit, any internal drains for the pit, and any internal system for collection or control of gas. Measurement and evaluation of most of these parameters is within the current state-of-practice. The parameters that will be the most difficult to measure and, at the same time, are of critical importance, are compressibility of the waste, characteristics of the earthen cover over the waste, and hydraulic conductivity of soils that contain thin sand seams, cracks, joints, or other hydraulic defects

  5. Myth and Reality in Hydrogeological Site Characterization at DD and R Sites

    International Nuclear Information System (INIS)

    Rubin, Yoram

    2008-01-01

    The science of hydrogeological site characterization has made significant progress over the last twenty years. Progress has been made in modeling of flow and transport in the heterogeneous subsurface, in understanding of the complex patterns of geological heterogeneity and in measurement technologies. Modeling of uncertainty has also advanced significantly, in recognition of the inherent limitations of subsurface characterization. Much less progress has been made in transforming this progress into practice, where characterization is determined to a large extent by regulations. Environmental regulations have not progressed as much as the science, for example, in recognizing uncertainty. As such, practitioners are less inclined to adopt advanced, science-based solutions, this opening the door for myths and conflicts. Myths develop where the science base is perceived to be weak, whereas conflicts arise in the face of a disconnect between the science and the regulations. Myths translate to ad-hoc solutions and misplaced empiricism, as well as to unjustified reliance on field experience, to the detriment of D and DR. This paper explores the roots for this situation and identifies ideas that may help in bridging the gap between research and applications. A rational approach for DD and R is needed that will encourage innovation in site characterization, reduce costs and accelerate completion. Such an approach needs to include several elements. DD and R regulations need to recognize the various aspects of uncertainty inherent to site characterization, and as such, should be formulated using probabilistic concepts. One of the immediate benefits will be in allowing a gradual approach for data acquisition in DD and R sites: decisions can be made even under the most severe data limitations, and can be modified as additional data become available. The definition of risk is another major element. There is no universal definition of risk or of a methodology to define risk

  6. Final audit report of remedial action construction at the UMTRA project site Rifle, Colorado. Rev. 1

    International Nuclear Information System (INIS)

    1997-01-01

    This final audit report summarizes the assessments performed by the U.S. Department of Energy (DOE) Environmental Restoration Division (ERD) and its Technical Assistance Contractor (TAC) of remedial action compliance with approved plans, specifications, standards, and 40 CFR Part 192 at the Rifle, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site. Remedial action construction was directed by the Remedial Action Contractor (RAC)

  7. Physicochemical characterization of ceramics from Sao Paulo II archaeological site

    International Nuclear Information System (INIS)

    Ribeiro, Rogerio Baria

    2013-01-01

    Archaeometry is a consolidated field with a wide application of nuclear analytical techniques for the characterization, protection, and restoration of archaeological pieces. This project aimed at studying the elementary chemical composition of 70 ceramic fragments samples from Sao Paulo II archaeological site, located along the Solimoes River channel, next to Coari city, in Brazilian Amazon. The characterization of samples was performed by neutron activation analysis (NAA). By the determination of 24 elements in the ceramic fragments ( Ce, Co, Cr, Cs, Eu, Fe, Hf, K, La, Lu, Na, Nd, Sb, Sm. Rb, Se, Ta, Tb, Th, U, Yb and Zn), it was possible to define groups of samples regarding the similarity/dissimilarity in elementary chemical composition. For such a task, the multivariate statistical methods employed were cluster analysis (C A), principal component analysis (PCA) and discriminant analysis (DA). Afterwards, seven ceramic fragments were selected based on the groups previously established, for the characterization of the site temporal horizon. Those ceramic fragments were analyzed by thermoluminescence (TL) and EPR for dating purposes. The firing temperatures were determined by electron paramagnetic resonance (EPR) technique, in order to infer about some aspects of the ceramic manufacture employed by the ancient peoples that lived in Sao Paulo 11. By the results obtained in this study, it was possible to identify the quantity of clay sources employed by the ceramists and the age of the ceramic pieces. Therefore, the results of this research may contribute to the study on the occupation dynamics in the pre-colonial Brazilian Amazon. (author)

  8. Final audit report of remedial action construction at the UMTRA Project Falls City, Texas, site

    International Nuclear Information System (INIS)

    1995-05-01

    This final audit report for the Falls City, Texas, Uranium Mill Tailings Remedial Action Project site summarizes the radiological audits and the quality assurance (QA) in-process surveillances, audits, and final close-out inspection performed by the U.S. Department of Energy (DOE) and Technical Assistance Contractor (TAC). It also summarizes U.S. Nuclear Regulatory Commission (NRC) surveillances. One radiological audit and three radiological surveillances were performed at the Falls City site. These surveillances and audit, which resulted in 31 observations, focused primarily on processing site activities and were performed on the following dates: 3-6 August 1992, 29-30 October 1992, 22-26 March 1993, and 1-3 November 1993. All outstanding radiological issues were closed out at the completion of the construction activities. Six QA in-process surveillances, which resulted in 71 observations, were performed at the Falls City site on the following dates: 22-24 July 1992, 23-25 November 1992, 17-19 May 1993, 16-18 August 1993, 13-15 October 1993, and 2-4 February 1994. All outstanding issues were closed out with the February surveillance on 3 March 1994. The DOE/TAC remedial action close-out inspections of the Falls City site, which resulted in 56 observations, were conducted 9-10 June 1994 and 26 July 1994. The inspections were closed out on 26 January 1995. The NRC performed three on-site construction reviews (OSCR), resulting in seven observations of remedial action construction activities that occurred during site visits. The OSCRs were performed 9 December 1992, 12 May 1993, and 25 October 1993. Since all audit and surveillance observations and recommendations have been closed out, this final audit report segment of the site certification process is complete

  9. SUMMARY OF TECHNIQUES AND UNIQUE USES FOR DIRECT PUSH METHODS IN SITE CHARACTERIZATION ON CONTAMINATED FIELD SITES

    Science.gov (United States)

    Site characterization of subsurface contaminant transport is often hampered by a lack of knowledge of site heterogeneity and temporal variations in hydrogeochemistry. Two case studies are reviewed to illustrate the utility of macro-scale mapping information along with spatially-...

  10. Site investigation - equipment for geological, geophysical, hydrogeological and hydrochemical characterization

    International Nuclear Information System (INIS)

    Almen, K.E.; Fridh, B.; Johansson, B.E.; Sehlstedt, M.

    1986-11-01

    The investigations are performed within a site investigation program. In total about 60,000 m of cored 56 mm boreholes have been drilled and investigated at eight study sites. A summarized description of the main investigation methods is included. Instruments for geophysical investigations contains equipment for ground measurements as well as for borehole logging. The Geophysical investigations including the borehole radar measurements, are indirect methods for the geological and hydrogeological characterization of the rock formation. Great effort has been laid on the development of hydrogeological instruments for hydraulic tests and groundwater head measurements. In order to obtain hydrochemical investigations with high quality, a complete system for sampling and analysis of ground water has been developed. (orig./PW)

  11. Site characterization and the method of multiple working hypotheses

    International Nuclear Information System (INIS)

    Fenster, D.F.; Cline, K.M.; Blair, J.A.; Stockey, J.

    1992-01-01

    Geologic investigations are necessary to determine whether a site is suitable for repository development and, if suitable, whether the site complies with regulatory requirements. Geologic processes and events often cannot be characterized without some degree of residual uncertainty. The method of multiple working hypotheses (MWH) is an approach in which alternative explanations for natural processes and/or events are identified, tested, and evaluated. This paper reports that in practice, several hypotheses may remain viable after all reasonable studies have been completed. Within the context of waste management and civil construction projects, all viable hypotheses that correspond with potential natural hazards must be analyzed in terms of adverse consequences to public health and safety, including radiological safety. For the repository licensing process, viable hypotheses remaining after the evaluation of data and quantification of uncertainty must be analyzed with regard to their consequences related to waste isolation. This approach can be used to determine whether additional studies are necessary to complete the license application

  12. Activities related to site characterization in ENRESA's research and development plan

    International Nuclear Information System (INIS)

    Olmo, C. del; Astudillo, J.; Bajos, C.; Hernan, P.

    1995-01-01

    Following a short introduction that summarizes the global strategy for high-level waste (HLW) disposal, an outline is given of the El Berrocal Project, with an emphasis on site characterization is given. The article focuses special attention on the technological developments achieved over the last few years within the framework of the ENRESA R and D Plans, both in global terms and within the El Berrocal project in particular, regarding the conception and construction of mobile hydrogeological and hydrogeochemical characterization units and the performance of tracer tests. These developments will make it possible to undertake, with slight modification and enhancements, the work required in the search for sites suitable for the definitive disposal of high-level radioactive wastes. A final section is devoted to presenting an overview of anticipated R and D actions for the five-year period 1995--1999

  13. Uranium characterization at the St. Louis Airport Site

    International Nuclear Information System (INIS)

    Schilk, A.J.; Hubbard, C.W.; Bowyer, T.W.; Reiman, R.T.

    1995-05-01

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

  14. Studies on site characterization methodologies for high level radioactive waste disposal

    International Nuclear Information System (INIS)

    Wang Ju; Guo Yonghai; Chen Weiming

    2008-01-01

    This paper presents the final achievement of the project 'Studies of Site-specific Geological Environment for High Level Waste Disposal and Performance Assessment Methodology, Part Ⅰ: Studies on Site Characterization Methodologies for High Level Radioactive Waste Disposal', which is a 'Key Scientific and Technological Pre-Research Project for National Defense' during 2001-2005. The study area is Beishan area, Gansu Province, NW China--the most potential site for China's underground research laboratory and high level radioactive waste repository. The boreholes BS01, BS2, BS03 and BS04 drilled in fractured granite media in Beishan are used to conduct comprehensive studies on site characterization methodologies, including: bore hole drilling method, in situ measurement methods of hydrogeological parameters, underground water sampling technology, hydrogeochemical logging method, geo-stress measurement method, acoustic borehole televiewer measurement method, borehole radar measurement method, fault stability evaluation methods and rock joint evaluation method. The execution of the project has resulted in the establishment of an 'Integrated Methodological System for Site Characterization in Granite Site for High Level Radioactive Waste Repository' and the 8 key methodologies for site characterization: bore hole drilling method with minimum disturbance to rock mass, measurement method for hydrogeological parameters of fracture granite mass, in situ groundwater sampling methods from bore holes in fractured granite mass, fracture measurement methods by borehole televiewer and bore radar system, hydrogeochemical logging, low permeability measurement methods, geophysical methods for rock mass evaluation, modeling methods for rock joints. Those methods are comprehensive, advanced, innovative, practical, reliable and of high accuracy. The comprehensive utilization of those methods in granite mass will help to obtain systematic parameters of

  15. Consultation draft: Site characterization plan overview, Deaf Smith County Site, Texas: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy (DOE) is preparing a site characterization plan for the candidate site in Deaf Smith County, Texas. The DOE has provided, for information and review, a consultation draft of the plan to the State of Texas and the US Nuclear Regulatory Commission. 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 repository system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Deaf Smith County site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons 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. 15 figs., 1 tab

  16. Repository site characterization and development - interaction with the public

    International Nuclear Information System (INIS)

    Beale, H.

    1993-01-01

    Radioactive waste management policy in the UK has a chequered past. Endeavours to develop new disposal facilities for radioactive waste have included consideration of green field sites and existing underground openings. Currently Nirex is implementing a programme of geological investigations at Sellafield, in Cumbria, and has brought forwards its plans for development there of an underground rock characterization facility (RCF). This paper reviews the evolution of UK radioactive waste management policy, since the 1970s, outlines the Company's current activities at Sellafield and points to the importance of interactions with the local community. 2 refs

  17. CCS acceptability: social site characterization and advancing awareness at prospective storage sites in Poland and Scotland

    International Nuclear Information System (INIS)

    Brunsting, Suzanne; Mastop, Jessanne; Kaiser, Marta; Zimmer, Rene; Shackley, Simon; Mabon, Leslie; Howell, Rhys

    2015-01-01

    This paper summarizes the work on the social dimension conducted within the EU FP7 SiteChar project. The most important aim of the research was to advance public awareness and draw lessons for successful public engagement activities when developing a CO 2 storage permit application. To this end, social site characterization (e.g. representative surveys) and public participation activities (focus conference) were conducted at two prospective Carbon Capture and Storage (CCS) sites: an onshore site in Poland and an offshore site in Scotland. The research consisted of four steps over a time period of 1.5 year, from early 2011 to mid-2012. The first step consisted of four related qualitative and quantitative research activities to provide a social characterization of the areas: desk research, stakeholder interviews, media analyses, and a survey among representative samples of the local community. The aim was to identify: - stakeholders or interested parties; - factors that may drive their perceptions of and attitudes towards CCS. Results were used to as input for the second step, in which a new format for public engagement named 'focus conferences' was tested at both sites involving a small sample of the local community. The third step consisted of making available generic as well as site-specific information to the general and local public, by: - setting up a bilingual set of information pages on the project web site suitable for a lay audience; - organizing information meetings at both sites that were open to all who took interest. The fourth step consisted of a second survey among a new representative sample of the local community. The survey was largely identical to the survey in step 1 to enable the monitoring of changes in awareness, knowledge and opinions over time. Results provide insight in the way local CCS plans may be perceived by the local stakeholders, how this can be reliably assessed at early stage without raising unnecessary concerns, and how

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

    Energy Technology Data Exchange (ETDEWEB)

    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))

    1991-09-01

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

  19. Final environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Summary

    International Nuclear Information System (INIS)

    1996-08-01

    This sitewide EIS evaluates the potential environmental impacts of four possible land-use alternatives being considered for the Nevada Test Site (NTS), the Tonopah Test Range, and the formerly operated DOE sites in the state of Nevada: the Project Shoal Area, the Central Nevada Test Area, and portions of the Nellis Air Force Range Complex. Three additional sites in Nevada-Eldorado Valley, Dry Lake Valley, and Coyote Spring Valley-are evaluated for collocation of solar energy production facilities. The four alternatives include Continue Current Operations (No Action, continue to operate at the level maintained for the past 3 to 5 years); Discontinue Operations 1 (discontinue operations and interagency programs); Expanded Use (increased use of NTS and its resources to support defense and nondefense programs); and Alternate Use of Withdrawn Lands (discontinue all defense-related activities at NTS; continue waste management operations in support of NTS environmental restoration efforts; expand nondefense research). Environmental impacts were assessed for each alternative by analyzing, to the extent possible, the discrete and cumulative environmental impacts associated with Defense Waste Management, Environmental Restoration, Nondefense Research and Development, and Work for Others Programs. A framework for a Resource Management Plan is included as Volume 2 of this EIS and represents the development of an ecosystem based planning process closely integrated with the National Environmental Policy Act process. This EIS, among other things, analyzed the impacts of transportation of low level waste, and site characterization activities related to the Yucca Mountain Project but did not analyze the suitability of the site as a repository. This EIS does not analyze the suitability of the Yucca Mountain site as a repository as this is an action beyond the scope of the EIS. Volume 3 of this EIS contains the public comments and the responses to the comments

  20. Site-selection studies for final disposal of spent fuel in Finland

    International Nuclear Information System (INIS)

    Vuorela, P.; Aeikaes, T.

    1984-02-01

    In the management of waste by the Industrial Power Company Ltd. (TVO) preparations are being made for the final disposal of unprocessed spent fuel into the Finnish bedrock. The site selection program will advance in three phases. The final disposal site must be made at the latest by the end of the year 2000, in accordance with a decision laid down by the Finnish Government. In the first phase, 1983-85, the main object is to find homogeneous stable bedrock blocks surrounded by fracture zones located at a safe distance from the planned disposal area. The work usually starts with a regional structural analysis of mosaics of Landsat-1 winter and summer imagery. Next an assortment of different maps, which cover the whole country, is used. Technical methods for geological and hydrogeological site investigations are being developed during the very first phase of the studies, and a borehole 1000 meters deep will be made in southwestern Finland. Studies for the final disposal of spent fuel or high-level reprocessing waste have been made since 1974 in Finland. General suitability studies of the bedrock have been going on since 1977. The present results indicate that suitable investigation areas for the final disposal of highly active waste can be found in Finland

  1. Fracture analysis and rock quality designation estimation for the Yucca Mountain Site Characterization Project; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-02-01

    Within the Yucca Mountain Site Characterization Project, the design of drifts and ramps and evaluation of the impacts of thermomechanical loading of the host rock requires definition of the rock mass mechanical properties. Ramps and exploratory drifts will intersect both welded and nonwelded tuffs with varying abundance of fractures. The rock mass mechanical properties are dependent on the intact rock properties and the fracture joint characteristics. An understanding of the effects of fractures on the mechanical properties of the rock mass begins with a detailed description of the fracture spatial location and abundance, and includes a description of their physical characteristics. This report presents a description of the abundance, orientation, and physical characteristics of fractures and the Rock Quality Designation in the thermomechanical stratigraphic units at the Yucca Mountain site. Data was reviewed from existing sources and used to develop descriptions for each unit. The product of this report is a data set of the best available information on the fracture characteristics.

  2. Site characterization at the Rabbit Valley Geophysical Performance Evaluation Range

    International Nuclear Information System (INIS)

    Koppenjan, S.; Martinez, M.

    1994-01-01

    The United States Department of Energy (US DOE) is developing a Geophysical Performance Evaluation Range (GPER) at Rabbit Valley located 30 miles west of Grand Junction, Colorado. The purpose of the range is to provide a test area for geophysical instruments and survey procedures. Assessment of equipment accuracy and resolution is accomplished through the use of static and dynamic physical models. These models include targets with fixed configurations and targets that can be re-configured to simulate specific specifications. Initial testing (1991) combined with the current tests at the Rabbit Valley GPER will establish baseline data and will provide performance criteria for the development of geophysical technologies and techniques. The US DOE's Special Technologies Laboratory (STL) staff has conducted a Ground Penetrating Radar (GPR) survey of the site with its stepped FM-CW GPR. Additionally, STL contracted several other geophysical tests. These include an airborne GPR survey incorporating a ''chirped'' FM-CW GPR system and a magnetic survey with a surfaced-towed magnetometer array unit Ground-based and aerial video and still frame pictures were also acquired. STL compiled and analyzed all of the geophysical maps and created a site characterization database. This paper discusses the results of the multi-sensor geophysical studies performed at Rabbit Valley and the future plans for the site

  3. Hydrogeologic characterization of an arid zone Radioactive Waste Management Site

    International Nuclear Information System (INIS)

    Ginanni, J.M.; O'Neill, L.J.; Hammermeister, D.P.; Blout, D.O.; Dozier, B.L.; Sully, M.J.; Johnejack, K.R.; Emer, D.F.; Tyler, S.W.

    1994-01-01

    An in-depth subsurface site characterization and monitoring program for the soil water migration pathway has been planned, implemented, and completed to satisfy data requirements for a waiver from groundwater monitoring, for an exemption from liner leachate collections systems, and for different regulatory driven performance assessments. A traditional scientific approach has been taken to focus characterization and monitoring efforts. This involved developing a conceptual model of the hydrogeologic system and defining and testing hypotheses about this model. Specific hypotheses tested included: that the system was hydrologically heterogenous and anisotropic, and that recharge was very low or negligible. Mineralogical, physical, and hydrologic data collected to test hypotheses has shown the hydrologic system to be remarkably homogenous and isotropic rather than heterogenous and anisotropic. Both hydrodynamic and environmental tracer approaches for estimating recharge have led to the conclusion that recharge from the Area 5 RWMS is not occurring in the upper region of the vadose zone, and that recharge at depth is extremely small or negligible. This demonstration of ''no migration of hazardous constituents to the water table satisfies a key requirement for both the groundwater monitoring waiver and the exemption from liner leachate collection systems. Data obtained from testing hypotheses concerning the soil water migration pathway have been used to refine the conceptual model of the hydrogeologic system of the site. These data suggest that the soil gas and atmospheric air pathways may be more important for transporting contaminants to the accessible environment than the soil water pathway. New hypotheses have been developed about these pathways, and characterization and monitoring activities designed to collect data to test these hypotheses

  4. Sites of Final Paleolithic and Mesolithic from the Chuvash Volga Region: the issue of cultural interpretation

    Directory of Open Access Journals (Sweden)

    Berezina Natalia S.

    2017-09-01

    Full Text Available The article features a comprehensive assessment of monuments dating back to the Final Paleolithic and Mesolithic periods located in the Chuvash Volga Region: topography, description of the structural aspects of studied dwellings, characteristics of the stone industry, bone articles, etc. All the described sites have deteriorated to a certain degree, and others have been lost completely. The author analyses all the available archaeological and natural scientific information, which suggests the cultural nature of the monuments. Sholma 1 site was presumably populated by wild horse hunters and related to the process of migration from the Forest-Steppe Area of the Lower Volga Region in the Final Paleolithic period. Monuments of the Mesolithic period located in the Chuvash Volga Region are linked by the author and other researchers to the cultural group of monuments with Post-Swiderian arrowheads and the Russko-Lugovskaya culture recently identified in the Mari Volga Region.

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

    International Nuclear Information System (INIS)

    Goranson, C.

    1992-09-01

    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

  6. Site investigations for final disposal of high-level nuclear waste

    International Nuclear Information System (INIS)

    Aeikaes, T.; Laine, T.

    1982-12-01

    Research concerning disposal of high-level nuclear waste of the Industrial Power Company Ltd has focused on deep underground disposal in Finnish precambrian bedrock. The present target is to have a repository for high-level waste in operation by 2020. Selection of the repository site is based on site investigations. In addition to geosciences, selection of appropriate site includes many branches of studies; engineering, safety analysis, ecology, transport, demography etc. The investigations required for site selection for high-level waste have been arranged in a sequence of four phases. The aim of the phases is that investigations become more and more detailed as the selection process continues. Phase I of the investigations is the characterization of potential areas. This comprises establishment of criteria for site selection and identification of areas that meet selection criteria. Objective of these studies is to determine areas for phase II field investigations. The studies are largely made by reviewing existing data and remote-sensing techniques. Phase II field investigations will be undertaken between 1986-1992. The number of potential candidates for repository site is reduced to few preferred areas by preceeding generic study. The site selection process culminates in phase III in site confirmation studies carried out at 2...3 most suitable sites during 1992-2010. This is then followed by phase IV, which comprises very detailed investigations at the selected site. An alternative for these investigations is to undertake them by using pilot shaft and drifts. Active development is taking place in all phases concerning investigation methods, criteria, parameters, data processing and modelling. The applicability of the various investigation methods and techniques is tested in a deep borehole in phase I. The co-operation with countries with similar geological conditions makes it possible to compare results obtained by different techniques

  7. Water Resources Research Program. Abatement of malodors at diked, dredged-material disposal sites. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, W.; Dravnieks, A.; Zussman, R.; Goltz, R.

    1976-06-01

    Samples of malodorous air and dredged material were collected at diked disposal sites at the following locations: Buffalo, NY; Milwaukee, WI; Mobile, AL; York Harbor, ME; Houston, TX; Detroit, MI; and Anacortes, WA; during the period July--October, 1975. Odorous compounds in the air samples were identified by gas chromatography/mass spectrometry, while the detection threshold, intensity, and character of the various odors were determined by experienced panelists using a dynamic, forced-choice-triangle olfactometer. Although significant problems with malodors were not observed beyond the disposal-area dikes during site visits, noteworthy odor episodes had occurred at some sites. An odor-abatement strategy is presented for handling the expected range of odor conditions at dredged-material disposal sites. Its aim is to reduce to an acceptable level the intensity of malodors in an affected community. The main steps in the strategy cover selection of the disposal site, site preparation, odor characterization of sediments to be dredged, malodor abatement during dredging and disposal operations, malodor abatement after filling of the disposal site, and the handling of malodor complaints.

  8. Final audit report of remedial action construction at the UMTRA Project Ambrosia Lake, New Mexico, site

    International Nuclear Information System (INIS)

    1995-09-01

    The final audit report for remedial action at the Ambrosia Lake, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project site consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and a QA final closeout inspection performed by the US Department of Energy (DOE) and the Technical Assistance Contractor (TAC). One radiological surveillance and three radiological audits were performed at the Ambrosia Lake site. The surveillance was performed on 12--16 April 1993 (DOE, 1993d). The audits were performed on 26--29 July 1993 (DOE, 1993b); 21--23 March 1994 (DOE, 1994d); and 1--2 August 1994 (DOE, 1994d). The surveillance and audits resulted in 47 observations. Twelve of the observations raised DOE concerns that were resolved on site or through subsequent corrective action. All outstanding issues were satisfactorily closed out on 28 December 1994. The radiological surveillance and audits are discussed in this report. A total of seven QA in-process surveillances were performed at the Ambrosia Lake UMTRA site are discussed. The DOE/TAC Ambrosia Lake final remedial action close-out inspection was conducted on 26 July 1995 (DOE, 1995a). To summarize, a total of 155 observations were noted during DOE/TAC audit and surveillance activities. Follow-up to responses required from the RAC for the DOE/TAC surveillance and audit observations indicated that all issues related to the Ambrosia Lake site were resolved and closed to the satisfaction of the DOE

  9. Final audit report of remedial action construction at the UMTRA Project, Grand Junction, Colorado, processing site

    International Nuclear Information System (INIS)

    1995-02-01

    This final audit report (FAR) for remedial action at the Grand Junction, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project processing site consists of a summary of the radiological surveillances/ audits, the quality assurance (QA) in-process surveillances, and the QA final close-out inspection performed by the US Department of Energy (DOE) and Technical Assistance Contractor (TAC). The FAR also summarizes other surveillances performed by the US Nuclear Regulatory Commission (NRC). To summarize, a total of one finding and 127 observations were noted during DOE/TAC audit and surveillance activities. The NRC noted general site-related observations during the OSCRs. Follow-up to responses required from MK-Ferguson for the DOE/TAC finding and observations indicated that all issues related to the Grand Junction processing site were resolved and closed out to the DOE's satisfaction. The NRC OSCRs resulted in no issues related to the Grand Junction processing site requiring a response from MK-Ferguson

  10. Final Hanford Comprehensive Land-Use Plan Environmental Impact Statement, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-10-01

    This Final ''Hanford Comprehensive Land-Use Plan Environmental Impact Statement'' (HCP EIS) is being used by the Department of Energy (DOE) and its nine cooperating and consulting agencies to develop a comprehensive land-use plan (CLUP) for the Hanford Site. The DOE will use the Final HCP EIS as a basis for a Record of Decision (ROD) on a CLUP for the Hanford Site. While development of the CLUP will be complete with release of the HCP EIS ROD, full implementation of the CLUP is expected to take at least 50 years. Implementation of the CLUP would begin a more detailed planning process for land-use and facility-use decisions at the Hanford Site. The DOE would use the CLUP to screen proposals. Eventually, management of Hanford Site areas would move toward the CLUP land-use goals. This CLUP process could take more than 50 years to fully achieve the land-use goals.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

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

    International Nuclear Information System (INIS)

    1988-01-01

    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

  13. Yucca Mountain Site Characterization Project Waste Package Plan

    International Nuclear Information System (INIS)

    Harrison-Giesler, D.J.; Jardine, L.J.

    1991-02-01

    The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package program is to develop, confirm the effectiveness of, and document a design for a waste package and associated engineered barrier system (EBS) for spent nuclear fuel and solidified high-level nuclear waste (HLW) that meets the applicable regulatory requirements for a geologic repository. The Waste Package Plan describes the waste package program and establishes the technical approach against which overall progress can be measured. It provides guidance for execution and describes the essential elements of the program, including the objectives, technical plan, and management approach. The plan covers the time period up to the submission of a repository license application to the US Nuclear Regulatory Commission (NRC). 1 fig

  14. Electrokinetic applications: Site characterization and remediation of soils

    International Nuclear Information System (INIS)

    Haupt, R.W.

    1995-01-01

    This paper summarizes the role of primary and secondary driving forces of pore fluid and contaminant transport in soils during electrokinetic applications. For site characterization, the coupling of pressure gradients (driving force) and electric current (secondary force) are discussed in terms of a 2-dimensional finite difference model for heterogeneous, porous media. The model can be used to determine flow orientation and delineate the spatial flow field. In soil remediation applications, transport is driven by primary electric fields. A computer model of solute transport driven by an applied electrical field was expanded to examine transient behavior of ionic mobilization due to electromigration, chemical diffusion, and fluid convection. An experiment demonstrating the transport of an anionic dye was compared to the model. Although the model appears to predict the transport of the dye, there are concerns that the model may not maintain reasonable electroneutrality throughout the modeled cell

  15. Environmental Monitoring and Mitigation Plan for site characterization:

    International Nuclear Information System (INIS)

    1988-01-01

    The DOE is committed to conduct its operations in an environmentally safe and sound manner, and will comply with the letter and the spirit of applicable environmental statues and regulations. This document - the NNWSI Project's Environmental Regulatory Compliance Plan (ERCP) - is one means of implementing the policy. The ERCP describes the plan by which the NNWSI Project Office will comply with applicable environmental statutes and regulations. The ERCP also discusses how DOE will address State and local environmental statues and regulations. To achieve the goals of DOE, the ERCP will be developed in phases. This version of the ERCP is the first phase in this development. It represents the NNWSI Project's understanding of environmental regulatory requirements for site characterization of Yucca Mountain. After consultation with appropriate Federal and State agencies, the ERCP will be updated to reflect the results of these consultations. 29 figs., 1 tab

  16. Wetlands Assessment for site characterization, Advanced Neutron Source (ANS)

    International Nuclear Information System (INIS)

    Wade, M.C.; Socolof, M.L.

    1994-10-01

    This Wetlands Assessment has been prepared in accordance with the Department of Energy's (DOE) Code of Federal Regulations (CFR) 10 CFR 1022, Compliance with Floodplain/Wetlands Environmental Review Requirements, which established the policy and procedure for implementing Executive Order 11990, Protection of Wetlands. The proposed action is to conduct characterization activities in or near wetlands at the ANS site. The proposed action will covered under a Categorical Exclusion, therefore this assessment is being prepared as a separate document [10 CFR 1022.12(c)]. The purpose of this Wetlands Assessment is to fulfill the requirements of 10 CFR 1022.12(a) by describing the project, discussing the effects of the proposed action upon the wetlands, and considering alternatives to the proposed action

  17. Wetlands Assessment for site characterization, Advanced Neutron Source (ANS)

    Energy Technology Data Exchange (ETDEWEB)

    Wade, M.C.; Socolof, M.L. [Oak Ridge National Lab., TN (United States). Energy Div.; Rosensteel, B.; Awl, D. [JAYCOR, Vienna, VA (United States)

    1994-10-01

    This Wetlands Assessment has been prepared in accordance with the Department of Energy`s (DOE) Code of Federal Regulations (CFR) 10 CFR 1022, Compliance with Floodplain/Wetlands Environmental Review Requirements, which established the policy and procedure for implementing Executive Order 11990, Protection of Wetlands. The proposed action is to conduct characterization activities in or near wetlands at the ANS site. The proposed action will covered under a Categorical Exclusion, therefore this assessment is being prepared as a separate document [10 CFR 1022.12(c)]. The purpose of this Wetlands Assessment is to fulfill the requirements of 10 CFR 1022.12(a) by describing the project, discussing the effects of the proposed action upon the wetlands, and considering alternatives to the proposed action.

  18. Characterization of muon and gamma radiations at the PTOLEMY site

    Science.gov (United States)

    Betts, Susannah; Gentile, Charles; Tully, Chris; Zapata, Sandra; Chris Tully Collaboration

    2013-10-01

    PTOLEMY is an experimental project at Princeton Plasma Physics Laboratory designed to determine the present day number density of relic neutrinos through measurement of electrons produced from neutrino capture on tritium. The weak interaction cross section for relic neutrino interactions necessitates high sensitivity measurements that could be influenced by high energy particles, like muons and gamma ray photons, which induce nuclear transitions and secondary electrons. Muons produced from the collision of cosmic rays with atmospheric nuclei are a significant source of background radiation at and below Earth's surface. The muon flux is measured by the coincidence of minimum ionization radiation loss in two plastic scintillator paddles. The spectrum of gamma ray photons is measured using sodium iodide based scintillators. These measurements will provide a characterization of the background and rates at the PTOLEMY site.

  19. Characterization of Reconsolidated Crushed Salt from the BAMBUS Site.

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Francis D.

    2016-03-01

    Observational petrofabrics, thermal, mechanical, and hydrological measurements were made on reconsolidated salt samples extracted from the field site in which a study called Backfilling and Sealing of Underground Repositories for Radioactive Waste in Salt was conducted. Similar characterization was completed more than a decade ago, so this work furthers previous measurements after sustained consolidation in situ . Porosity determined by traditional point-counting on polished sections and helium porosimeter methods ranged from 20-25% with consolidation governed by brittle processes, as evidence of fluid-aided, grain-boundary processes was rarely observed. Thermal conductivity in the range of 2.3 W /( m * K ) is consistent for granular halite in this porosity range. Gas flow measurements yielded permeability of the order of 5e -13 m 2 . Pressure-sensitive compressive strengths at 0.5, 1.0, and 2.0 MPa confining pressure were 8, 9, and 14 MPa, respectively, with apparent elastic moduli increase with deformation.

  20. Characterization of nuclear reactor containment penetrations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Shackelford, M.H.; Bump, T.R.; Seidensticker, R.W.

    1985-02-01

    This report concludes a preliminary report prepared by ANL for Sandia, published as NUREG/CR-3855, in June 1984. The preliminary report, NUREG/CR-3855, presented the results of a survey of nuclear reactor containment penetrations, covering the number of plants surveyed at that time (22 total). Since that time, an additional 26 plants have been included in the survey. This final report serves two purposes: (1) to add the summary data sheets and penetration details for the additional plants now included in the survey; and (2) to confirm, revise, or add to analyses and discussions presented in the first report which, of course, were based solely on the earlier sample of 22 plants. This final report follows the outline and format of the preliminary survey report. In general, changes and additions to the preliminary report are implied, rather than stated as such to avoid repeated reference to that report. If no changes have been made in a section the title of the section of the previous report is simply repeated followed by ''No Changes''. Some repetition is used for continuity and clarity.

  1. Characterization of nuclear reactor containment penetrations. Final report

    International Nuclear Information System (INIS)

    Shackelford, M.H.; Bump, T.R.; Seidensticker, R.W.

    1985-02-01

    This report concludes a preliminary report prepared by ANL for Sandia, published as NUREG/CR-3855, in June 1984. The preliminary report, NUREG/CR-3855, presented the results of a survey of nuclear reactor containment penetrations, covering the number of plants surveyed at that time (22 total). Since that time, an additional 26 plants have been included in the survey. This final report serves two purposes: (1) to add the summary data sheets and penetration details for the additional plants now included in the survey; and (2) to confirm, revise, or add to analyses and discussions presented in the first report which, of course, were based solely on the earlier sample of 22 plants. This final report follows the outline and format of the preliminary survey report. In general, changes and additions to the preliminary report are implied, rather than stated as such to avoid repeated reference to that report. If no changes have been made in a section the title of the section of the previous report is simply repeated followed by ''No Changes''. Some repetition is used for continuity and clarity

  2. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington site. Appendices E through W

    International Nuclear Information System (INIS)

    1983-03-01

    Volume 2 contains Appendices E through W: potential for large-scale pump tests in the Grande Ronde; review of hydrochemical characterization related to flow system interpretation in Hanford basalts; limitations of packer-testing for head evaluation in Hanford basalts; hydrogeologic data integration for conceptual groundwater flow models; drilling mud effects on hydrogeologic testing; site issue analyses related to the nature at the present groundwater system at the Hanford site, Washington; structural and stratigraphic characteristics related to groundwater flow at the Hanford site, Washington; seismic hazard and some examples of hazard studies at Hanford; earthquake swarms in the Columbia Plateau; seismic ground motion at depth; failure modes for the metallic waste package component; degradation mechanisms of borosilicate glass; transport and retardation of radionuclides in the waste package; determination and interpretation of redox conditions and changes in underground high-level repositories; determination and interpretation of sorption data applied to radionuclide migration in underground repositories; solubility of radionuclide compounds presented in the BWIP site characterization report; and release rate from engineered system

  3. Northeastern Regional geologic characterization report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Connecticut, Maine, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont. For each of the states within the Northeastern Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening. The geologic factor and variables include deep mines and quarries, rock mass extent, postemplacement faulting, suspected Quaternary faulting, seismicity, rock and mineral resources, major ground-water discharge zones, ground-water resources, state of stress, thickness of rock mass, and thickness of overburden. Information is presented on age, areal extent, shape, composition, texture, degree and type of alteration, thickness, and structural features associated with each rock body or complex. Regional seismic and tectonic information is presented, including patterns of earthquake occurrence, earthquake magnitudes, horizontal ground accelerations, and vertical crusal movements. Also included are discussions of the rock and mineral deposits or mines located within or near crystalline bodies; ground-water resources and regional hydrology; postulated changes in climate and the associated effects; and landforms, surface processes, and surficial materials on or near the rock bodies. A discussion is also presented on the relationship between the US Department of Energy (DOE) Siting Guidelines (10 CFR 960) and the geologic disqualifying factor and regional screening variables to be used in the region-to-area screening process

  4. North Central Regional geologic characterization report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the states within the North Central Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening. The geologic factor and variables include deep mines and quarries, rock mass extent, post-emplacement faulting, suspected Quaternary faulting, seismicity, rock and mineral resources, major groundwater discharge zones, groundwater resources, state of stress, thickness of rock mass, and thickness of overburden. Information is presented on age, areal extent, shape, composition, texture, degree and type of alteration, thickness, and structural features associated with each rock body or complex. Regional seismic and tectonic information is presented, including patterns of earthquake occurrence, earthquake magnitudes, horizontal ground accelerations, and vertical crustal movements. Also included are discussions of the rock and mineral deposits or mines located within or near crystalline rock bodies; groundwater resources and regional hydrology; postulated changes in climate and the associated effects; and landforms, surface processes, and surficial materials on or near the rock bodies. A discussion is also presented of the relationship between the US Department of Energy Siting Guidelines (10 CFR 960) and the geologic disqualifying factor and regional screening variables to be used in the region-to-area screening process. 43 figs., 15 tabs

  5. Technical procedures for ecology: Environmental field program, Deaf Smith County Site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including walkover surveys for threatened, endangered, or candidate species; vegetation classification and mapping; reclamation planning; wetland and floodplain determination and characterization of playas; wildlife habitat mapping methods; mammal sampling; bird survey methods; reptile and amphibian survey methods; preexisting environmental; stress and disturbance studies methods; voucher specimens for plants; and voucher specimens to wildlife. 9 refs., 5 figs., 1 tab

  6. Osteopontin: A uranium phosphorylated binding-site characterization

    International Nuclear Information System (INIS)

    Safi, Samir; Jeanson, Aurelie; Roques, Jerome; Simoni, Eric; Creff, Gaelle; Qi, Lei; Basset, Christian; Vidaud, Claude; Solari, Pier Lorenzo; Den Auwer, Christophe

    2013-01-01

    Herein, we describe the structural investigation of one possible uranyl binding site inside a non structured protein. This approach couples spectroscopy, thermodynamics, and theoretical calculations (DFT) and studies the interaction of uranyl ions with a phospho-peptide, thus mimicking a possible osteopontin (OPN) hydroxyapatite growth-inhibition site. Although thermodynamical aspects were investigated by using time-resolved laser fluorescence spectroscopy (TRLFS) and isothermal titration calorimetry (ITC), structural characterization was performed by extended X-ray absorption fine structure (EXAFS) at the U L(III)-edge combined with attenuated total reflection Fourier transform infrared (ATR-FTIR) spectroscopy. From the vibrational and fluorescence spectra, several structural models of a UO 2 2+ /peptide complex were developed and subsequently refined by using theoretical calculations to fit the experimental EXAFS obtained. The structural effect of the pH value was also considered under acidic to moderately acidic conditions (pH 1.5-5.5). Most importantly, the uranyl/peptide coordination environment was similar to that of the native protein. (authors)

  7. Final Report: Characterization of Canister Mockup Weld Residual Stresses

    Energy Technology Data Exchange (ETDEWEB)

    Enos, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-12-01

    Stress corrosion cracking (SCC) of interim storage containers has been indicated as a high priority data gap by the Department of Energy (DOE) (Hanson et al., 2012), the Electric Power Research Institute (EPRI, 2011), the Nuclear Waste Technical Review Board (NWTRB, 2010a), and the Nuclear Regulatory Commission (NRC, 2012a, 2012b). Uncertainties exist in terms of the environmental conditions that prevail on the surface of the storage containers, the stress state within the container walls associated both with weldments as well as within the base metal itself, and the electrochemical properties of the storage containers themselves. The goal of the work described in this document is to determine the stress states that exists at various locations within a typical storage canister by evaluating the properties of a full-diameter cylindrical mockup of an interim storage canister. This mockup has been produced using the same manufacturing procedures as the majority of the fielded spent nuclear fuel interim storage canisters. This document describes the design and procurement of the mockup and the characterization of the stress state associated with various portions of the container. It also describes the cutting of the mockup into sections for further analyses, and a discussion of the potential impact of the results from the stress characterization effort.

  8. Gulf of Mexico miocene CO₂ site characterization mega transect

    Energy Technology Data Exchange (ETDEWEB)

    Meckel, Timothy [Univ. of Austin, Austin, TX (United Staes); Trevino, Ramon [Univ. of Austin, Austin, TX (United Staes)

    2014-12-01

    This project characterized the Miocene-age sub-seafloor stratigraphy in the near-offshore portion of the Gulf of Mexico adjacent to the Texas coast. The large number of industrial sources of carbon dioxide (CO₂) in coastal counties and the high density of onshore urbanization and environmentally sensitive areas make this offshore region extremely attractive for long-term storage of carbon dioxide emissions from industrial sources (CCS). The study leverages dense existing geologic data from decades of hydrocarbon exploration in and around the study area to characterize the regional geology for suitability and storage capacity. Primary products of the study include: regional static storage capacity estimates, sequestration “leads” and prospects with associated dynamic capacity estimates, experimental studies of CO₂-brine-rock interaction, best practices for site characterization, a large-format ‘Atlas’ of sequestration for the study area, and characterization of potential fluid migration pathways for reducing storage risks utilizing novel high-resolution 3D (HR3D) seismic surveys. In addition, three subcontracted studies address source-to-sink matching optimization, offshore well bore management and environmental aspects. The various geologic data and interpretations are integrated and summarized in a series of cross-sections and maps, which represent a primary resource for any near-term commercial deployment of CCS in the area. The regional study characterized and mapped important geologic features (e.g., Clemente-Tomas fault zone, the regionally extensive Marginulina A and Amphistegina B confining systems, etc.) that provided an important context for regional static capacity estimates and specific sequestration prospects of the study. A static capacity estimate of the majority of the Study area (14,467 mi2) was estimated at 86 metric Gigatonnes. While local capacity estimates are likely to be lower due to reservoir-scale characteristics, the

  9. Site characterization and site response in Port-au-Prince, Haiti

    Science.gov (United States)

    Hough, Susan E.; Yong, Alan K.; Altidor, Jean Robert; Anglade, Dieuseul; Given, Douglas D.; Mildor, Saint-Louis

    2011-01-01

    Waveform analysis of aftershocks of the Mw7.0 Haiti earthquake of 12 January 2010 reveals amplification of ground motions at sites within the Cul de Sac valley in which Port-au-Prince is situated. Relative to ground motions recorded at a hard-rock reference site, peak acceleration values are amplified by a factor of approximately 1.8 at sites on low-lying Mio-Pliocene deposits in central Port-au-Prince and by a factor of approximately 2.5–3 on a steep foothill ridge in the southern Port-au-Prince metropolitan region. The observed amplitude, predominant periods, variability, and polarization of amplification are consistent with predicted topographic amplification by a steep, narrow ridge. A swath of unusually high damage in this region corresponds with the extent of the ridge where high weak-motion amplifications are observed. We use ASTER (Advanced Spaceborne Thermal Emission and Reflection Radiometer) imagery to map local geomorphology, including characterization of both near-surface and of small-scale topographic structures that correspond to zones of inferred amplification.

  10. Remedial action at the Acid/Pueblo Canyon site, Los Alamos, New Mexico. Final report

    International Nuclear Information System (INIS)

    1984-10-01

    The Acid/Pueblo Canyon site (TA-45) was designated in 1976 for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP). During the period 1943 to 1964 untreated and treated liquid wastes generated by nuclear weapons research activities at the Los Alamos Scientific Laboratory (LASL) were discharged into the two canyons. A survey of the site conducted by LASL in 1976 to 1977 identified two areas where radiological contamination exceeded criteria levels. The selected remedial action was based on extensive radiological characterization and comprehensive engineering assessments and comprised the excavation and disposal of 390 yd 3 of contaminated soil and rock. This document describes the background to the remedial action, the parties involved in administering and executing it, the chronology of the work, verification of the adequacy of the remedial action, and the cost incurred. 14 references, 5 figures, 5 tables

  11. Revegetation and rock cover for stabilization of inactive uranium mill tailings disposal sites. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Beedlow, P.A.

    1984-05-01

    Guidelines for using vegetation and rock to protect inactive uranium mill tailings from erosion were developed by Pacific Northwest Laboratory as part of the Department of Energy's Uranium Mill Tailings Remedial Action Project (UMTRAP) Technology Development program. Information on soils, climate, and vegetation were collected for 20 inactive tailings sites in the western United States. Sites were grouped according to similarities in climate and vegetation. Soil loss for those sites was characterized using the Universal Soil Loss Equation. Test plots were used to evaluate (1) the interaction between vegetation and sealant barrier systems and (2) the effects of surface rock on soil water and vegetation. Lysimeter and simulation studies were used to direct and support field experiments. 49 references, 17 figures, 16 tables.

  12. Revegetation and rock cover for stabilization of inactive uranium mill tailings disposal sites. Final report

    International Nuclear Information System (INIS)

    Beedlow, P.A.

    1984-05-01

    Guidelines for using vegetation and rock to protect inactive uranium mill tailings from erosion were developed by Pacific Northwest Laboratory as part of the Department of Energy's Uranium Mill Tailings Remedial Action Project (UMTRAP) Technology Development program. Information on soils, climate, and vegetation were collected for 20 inactive tailings sites in the western United States. Sites were grouped according to similarities in climate and vegetation. Soil loss for those sites was characterized using the Universal Soil Loss Equation. Test plots were used to evaluate (1) the interaction between vegetation and sealant barrier systems and (2) the effects of surface rock on soil water and vegetation. Lysimeter and simulation studies were used to direct and support field experiments. 49 references, 17 figures, 16 tables

  13. Advanced airborne geophysics for site and watershed characterization and remediation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, B.; Hodges, G. [Fugro Airborne Surveys, Mississauga, ON (Canada)

    2007-04-01

    Airborne geophysics systems now have the ability to make accurately map the conductivity of the earth's subsurface. This article provided details of various site characterization surveys conducted using helicopter electromagnetic (HEM) surveys. Recent improvements in computer software, the use of global positioning systems (GPS), lasers, and fiber optics have increased the ability of HEM systems to accurately map ground conditions. Airborne electromagnetic survey techniques were used to characterize the geological features and lithology of the Sulphur Bank Mercury Mine (SBMM) on the eastern shore of Clear Lake in California. Natural conduits for the movement of groundwater were identified. Data showed that acidic water and mercury from the mine were contaminating the lake. The data showed good agreement with results obtained from previous conventional geologic and hydrologic investigations. HEM surveys were also used to characterize conductive mine pools and groundwater plumes at areas in the eastern United States that contained abandoned surface and underground coal mines. HEM was used to delineate source areas and flow paths for acidic, metal-containing groundwater, and data obtained from the surveys were used to plan mitigation activities. The survey identified 11 mine pools, as well as flooded workings that had previously not been mapped. HEM surveys were also used to map water-bearing fractures in areas of crystalline bedrock in drought-ridden regions in Brazil. Information from the surveys was used to locate drill targets for water wells. A test survey was used to identify wellheads leaking methane in a privately-owned gas field in Wyoming. Five methane leakage plumes were detected as a result of the survey. HEM geophysical surveys have also been used to map conductivity variations due to changes in water salinity at the Biscayne aquifer in the Florida everglades. It was concluded that airborne and HEM surveys provide significant cost savings when

  14. Characterization of grinding wheels: An annotated Bibliography. Final report

    Energy Technology Data Exchange (ETDEWEB)

    McClung, R.W.

    1995-12-01

    The characteristics of grinding wheels, after both fabrication and periods of operation, have a significant effect on the processed surface and the mechanical properties of advanced ceramics. An extensive literature survey and review has been conducted to determine and catalogue the various characterization methods that have been investigated and reported. Although many of the references have addressed the grinding of metals, the historical and technical merit justify their inclusion in this bibliography. For convenience, the references have been subdivided into nine subheadings: Nondestructive examination; elasticity and stiffness; wheel hardness; topography and profilometry; observation of texture of wheel surfaces wheel wear; in process monitoring of grinding, acoustic emission, other; characteristics of ground surfaces; and miscellaneous.

  15. An Intelligent Systems Approach to Reservoir Characterization. Final Report

    International Nuclear Information System (INIS)

    Shahab D. Mohaghegh; Jaime Toro; Thomas H. Wilson; Emre Artun; Alejandro Sanchez; Sandeep Pyakurel

    2005-01-01

    Today, the major challenge in reservoir characterization is integrating data coming from different sources in varying scales, in order to obtain an accurate and high-resolution reservoir model. The role of seismic data in this integration is often limited to providing a structural model for the reservoir. Its relatively low resolution usually limits its further use. However, its areal coverage and availability suggest that it has the potential of providing valuable data for more detailed reservoir characterization studies through the process of seismic inversion. In this paper, a novel intelligent seismic inversion methodology is presented to achieve a desirable correlation between relatively low-frequency seismic signals, and the much higher frequency wireline-log data. Vertical seismic profile (VSP) is used as an intermediate step between the well logs and the surface seismic. A synthetic seismic model is developed by using real data and seismic interpretation. In the example presented here, the model represents the Atoka and Morrow formations, and the overlying Pennsylvanian sequence of the Buffalo Valley Field in New Mexico. Generalized regression neural network (GRNN) is used to build two independent correlation models between; (1) Surface seismic and VSP, (2) VSP and well logs. After generating virtual VSP's from the surface seismic, well logs are predicted by using the correlation between VSP and well logs. The values of the density log, which is a surrogate for reservoir porosity, are predicted for each seismic trace through the seismic line with a classification approach having a correlation coefficient of 0.81. The same methodology is then applied to real data taken from the Buffalo Valley Field, to predict inter-well gamma ray and neutron porosity logs through the seismic line of interest. The same procedure can be applied to a complete 3D seismic block to obtain 3D distributions of reservoir properties with less uncertainty than the geostatistical

  16. Final storage high-level radioactive waste in Sweden - the way to the 2009 siting decision

    International Nuclear Information System (INIS)

    Schneider, Horst

    2010-01-01

    In Sweden, high-level radioactive waste producing heat, i.e. spent fuel, is to be emplaced for final storage on the site of Forsmark, which also holds three reactor units. The siting decision was taken in June 2009. A 100 percent private company, a merger of the commercial nuclear power plant operators as producers of the waste, is responsible for the siting decision as well as for waste storage. Major impulses were given to the back-end fuel cycle policy in the early 1970s. Sweden practically gave up the reprocessing option very soon, but kept on pursuing final storage in deep geologic formations. Between 1977, when legislation was adopted with conditions relating to repository storage, and 2009, when the decision in favour of the Forsmark site was taken, the path followed was not always a straight line. The boundary conditions, such as the organization of the repository and procedural and safety criteria established by the government, are interesting with regard to their influence on the siting decision, if any. For this reason, the approaches chosen and their connections with government criteria and with geological conditions in Sweden, including their impacts on the repository concept chosen, will be examined. After a summary review of developments in Sweden, filing of the licensing application and the accompanying documents up to commissioning of the repository, a short comparison will be made with the situation in Germany, especially the status reached of the Gorleben salt dome, highlighting and evaluating important criteria and parameters. Sweden as a model is important especially in these respects: A repository site was found by a private company in consensus with the local government within the framework of government criteria, and with ultimate responsibility resting with the government; the local government of a place not winning the siting decision is disappointed although it will have the conditioning plant and receive higher grants; it was not only

  17. Characterize and Model Final Waste Formulations and Offgas Solids from Thermal Treatment Processes - FY-98 Final Report for LDRD 2349

    Energy Technology Data Exchange (ETDEWEB)

    Kessinger, Glen Frank; Nelson, Lee Orville; Grandy, Jon Drue; Zuck, Larry Douglas; Kong, Peter Chuen Sun; Anderson, Gail

    1999-08-01

    The purpose of LDRD #2349, Characterize and Model Final Waste Formulations and Offgas Solids from Thermal Treatment Processes, was to develop a set of tools that would allow the user to, based on the chemical composition of a waste stream to be immobilized, predict the durability (leach behavior) of the final waste form and the phase assemblages present in the final waste form. The objectives of the project were: • investigation, testing and selection of thermochemical code • development of auxiliary thermochemical database • synthesis of materials for leach testing • collection of leach data • using leach data for leach model development • thermochemical modeling The progress toward completion of these objectives and a discussion of work that needs to be completed to arrive at a logical finishing point for this project will be presented.

  18. Southeastern Regional geologic characterization report. Volume 1. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This report presents available geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in central Maryland; noncoastal Virginia, North Carolina, and South Carolina; and northern Georgia. For each of the states within the Southeastern Region, information is provided on the geological disqualifying factor and the geologic regional screening variables to be used in region-to-area screening. The geological factor and variables include deep mines and quarries, rock mass extent, postemplacement faulting, suspected Quaternary faulting, seismicity, rock and mineral resources, major ground-water discharge zones, ground-water resources, state of stress, thickness of rock mass, and thickness of overburden. Information is presented on the age, areal extent, shape, composition, texture, degree and type of alteration, thickness, and structural features associated with each rock body or complex. Regional seismic and tectonic information is presented, including patterns of earthquake occurrence, earthquake magnitudes, horizontal ground accelerations, and vertical crustal movements. Also included are discussions of the rock and mineral deposits or mines located within or near crystalline bodies; ground-water resources and regional hydrology; postulated changes in climate and the associated effects; and landforms, surface processes, and surficial materials on or near the rock bodies

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

    International Nuclear Information System (INIS)

    Holdaway, R.F.; Miller, J.W.; Sease, J.D.; Moses, R.J.; O'Connor, D.G.; Carrell, R.D.; Jaeger, C.D.; Thompson, M.L.; Strasser, A.A.

    1998-03-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

    1998-03-01

    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.

  1. Generation and Characterization of Attosecond Pulses. Final report

    International Nuclear Information System (INIS)

    Ian A. Walmsley; Robert W. Boyd

    2006-01-01

    The research undertaken in this project has been directed toward the area of attoscience, in particular the problem of attosecond metrology. That is, the accurate determination of the electric field of attosecond XUV radiation. This outstanding problem has been identified as a critical technology for further development of the field, and our research adds to the area by providing the first method for characterization using the harmonic radiation itself as a tool. The technical effectiveness of this approach is very high, since it is vastly easier to detect XUV radiation directly than via the spectrum of photoelectrons liberated from atoms by it. This means that the experimental data rate can be much higher in principle using all-optical detection that electron detection, which will greatly aid the utility of harmonic XUV sources in attoscience applications. There are as yet no direct public benefits from this area of scientific research, though access to material structural dynamics on unprecedented brief timescales are expected to yield significant benefits for the future

  2. Area Completion Strategies at Savannah River Site: Characterization for Closure and Beyond

    International Nuclear Information System (INIS)

    Bagwell, Laura; O'Quinn, Sadika; Amidon, Mark

    2008-01-01

    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 1990's, the site's primary missions became waste site closure, environmental restoration, and deactivation and decommissioning (D and 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: - unites several discrete waste units into one conceptual model, - integrates historically disparate environmental characterization and D and D activities - reduces the number of required regulatory documents, - and, in some cases, compresses schedules for achieving a stakeholder-approved end-state. The area completion approaches being implemented at SRS reflect an evolution of the traditional RCRA/ CERCLA remedial process. Area completion strategies: - group waste units and/or D and D facilities together for characterization, remediation, and possible reuse; - identify data needs and integrate data collection activities for D and D, characterization, and remediation; - identify problems that require action

  3. Final Review of Safety Assessment Issues at Savannah River Site, August 2011

    Energy Technology Data Exchange (ETDEWEB)

    Napier, Bruce A.; Rishel, Jeremy P.; Bixler, Nathan E.

    2011-12-15

    At the request of Savannah River Nuclear Solutions (SRNS) management, a review team composed of experts in atmospheric transport modeling for environmental radiation dose assessment convened at the Savannah River Site (SRS) on August 29-30, 2011. Though the meeting was prompted initially by suspected issues related to the treatment of surface roughness inherent in the SRS meteorological dataset and its treatment in the MELCOR Accident Consequence Code System Version 2 (MACCS2), various topical areas were discussed that are relevant to performing safety assessments at SRS; this final report addresses these topical areas.

  4. Aerosol characterization at the Saharan AERONET site Tamanrasset

    Science.gov (United States)

    Guirado, C.; Cuevas, E.; Cachorro, V. E.; Toledano, C.; Alonso-Pérez, S.; Bustos, J. J.; Basart, S.; Romero, P. M.; Camino, C.; Mimouni, M.; Zeudmi, L.; Goloub, P.; Baldasano, J. M.; de Frutos, A. M.

    2014-11-01

    More than 2 years of columnar atmospheric aerosol measurements (2006-2009) at the Tamanrasset site (22.79° N, 5.53° E, 1377 m a.s.l.), in the heart of the Sahara, are analysed. Aerosol Robotic Network (AERONET) level 2.0 data were used. The KCICLO (K is the name of a constant and ciclo means cycle in Spanish) method was applied to a part of the level 1.5 data series to improve the quality of the results. The annual variability of aerosol optical depth (AOD) and Ångström exponent (AE) has been found to be strongly linked to the convective boundary layer (CBL) thermodynamic features. The dry-cool season (autumn and winter) is characterized by a shallow CBL and very low mean turbidity (AOD ~ 0.09 at 440 nm, AE ~ 0.62). The wet-hot season (spring and summer) is dominated by high turbidity of coarse dust particles (AE ~ 0.28, AOD ~ 0.39 at 440 nm) and a deep CBL. The aerosol-type characterization shows desert mineral dust as the prevailing aerosol. Both pure Saharan dust and very clear sky conditions are observed depending on the season. However, several case studies indicate an anthropogenic fine mode contribution from the industrial areas in Libya and Algeria. The concentration weighted trajectory (CWT) source apportionment method was used to identify potential sources of air masses arriving at Tamanrasset at several heights for each season. Microphysical and optical properties and precipitable water vapour were also investigated.

  5. Ground Characterization Studies in Canakkale Pilot Site of LIQUEFACT Project

    Science.gov (United States)

    Ozcep, F.; Oztoprak, S.; Aysal, N.; Bozbey, I.; Tezel, O.; Ozer, C.; Sargin, S.; Bekin, E.; Almasraf, M.; Cengiz Cinku, M.; Ozdemir, K.

    2017-12-01

    The our aim is to outline the ground characterisation studies in Canakkale test site. Study is based on the EU H2020 LIQUEFACT project entitled "Liquefact: Assessment and mitigation of liquefaction potential across Europe: a holistic approach to protect structures / infrastructures for improved resilience to earthquake-induced liquefaction disasters". Objectives and extent of ground characterization for Canakkale test site includes pre-existing soil investigation studies and complementary field studies. There were several SPT and geophysical tests carried out in the study area. Within the context of the complementary tests, six (6) study areas in the test site were chosen and complementary tests were carried out in these areas. In these areas, additional boreholes were opened and SPT tests were performed. It was decided that additional CPT (CPTU and SCPT) and Marchetti Dilatometer (DMT) tests should be carried out within the scope of the complementary testing. Seismic refraction, MASW and micro tremor measurements had been carried out in pre-existing studies. Shear wave velocities obtained from MASW measurements were evaluated to the most rigorous level. These tests were downhole seismic, PS-logging, seismic refraction, 2D-ReMi, MASW, micro tremor (H/V Nakamura method), 2D resistivity and resonance acoustic profiling (RAP). RAP is a new technique which will be explained briefly in the relevant section. Dynamic soil properties had not been measured in pre-existing studies, therefore these properties were investigated within the scope of the complementary tests. Selection of specific experimental tests of the complementary campaign was based on cost-benefit considerations Within the context of complementary field studies, dynamic soil properties were measured using resonant column and cyclic direct shear tests. Several sieve analyses and Atterberg Limits tests which were documented in the pre-existing studies were evaluated. In the complementary study carried out

  6. Tri-Service Site Characterization and Analysis Penetrometer System (SCAPS) Validation of the Hydrosparge Volatile Organic Compound Sensor

    National Research Council Canada - National Science Library

    Davis, William

    2001-01-01

    Site characterization for subsurface contaminants is time consuming and costly. The Hydrosparge VOC sensor was developed for the Tri-Services Site characterization and Analysis Penetrometer System (SCAPS...

  7. Preliminary site characterization at Beishan northwest China-A potential site for China's high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Wang Ju; Su Rui; Xue Weiming; Zheng Hualing

    2004-01-01

    Chinese nuclear power plants,radioactive waste and radioactive waste disposal are introduced. Beishan region (Gansu province,Northwest China)for high-level radioactive waste repository and preliminary site characterization are also introduced. (Zhang chao)

  8. Comprehensive characterization of atmospheric organic carbon at a forested site

    Science.gov (United States)

    Hunter, James F.; Day, Douglas A.; Palm, Brett B.; Yatavelli, Reddy L. N.; Chan, Arthur W. H.; Kaser, Lisa; Cappellin, Luca; Hayes, Patrick L.; Cross, Eben S.; Carrasquillo, Anthony J.; Campuzano-Jost, Pedro; Stark, Harald; Zhao, Yunliang; Hohaus, Thorsten; Smith, James N.; Hansel, Armin; Karl, Thomas; Goldstein, Allen H.; Guenther, Alex; Worsnop, Douglas R.; Thornton, Joel A.; Heald, Colette L.; Jimenez, Jose L.; Kroll, Jesse H.

    2017-10-01

    Atmospheric organic compounds are central to key chemical processes that influence air quality, ecological health, and climate. However, longstanding difficulties in predicting important quantities such as organic aerosol formation and oxidant lifetimes indicate that our understanding of atmospheric organic chemistry is fundamentally incomplete, probably due in part to the presence of organic species that are unmeasured using standard analytical techniques. Here we present measurements of a wide range of atmospheric organic compounds--including previously unmeasured species--taken concurrently at a single site (a ponderosa pine forest during summertime) by five state-of-the-art mass spectrometric instruments. The combined data set provides a comprehensive characterization of atmospheric organic carbon, covering a wide range in chemical properties (volatility, oxidation state, and molecular size), and exhibiting no obvious measurement gaps. This enables the first construction of a measurement-based local organic budget, highlighting the high emission, deposition, and oxidation fluxes in this environment. Moreover, previously unmeasured species, including semivolatile and intermediate-volatility organic species (S/IVOCs), account for one-third of the total organic carbon, and (within error) provide closure on both OH reactivity and potential secondary organic aerosol formation.

  9. Analysis of the portfolio of sites to characterize for selecting a nuclear repository

    International Nuclear Information System (INIS)

    Keeney, R.L.

    1987-01-01

    The US Department of Energy has selected three sites, from five nominated, to characterize for a nuclear repository to permanently dispose of nuclear waste. This decision was made without the benefit of an analysis of this portfolio problem. This paper analyzes different portfolios of three sites for simultaneous characterization and strategies for sequential characterization. Characterization of each site, which involves significant subsurface excavation, is now estimated to cost $1 billion. Mainly because of the high characterization costs, sequential characterization strategies are identified which are the equivalent of $1.7-2.0 billion less expensive than the selected DOE simultaneous characterization of the three sites. If three sites are simultaneously characterized, one portfolio is estimated to be the equivalent of $100-400 million better than the selected DOE portfolio. Because of these potential savings and several other complicating factors that may influence the relative desirability of characterization strategies, a thorough analysis of characterization strategies that addresses the likelihood of finding disqualifying conditions during site characterization, uncertainties, and dependencies in forecast site repository costs, preclosure and postclosure health and safety impacts, potential delays of both sequential and simultaneous characterization strategies, and the environmental, socioeconomic, and health and safety impacts of characterization activities is recommended

  10. Final audit report of remedial action construction at the UMTRA Project Site, Gunnison, Colorado. Revision 0

    International Nuclear Information System (INIS)

    1996-01-01

    The final audit report for remedial action at the Gunnison, Colorado Uranium Mill Tailings Remedial Action (UMTRA) Project site consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and QA remedial action close-out inspections performed by the U.S. Department of Energy (DOE) and the Technical Assistance Contractor (TAC); and on-site construction reviews (OSCR) performed by the U.S. Nuclear Regulatory Commission (NRC). Two radiological surveillances and four radiological audits were performed at the Gunnison site. The surveillances were performed on 16 to 19 September 1992 and 28 June to 1 July 1993. The radiological audits were performed on 4 to 7 October 1993; 13 to 16 June 1994; 19 to 22 September 1994 and 10 to 12 July 1995. The surveillances and audits resulted in 79 observations. Thirty-four of the observations raised DOE concerns that were resolved on the site or through subsequent corrective action. All outstanding issues were closed on 12 July 1995. The radiological surveillances and audits are discussed in Section 2.0 of this report. Ten QA in-process surveillances were performed at the Gunnison UMTRA Project site. The surveillances were performed on 24 to 25 September 1992, 7 to 9 July 1993, 29 October 1993, 27 to 28 June 1994, 31 October to 1 November 1994, 19 to 20 June 1 995, 20 to 21 July 1995, 17 to 18 August 1995, 20 September 1995, and 11 to 13 October 1995. The surveillances resulted in 100 observations. Six observations contained recommendations that required responses from the Remedial Action Contractor (RAC). Ninety-five observations contained a recommendation that required no response. All outstanding issues were closed on 8 January 1996. The QA in-process surveillances are discussed in Section 3.0 of this report

  11. 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

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    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.

  12. Site and Event Characterization Using the CTBT On-Site Inspection Techniques (Invited)

    Science.gov (United States)

    Labak, P.; Gaya Pique, L. R.; Rowlands, A. P.; Arndt, R. H.

    2013-12-01

    One of the four elements of the CTBT verification regime is On-Site Inspection (OSI). The sole purpose of an OSI is to clarify whether a nuclear weapon test explosion or any other nuclear explosion has been conducted in violation of the CTBT. An OSI would be conducted within an area no bigger than 1000 km2 and by no more than 40 inspectors at any one time, applying search logic and inspection techniques with the aim of collecting relevant information that will be the basis for the inspection report. During the course of an OSI less intrusive techniques applied over broad areas (usually with lower spatial resolution) are supplemented with more intrusive techniques applied to more targeted areas (usually at a higher spatial resolution). Environmental setting and the evolution of OSI-relevant observables over time will influence the application of OSI techniques. In the course of the development of OSI methodology and relevant techniques, field tests and exercises have been conducted. While earlier activities mainly focused on progress of individual techniques (such as visual observation, passive seismological monitoring for aftershocks and measurements of radioactivity), recent work covered both technique development (such as multi-spectral imaging including infrared measurements, and environmental sampling and analysis of solids, liquids and gases) as well as the integration of techniques, search logic and data flow. We will highlight examples of application of OSI technologies for site and event characterization from recently conducted field tests and exercises and demonstrate the synthesis of techniques and data necessary for the conduct of an OSI.

  13. Characterizing the Environmental Availability of Trace Metals in Savannah River Site Soils

    Energy Technology Data Exchange (ETDEWEB)

    Serkiz, S.M.

    1999-03-18

    An eight step sequential extraction technique was used to characterize the environmental availability of trace metals from background and waste site soil samples collected from the US Department of Energy's Savannah River Site (SRS).

  14. A potential Italian CCS site: site characterization and monitoring of Sulcis Basin (Sardinia).

    Science.gov (United States)

    Chiara Tartarello, Maria; Bigi, Sabina; Beaubien, Stanley Eugene; De Angelis, Davide; Graziani, Stefano; Lombardi, Salvatore; Sacco, Pietro; Ruggiero, Livio

    2017-04-01

    The Sulcis Basin is an area situated in SW Sardinia (Italy) and is a potential site for the implementation of CCS in Italy. In fact, in the last years many studies were conducted to characterize the area and to define the baseline. The "Miliolitico" has been identified as the potential reservoir and is composed by fractured carbonate, while the "Produttivo Fm.", a sequence of clay, coal and marl, is the caprock. Above the "Produttivo Fm." there is a thick volcanic sequence (more than 800 m) that could be considered also a secondary caprock. In the area of Matzaccara, the "Miliolitico" is below an alluvial plain and it is estimates that could reach a depth of more than 800 m. To characterize the reservoir-caprock system there were conducted an extensive structural-geological survey, and more in detail a fracture analysis on all the Formation at the outcrop. With regard to the faults, it has been examined their architecture, and in particular the conduit-barrier behaviors. Moreover, to evaluate the theoretical capacity of the potential reservoir, we built a Discrete Fracture Model, using the fracture data collected at outcrop. So, we estimate a secondary porosity of about 3%. As regards to the definition of geochemical baseline, it has been conducted both discontinuous and continuous monitoring of CO2 and other gases. More in details, there were carried out a regional and a detailed survey, measuring the concentration and the flux of CO2. in that manner, it has been possible to identify potential migration pathways along faults and to define the position of continuous monitoring station. We developed small, low-power consuming, low-cost pCO2 "GasPro", to measure the CO2 both in soil and water. In the next months, it is planned to extend the monitoring network and to inject a little quantity of CO2 along a fault in the Matzaccara plain.

  15. Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

    International Nuclear Information System (INIS)

    Gwin, Jeremy; Frenette, Douglas

    2010-01-01

    This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 - Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or ''clean,'' building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, ''Final Status Survey Plan for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201'') was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one

  16. Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Jeremy Gwin and Douglas Frenette

    2010-09-30

    This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room

  17. Using pre-screening methods for an effective and reliable site characterization at megasites

    DEFF Research Database (Denmark)

    Nielsen, Mette Algreen; Kalisz, Mariusz; Stalder, Marcel

    2015-01-01

    This paper illustrates the usefulness of prescreeningmethods for an effective characterization of pollutedsites. We applied a sequence of site characterization methodsto a former Soviet military airbase with likely fuel and benzene,toluene, ethylbenzene, and xylene (BTEX) contaminationin shallow...

  18. Final Report: Cathode Catalysis in Hydrogen/Oxygen Fuel Cells: New Catalysts, Mechanism, and Characterization

    Energy Technology Data Exchange (ETDEWEB)

    Gewirth, Andrew A. [Univ. of Illinois, Urbana, IL (United States). Dept. of Chemistry; Kenis, Paul J. [Univ. of Illinois, Urbana, IL (United States). Dept. of Chemical and Biomolecular Engineering; Nuzzo, Ralph G. [Univ. of Illinois, Urbana, IL (United States). Dept. of Chemistry; Rauchfuss, Thomas B. [Univ. of Illinois, Urbana, IL (United States). Dept. of Chemistry

    2016-01-18

    In this research, we prosecuted a comprehensive plan of research directed at developing new catalysts and new understandings relevant to the operation of low temperature hydrogen-oxygen fuel cells. The focal point of this work was one centered on the Oxygen Reduction Reaction (ORR), the electrochemical process that most fundamentally limits the technological utility of these environmentally benign energy conversion devices. Over the period of grant support, we developed new ORR catalysts, based on Cu dimers and multimers. In this area, we developed substantial new insight into design rules required to establish better ORR materials, inspired by the three-Cu active site in laccase which has the highest ORR onset potential of any material known. We also developed new methods of characterization for the ORR on conventional (metal-based) catalysts. Finally, we developed a new platform to study the rate of proton transfer relevant to proton coupled electron transfer (PCET) reactions, of which the ORR is an exemplar. Other aspects of work involved theory and prototype catalyst testing.

  19. Seismic site-response characterization of high-velocity sites using advanced geophysical techniques: application to the NAGRA-Net

    Science.gov (United States)

    Poggi, V.; Burjanek, J.; Michel, C.; Fäh, D.

    2017-08-01

    The Swiss Seismological Service (SED) has recently finalised the installation of ten new seismological broadband stations in northern Switzerland. The project was led in cooperation with the National Cooperative for the Disposal of Radioactive Waste (Nagra) and Swissnuclear to monitor micro seismicity at potential locations of nuclear-waste repositories. To further improve the quality and usability of the seismic recordings, an extensive characterization of the sites surrounding the installation area was performed following a standardised investigation protocol. State-of-the-art geophysical techniques have been used, including advanced active and passive seismic methods. The results of all analyses converged to the definition of a set of best-representative 1-D velocity profiles for each site, which are the input for the computation of engineering soil proxies (traveltime averaged velocity and quarter-wavelength parameters) and numerical amplification models. Computed site response is then validated through comparison with empirical site amplification, which is currently available for any station connected to the Swiss seismic networks. With the goal of a high-sensitivity network, most of the NAGRA stations have been installed on stiff-soil sites of rather high seismic velocity. Seismic characterization of such sites has always been considered challenging, due to lack of relevant velocity contrast and the large wavelengths required to investigate the frequency range of engineering interest. We describe how ambient vibration techniques can successfully be applied in these particular conditions, providing practical recommendations for best practice in seismic site characterization of high-velocity sites.

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

    International Nuclear Information System (INIS)

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

    2001-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-05-01

    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.

  2. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume VI

    International Nuclear Information System (INIS)

    1996-08-01

    The U.S. Department Of Energy and the Washington State Department of Ecology added Appendix L (Volume 6), Response to Public Comments, to the Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington, to fully address and respond to public comments on the Draft EIS. In addition, DOE considered public comments, along with other factors such as programmatic need, short- and long-term impacts, technical feasibility, and cost, in arriving at DOE's preferred alternative. During the public comment period for the Draft EIS, more than 350 individuals, agencies, Tribal Nations, and organizations provided comments. This volume represents a broad spectrum of private citizens; businesses; local, State, and Federal officials; Tribal Nations; and public interest groups

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

    International Nuclear Information System (INIS)

    Neitzel, D.A.; Fosmire, C.J.; Fowler, R.A.

    1998-09-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-09-01

    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.

  5. Final Phase II report : QuickSite(R) investigation, Everest, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M. (Environmental Research)

    2003-11-01

    this reason, the CCC/USDA is conducting an environmental site investigation to determine the source(s) and extent of the carbon tetrachloride contamination at Everest and to assess whether the contamination requires remedial action. The investigation at Everest is being performed by the Environmental Research Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by the University of Chicago for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an interagency agreement with DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. At these facilities, Argonne is applying its QuickSite{reg_sign} environmental site characterization methodology. This methodology has been applied successfully at a number of former CCC/USDA facilities in Kansas and Nebraska and has been adopted by the American Society for Testing and Materials (ASTM 1998) as standard practice for environmental site characterization. Phase I of the QuickSite{reg_sign} investigation examined the key geologic, hydrogeologic, and hydrogeochemical relationships that define potential contaminant migration pathways at Everest (Argonne 2001). Phase II of the QuickSite{reg_sign} investigation at Everest was undertaken with the primary goal of delineating and improving understanding of the distribution of carbon tetrachloride contamination in groundwater at this site and the potential source area(s) that might have contributed to this contamination. To address this goal, four specific technical objectives were developed to guide the Phase II field studies. Sampling of near-surface soils at the former Everest CCC/USDA facility that was originally planned for Phase I had to be postponed until October 2000 because of access restrictions. Viable vegetation was not available for sampling then. This period is termed the first session of Phase II

  6. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume I

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 1 of the Final Environmental Impact Statement, analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  7. Issuance of Final Guidance: Ecological Risk Assessment and Risk Management Principles for Superfund Sites, October 7, 1999

    Science.gov (United States)

    This guidance is intended to help Superfund risk managers make ecological risk management decisions that are based on sound science, consistent across Regions, and present a characterization of site risks that is transparent to the public.

  8. Lower Columbia River and Estuary Ecosystem Restoration Program Reference Site Study: 2011 Restoration Analysis - FINAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Borde, Amy B.; Cullinan, Valerie I.; Diefenderfer, Heida L.; Thom, Ronald M.; Kaufmann, Ronald M.; Zimmerman, Shon A.; Sagar, Jina; Buenau, Kate E.; Corbett, C.

    2012-05-31

    The Reference Site (RS) study is part of the research, monitoring, and evaluation (RME) effort developed by the Action Agencies (Bonneville Power Administration [BPA], U.S. Army Corps of Engineers, Portland District [USACE], and U.S. Bureau of Reclamation) in response to Federal Columbia River Power System (FCRPS) Biological Opinions (BiOp). While the RS study was initiated in 2007, data have been collected at relatively undisturbed reference wetland sites in the LCRE by PNNL and collaborators since 2005. These data on habitat structural metrics were previously summarized to provide baseline characterization of 51 wetlands throughout the estuarine and tidal freshwater portions of the 235-km LCRE; however, further analysis of these data has been limited. Therefore, in 2011, we conducted additional analyses of existing field data previously collected for the Columbia Estuary Ecosystem Restoration Program (CEERP) - including data collected by PNNL and others - to help inform the multi-agency restoration planning and ecosystem management work underway in the LCRE.

  9. 10 CFR 60.18 - Review of site characterization activities. 2

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Review of site characterization activities. 2 60.18 Section 60.18 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES... Atomic Energy Act of 1954, as amended. Accordingly, neither the issuance of a site characterization...

  10. Fast-turnaround RCRA site characterization of former TA-42 at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pratt, A.R.; Gainer, G.M.; Thomson, C.N.; Hutton, R.D.

    1994-01-01

    This report describes the results of an accelerated characterization to evaluate contamination at the site of former Technical Area (TA)-42. This characterization supported the construction validation for the Nuclear Safeguards Technology Laboratory (NSTL), which will be constructed at the site

  11. 10 CFR 63.16 - Review of site characterization activities. 2

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Review of site characterization activities. 2 63.16 Section 63.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES... recommendations or stating objections to DOE's site characterization program. The Director shall invite public...

  12. Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement Richland, Washington

    International Nuclear Information System (INIS)

    Collins, M.S.; Borgstrom, C.M.

    2004-01-01

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices at the Hanford Site. The HSW EIS updates analyses of environmental consequences from previous documents and provides evaluations for activities that may be implemented consistent with the Waste Management Programmatic Environmental Impact Statement (WM PEIS) Records of Decision (RODs). Waste types considered in the HSW EIS include operational low-level radioactive waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and transuranic (TRU) waste (including TRU mixed waste). MLLW contains chemically hazardous components in addition to radionuclides. Alternatives for management of these wastes at the Hanford Site, including the alternative of No Action, are analyzed in detail. The LLW, MLLW, and TRU waste alternatives are evaluated for a range of waste volumes, representing quantities of waste that could be managed at the Hanford Site. A single maximum forecast volume is evaluated for ILAW. The No Action Alternative considers continuation of ongoing waste management practices at the Hanford Site and ceasing some operations when the limits of existing capabilities are reached. The No Action Alternative provides for continued storage of some waste types. The other alternatives evaluate expanded waste management practices including treatment and disposal of most wastes. The potential environmental consequences of the alternatives are generally similar. The major differences occur with respect to the consequences of disposal versus continued storage and with respect to the range of waste volumes managed under the alternatives. DOE's preferred alternative is to dispose of LLW, MLLW, and ILAW in a single, modular, lined facility near PUREX on Hanford's Central Plateau; to treat MLLW using a combination of onsite and

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    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.

  15. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    International Nuclear Information System (INIS)

    1988-12-01

    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

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

    International Nuclear Information System (INIS)

    1988-12-01

    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

  17. Applications of geochemical modeling to site characterization and radionuclide transport in the NNWSI project

    International Nuclear Information System (INIS)

    Kerrisk, J.F.

    1985-01-01

    The Nevada Nuclear Waste Storage Investigations project (NNWSI) is studying a site at Yucca Mountain, in southern Nevada, as a possible nuclear waste repository. Los Alamos National Laboratory is responsible for the geochemical aspects of site characterization at Yucca Mountain. Geochemical models are being used in site characterization to help understand (a) local water chemistry, (b) local mineralogy, (c) the relation between water chemistry and mineralogy, and (d) the effects of water chemistry and mineralogy on waste-element solubility and transport

  18. Corrective Action Investigation Plan for the CNTA Subsurface Sites (CAU Number 443), Revision 1; FINAL

    International Nuclear Information System (INIS)

    1999-01-01

    This Corrective Action Investigation Plan (CAIP) describes the U.S. Department of Energy's (DOE's) planned environmental investigation of the subsurface Central Nevada Test Area (CNTA) Corrective Action Unit (CAU) No. 443. The CNTA is located in Hot Creek Valley in Nye County, Nevada, adjacent to U.S. Highway 6, about 48 kilometers (km) (30 miles[mi]) north of Warm Springs, Nevada. The CNTA was the site of Project Faultless, a nuclear device detonated in the subsurface by the U.S. Atomic Energy Commission (AEC) in January 1968. The purposes of this test were to gauge the seismic effects of a relatively large, high-yield detonation completed in Hot Creek Valley (outside the Nevada Test Site) and to determine the suitability of the site for future large detonations. The yield of the Faultless test was between 200 kilotons and 1 megaton. Two similar tests were planned for the CNTA, but neither of them was completed. Based on the general definition of a corrective action investigation (CAI) from Section IV.14 of the Federal Facility Agreement and Consent Order (FFACO), the purpose of the CAI is ''to gather data sufficient to characterize the nature, extent, and rate of migration or potential rate of migration from releases or discharges of pollutants or contaminants and/or potential releases or discharges from corrective action units identified at the facilities''. For CNTA CAU 443 the concepts developed for the Underground Test Area (UGTA) CAUs will be applied on a limited scale. For the UGTA CAUs, ''the objective of the CAI process is to define boundaries around each UGTA CAU that establish areas that contain water that may be unsafe for domestic and municipal use,'' as stated in Appendix VI of the FFACO (1996). Based on this strategy the CAI for CAU 443 will start with modeling using existing data. New data collection activities are generally contingent upon the results of the modeling and may or may not be part of the CAI. Specific objectives of the CAI ar e as

  19. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility: Volume 1. Revision 1

    International Nuclear Information System (INIS)

    Weekes, D.C.; Ford, B.H.; Jaeger, G.K.

    1996-09-01

    This site characterization report provides the results of the field data collection activities for the Environmental Restoration Disposal Facility site. Information gathered on the geology, hydrology, ecology, chemistry, and cultural resources of the area is presented. The Environmental Restoration Disposal Facility is located at the Hanford Site in Richland, Washington

  20. Site suitability, selection and characterization: Branch technical position--Low-Level Waste Licensing Branch

    International Nuclear Information System (INIS)

    Siefken, D.; Pangburn, G.; Pennifill, R.; Starmer, R.J.

    1982-04-01

    The staff provides an expanded interpretation of the site suitability requirements in the proposed rule 10 CFR Part 61, a description of the anticipated site selection process, and a detailed discussion of the site characterization program needed to support a license application and environmental report. The paper provides early-on guidance to prospective applicants in these three subject areas

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

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E. (ed.)

    1988-09-01

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

  2. A Remote Characterization System for subsurface mapping of buried waste sites

    International Nuclear Information System (INIS)

    Sandness, G.A.; Bennett, D.W.; Martinson, L.

    1992-06-01

    This paper describes a development project that will provide new technology for characterizing hazardous waste burial sites. The project is a collaborative effort by five of the national laboratories, involving the development and demonstration of a remotely controlled site characterization system. The Remote Characterization System (RCS) includes a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for non-invasive inspection of the surface and subsurface

  3. Seismic site coefficients and acceleration design response spectra based on conditions in South Carolina : final report.

    Science.gov (United States)

    2014-11-15

    The simplified procedure in design codes for determining earthquake response spectra involves : estimating site coefficients to adjust available rock accelerations to site accelerations. Several : investigators have noted concerns with the site coeff...

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

    1999-09-28

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

    2002-09-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

    2001-09-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

    2003-09-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

    2004-09-22

    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.

  9. Site characterization of the Romanian Seismic Network stations: a national initiative and its first preliminary results

    Science.gov (United States)

    Grecu, Bogdan; Zahria, Bogdan; Manea, Elena; Neagoe, Cristian; Borleanu, Felix; Diaconescu, Mihai; Constantinescu, Eduard; Bala, Andrei

    2017-04-01

    The seismic activity in Romania is dominated by the intermediate-depth earthquakes occurring in Vrancea region, although weak to moderate crustal earthquakes are produced regularly in different areas of the country. The National Institute for Earth Physics (NIEP) built in the last years an impressive infrastructure for monitoring this activity, known as the Romanian Seismic Network (RSN). At present, RSN consists of 122 seismic stations, of which 70 have broadband velocity sensors and 42 short period sensors. One hundred and eleven stations out of 122 have accelerometer sensors collocated with velocity sensors and only 10 stations have only accelerometers. All the stations record continuously the ground motion and the data are transmitted in real-time to the Romanian National Data Center (RoNDC), in Magurele. Last year, NIEP has started a national project that addresses the characterization of all real-time seismic stations that constitute the RSN. We present here the steps that were undertaken and the preliminary results obtained since the beginning the project. The first two activities consisted of collecting all the existent technical and geological data, with emphasize on the latter. Then, we performed station noise investigations and analyses in order to characterize the noise level and estimate the resonances of the sites. The computed H/V ratios showed clear resonant peaks at different frequencies which correlate relatively well with the thickness of the sedimentary package beneath the stations. The polarization analysis of the H/V ratios indicates for some stations a strong directivity of the resonance peak which suggests possible topographic effects at the stations. At the same time, special attention was given to the estimation of the site amplification from earthquake data. The spectral ratios obtained from the analysis of more than 50 earthquakes with magnitudes (Mw) larger than 4.1 are characterized by similar resonance peaks as those obtained from

  10. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

  11. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    International Nuclear Information System (INIS)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

  12. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume II

    International Nuclear Information System (INIS)

    1996-08-01

    This document, Volume 2, provides the inventory of waste addressed in this Final Environmental Impact Statement (EIS) for the Tank Waste Remediation System, Hanford Site, Richland, Washington. The inventories consist of waste from the following four groups: (1) Tank waste; (2) Cesium (Cs) and Strontium (Sr) capsules; (3) Inactive miscellaneous underground storage tanks (MUSTs); and (4) Anticipated future tank waste additions. The major component by volume of the overall waste is the tank waste inventory (including future tank waste additions). This component accounts for more than 99 percent of the total waste volume and approximately 70 percent of the radiological activity of the four waste groups identified previously. Tank waste data are available on a tank-by-tank basis, but the accuracy of these data is suspect because they primarily are based on historical records of transfers between tanks rather than statistically based sampling and analyses programs. However, while the inventory of any specific tank may be suspect, the overall inventory for all of the tanks combined is considered more accurate. The tank waste inventory data are provided as the estimated overall chemical masses and radioactivity levels for the single-shell tanks (SSTs) and double-shell tanks (DSTs). The tank waste inventory data are broken down into tank groupings or source areas that were developed for analyzing groundwater impacts

  13. Characterization of the atmospheric pathway at hazardous waste sites

    International Nuclear Information System (INIS)

    Droppo, J.G. Jr.; Buck, J.W.

    1988-10-01

    Evaluation of potential health effects for populations surrounding hazardous waste sites requires consideration of all potential contaminant transport pathways through groundwater, surface water, and the atmosphere. A comprehensive pathway model that includes emission, dispersion, and deposition computations has been developed as a component of the Remedial Action Priority System (RAPS). RAPS is designed to assess the relative potential risks associated with hazardous and radioactive mixed-waste disposal sites. The atmospheric component includes optional volatilization and suspension emission routines. Atmospheric transport, dispersion, and deposition are computed using relatively standard modeling techniques expanded to incorporate topographical influences. This sector-averaged Gaussian model accounts for local channeling, terrain heights, and terrain roughness effects. Long-term total deposition is computed for the terrain surrounding the hazardous waste site. An example is given of applications at a US Department of Energy site, where atmospheric emissions are potentially important. The multiple applications of RAPS have provided information on the relative importance of different constitutent transport pathways from a potential population risk basis. Our results show that the atmospheric pathway is often equally as important as other pathways such as groundwater and direct soil ingestion. 6 refs., 3 figs., 4 tabs

  14. SITE CHARACTERIZATION ANALYSIS PENETROMETER SYSTEM (SCAPS) - INNOVATIVE TECHNOLOGY EVALUATION REPORT

    Science.gov (United States)

    In August 1994, a demonstration of cone penetrometer-mounted sensor technologies took place to evaluate their effectiveness in sampling and analyzing the physical and chemical characteristics of subsurface sod at hazardous waste sites. he effectiveness of each technology was eval...

  15. Monitoring plan for characterization of the Building 3019 leak site

    International Nuclear Information System (INIS)

    1986-06-01

    The Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program to provide comprehensive management of areas where past research, development, and waste management activities have resulted in residual contamination of facilities or the environment. In the winter of 1985, elevated levels of strontium-90 were detected in White Oak Creek and the ORNL sewage treatment plant. A leak was subsequently identified in a low-level waste transfer line north of Building 3019. The period of leakage and the exact chemical composition of the effluent are unknown. Two dye tests conducted at the leak site have identified several possible pathways for contaminant migration. The discovery of a solution cavity in the Chickamauga bedrock underlying the leak site and the rapid appearance of dye in the sump at Building 3042 indicate the extension of the cavity system along strike to the east. This report outlines the available published and unpublished background information pertaining to the site and proposes a monitoring plan consisting of soil sample collection and monitor well installation to provide a preliminary assessment of the types and extent of contamination at the leak site. The plan is also designed to provide additional geologic and hydrologic data for evaluating possible contaminant migration pathways. 6 refs., 10 figs., 1 tab

  16. Final report for the geothermal well site restoration and plug and abandonment of wells: DOE Pleasant Bayou test site, Brazoria County, Texas

    Energy Technology Data Exchange (ETDEWEB)

    Rinehart, Ben N.; Seigel, Ben H.

    1994-03-13

    For a variety of reasons, thousands of oil and gas wells have been abandoned in the Gulf Coast Region of the United States. Many of these wells penetrated geopressured zones whose resource potential for power generation was undervalued or ignored. The U.S. Department of Energy (DOE) Geopressured-Geothermal Research Program was chartered to improve geothermal technology to the point where electricity could be commercially produced from a substantial number of geopressured resource sites. This research program focused on relatively narrow technical issues that are unique to geopressured resources such as the ability to predict reservoir production capacity based on preliminary flow tests. Three well sites were selected for the research program. These are the Willis Hulin and Gladys McCall sites in Louisiana, and the Pleasant Bayou site in Texas. The final phase of this research project consists of plug and abandonment (P&A) of the wells and site restoration.

  17. Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-10-01

    The Background Soil Characterization Project (BSCP) will provide background concentration levels of selected metals organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents. This volume contains the data from the Background Soil Characterization Project. When available, the following validation qualifiers are used in the appendixes. When validation qualifiers are not available, the corresponding contract laboratory data qualifiers appearing on the next page are used

  18. Final disposal of spent fuel in the Finnish bedrock. Detailed site investigations 1993-1996; Kaeytetyn polttoaineen loppusijoitus Suomen kallioperaeaen. Yksityiskohtaiset sijoituspaikkatutkimukset 1993-1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    Posiva Oy, jointly owned company of Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (TVO), studies the Finnish bedrock for the final disposal of the spent nuclear fuel. The study is in accordance with the decision in principle by Finnish government in 1983 and aims at site selection. The report is the summary of the first stage of the detailed site investigations carried out during the years 1993-1996. The three sites in question, Romuvaara in Kuhmo, Kivetty in Aeaenekoski and Olkiluoto in Eurajoki were selected for the detailed characterization on the basis of the preliminary site investigations at five areas. The interim reporting in 1996 is comprehensive and comprises a series of reports covering different disciplines and sites. The programme for 1993-1996 was divided into three sub-programs: (1) the baseline investigations describing the present conditions in the bedrock, (2) the additional characterization for the acquisition of complementary data, and (3) the investigations for testing the earlier results and hypotheses to build confidence in existing understanding. (refs.).

  19. Radioecological characterization of a uranium mining site located in a semi-arid region in Brazil

    International Nuclear Information System (INIS)

    Fernandes, Horst M.; Lamego Simoes Filho, F. Fernando; Perez, Valeska; Franklin, Mariza Ramalho; Gomiero, Luiz Alberto

    2006-01-01

    The work presents the radioecological characterization of the new Brazilian uranium mining and milling site located in a semi-arid region of the country. The process characterization demonstrated that in heap leach plants most of the 226 Ra remains in the leached ore. Despite the potential higher availability of radium isotopes in the soils of the studied region the lack of precipitation in that area reduces the leaching/mobilization of the radionuclides. High 226 Ra and 228 Ra concentrations were found in manioc while 21 Pb was significant in pasture. It was suggested that a range from 10 -3 to 10 -1 may conveniently encompass most of the transfer factors (TF) values for soil/plant systems (i.e. involving different cultures, different soils and natural radionuclides). Impacts due to aerial transportation of aerosols and radon generated in the mining were proved to be minimal and restricted to an area not greater than 15 km 2 . Finally, uranium complexation by carbonates was shown to be the main mechanism responding for the elevated radionuclide concentration in groundwater

  20. Resource Conservation and Recovery Act industrial site environmental restoration site characterization plan. Area 6 Steam Cleaning Effluent Ponds

    International Nuclear Information System (INIS)

    1996-02-01

    This plan presents the strategy for the characterization of the Area 6 South and North Steam Cleaning Effluent Ponds (SCEPs) at the Nevada Test Site (NTS) to be conducted for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration Division (ERD). The purposes of the planned activities are to: obtain sufficient, sample analytical data from which further assessment, remediation, and/or closure strategies may be developed for the site; obtain sufficient, sample analytical data for management of investigation-derived waste (IDW). The scope of the characterization may include excavation, drilling, and sampling of soil in and around both ponds; sampling of the excavated material; in situ sampling of the soil at the bottom and on the sides of the excavations as well as within subsurface borings; and conducting sample analysis for both characterization and waste management purposes. Contaminants of concern include RCRA-regulated VOCs and metals

  1. Technical Data Catalog: Yucca Mountain Site Characterization Project. Quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-30

    This report presents reference information contained in the Yucca Mountain Project Automated Technical Data Tracking System. The Department of Energy is seeking to design and maintain a geologic repository for the disposal of high-level radioactive wastes. However, before this repository can be built, the DOE must first do a comprehensive site evaluation. This evaluation is subject to many regulations. This report fulfills the reporting requirements of the Site-Specific Procedural Agreement for Geologic Repository to develop and maintain a catalog of data which will be updated and provided to the Nuclear Regulatory Commission on a quarterly basis. This catalog contains: description of data; time, place, and method of acquisition; and where data may be examined.

  2. Summary of 1990 eolian characterization studies, Hanford Site, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Gaylord, D.R.; Stetler, L.D.; Smith, G.D. [Washington State Univ., Pullman, WA (United States); Mars, R.W. [Wyoming Univ., Laramie, WY (United States)

    1993-12-01

    A study of eolian activity was initiated to improve understanding of past climate change and the likely effect of wind on engineered protective barriers at the Hanford Site. Eolian features from a Holocene sand dune field located in the southeastern portion of the Hanford Site were investigated using a variety of field and laboratory techniques including stratigraphic examinations of hand-dug pits, textural and compositional analyses of dune sand and potential source detritus, and air photo interpretations. These investigations were undertaken to evaluate the provenance and eolian dynamics of the sand dunes. Interpretations of sand dune migration using archival air photo stereopairs document a 20% reduction in the volume of active sand dunes (measured from an approximate 15-km{sup 2} test area) between 1948 and 1987. Changes in annual precipitation appear to have influenced active dune migration strongly.

  3. Geological characterization of contaminated sites in urban areas (Denmark)

    DEFF Research Database (Denmark)

    Andersen, Theis Raaschou; Nissen, Randi Warncke; Poulsen, Søren Erbs

    In Denmark, contaminations from industry and farming represent a significant threat to groundwater resources. Hence there is a focus on identifying and locating these contaminated places. Once located, contaminations are mapped and monitored and remediation efforts are undertaken. Remediation...... is often time consuming and expensive. Moreover, as cities expand, many contaminations are now located in urban areas where data compilation and remediation efforts are often challenged by logistics. The general lack of knowledge about theses contaminations introduces significant uncertainties...... geological models of the two sites were constructed. The 3D geological models will serve as a basis for simulating groundwater flow and contaminant transport at the field sites. The study demonstrates how detailed information about the geological setting in conjunction with contaminant transport modelling...

  4. Hydrogeological characterization on sites for high level radioactive waste repository

    International Nuclear Information System (INIS)

    Guo Yonghai; Liu Shufen; Wang Ju; Su Rui

    2006-01-01

    Based on the research experiences of our country and some developed countries in the world, the processes and methods on hydrological performance assessment for sitting of high radioactive repository radioactive waste to distinct research stages are discussed in this paper. Hydrological investigation in three scales of the region, the area and the site are discussed in hydrological performance assessment. Meanwhile, the presentation on evaluation of hydrological performance is introduced, aiming at providing reference for future study. (authors)

  5. Nuclear Reactor RA Safety Report, Vol. 2, Site characterization

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is located in the village Vinca, in the vicinity of the Danube right bank, downstream from Belgrade, about 12 km from the city center. The reactor building is in the shallow valley on a plateau about 100 m above the sea level and 20 m above the Danube level. Apart from geographic and demographic data of the reactor site this document covers geologic, seismology and hydrology data. Climatic, ecology and radioactivity data of the surroundings are included as well [sr

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-10-01

    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.

  7. Site characterization progress report: Yucca Mountain, Nevada, April 1, 1990--September 30, 1990, Number 3

    International Nuclear Information System (INIS)

    1991-03-01

    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

  8. Site characterization progress report: Yucca Mountain, Nevada, October 1, 1990--March 31, 1991

    International Nuclear Information System (INIS)

    1991-10-01

    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

  9. Preliminary recommendations on the design of the characterization program for the Hanford Site single-shell tanks: A system analysis

    Energy Technology Data Exchange (ETDEWEB)

    Buck, J.W.; Peffers, M.S.; Hwang, S.T.

    1991-11-01

    The work described in this volume was conducted by Pacific Northwest Laboratory to provide preliminary recommendations on data quality objectives (DQOs) to support the Waste Characterization Plan (WCP) and closure decisions for the Hanford Site single-shell tanks (SSTs). The WCP describes the first of a two-phase characterization program that will obtain information to assess and implement disposal options for SSTs. This work was performed for the Westinghouse Hanford Company (WHC), the current operating contractor on the Hanford Site. The preliminary DQOs contained in this volume deal with the analysis of SST wastes in support of the WCP and final closure decisions. These DQOs include information on significant contributors and detection limit goals (DLGs) for SST analytes based on public health risk.

  10. Technical and political aspects for site characterization, evaluation and acceptance

    International Nuclear Information System (INIS)

    Kuehn, K.

    1993-01-01

    All countries which use nuclear energy - have to solve the problem how and where to dispose of the radioactive wastes which are generated by application of nuclear energy. Within these radioactive wastes we can differentiate three categories with regard to their disposal: Irradiated fuel elements if they are declared waste. This is the case in the United States, in Canada, Spain, Sweden, and Finland. Some strong trends into this direction can also be observed in Germany. High-level heat-generating wastes which are generated by vitrification - of liquid wastes produced by reprocessing irradiated fuel. This is true for France, United Kingdom, Japan, Germany, Switzerland, Belgium and the Netherlands. But this is also true for those five countries which possess and/or produce nuclear weapons, namely the United States, the former USSR, China, France, and United Kingdom. Low- and intermediate-level radioactive wastes which are mainly produced by operating nuclear power and reprocessing plants but also by other nuclear fuel cycle facilities and through application of radionuclides in industry, medicine and research. Most countries have decided to dispose of these wastes by shallow land burial, like the United States, Canada, Japan, France, and United Kingdom. Some other countries, like Germany, Sweden, Finland, and Switzerland, will dispose of these wastes in underground repositories too. Because of the difficult problem of public acceptance, site selection for a radioactive waste repository is not a pure technical and scientific task. On the contrary, it is mainly a political one. Two examples where possible sites were selected more because of political than of technical reasons are Yucca Mountain in the United States and Gorleben in Germany. There do exist, however, also approaches to select a site on technical and scientific grounds like in Canada, France, or Sweden

  11. Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Hatmaker, T.L.; Hook, L.A.; Jackson, B.L.

    1993-10-01

    The Background Soil Characterization Project (BSCP) will provide background concentration levels of selected metals, organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents. ORR background soil characterization data will be used for two purposes. The first application will be in differentiating between naturally occurring constituents and site-related contamination. This is a very important step in a risk assessment because if sufficient background data are not available, no constituent known to be a contaminant can be eliminated from the assessment even if the sampled concentration is measured at a minimum level. The second use of the background data will be in calculating baseline risks against which site-specific contamination risks can be compared

  12. Characterization of unsaturated hydraulic conductivity at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Rockhold, M.L.; Fayler, M.J.; Gee, G.W.

    1988-07-01

    This report details some recent field measurements and compares predicted and measured values of hydraulic conductivities for three locations at the Hanford Site. Measurements from small (6-cm-dia) /open quotes/point/close quotes/ and large (2-m by 2-m) /open quotes/plot/close quotes/ areas utilized inflitration and drainage techniques to obtain in situ data for field-saturated and unsaturated hydraulic conductivity. The Guelph permeameter was used for point sampling, and the unsteady drainage-flux method was used on plots for field-saturated and unsaturated hydraulic conductivity measurements. Steady-state techniques were used to measure unsaturated hydraulic conductivities in small columns in the laboratory for one of the three soils tested to provide a comparison with data obtained from the field. Measured unsaturated hydraulic conductivities and those predicted from particle-size distribution and bulk density data agree within one-half to one and one-half orders of magnitude, depending on soil type. To use a particle-size distribution to estimate water retention characteristics and, subsequently, to predict unsaturated hydraulic conductivities, measurements of water-retention characteristics are necessary to determine a parameter value used in one of the models. No single method for measuring or calculating unsaturated hydraulic conductivities was found appropriate for all Hanford Site soils. Ideally, several methods should be used to take advantage of the strengths of each method, considering the data needs and resources available. 45 refs., 24 figs., 19 tabs.

  13. Characterization of unsaturated hydraulic conductivity at the Hanford Site

    International Nuclear Information System (INIS)

    Rockhold, M.L.; Fayler, M.J.; Gee, G.W.

    1988-07-01

    This report details some recent field measurements and compares predicted and measured values of hydraulic conductivities for three locations at the Hanford Site. Measurements from small (6-cm-dia) /open quotes/point/close quotes/ and large (2-m by 2-m) /open quotes/plot/close quotes/ areas utilized inflitration and drainage techniques to obtain in situ data for field-saturated and unsaturated hydraulic conductivity. The Guelph permeameter was used for point sampling, and the unsteady drainage-flux method was used on plots for field-saturated and unsaturated hydraulic conductivity measurements. Steady-state techniques were used to measure unsaturated hydraulic conductivities in small columns in the laboratory for one of the three soils tested to provide a comparison with data obtained from the field. Measured unsaturated hydraulic conductivities and those predicted from particle-size distribution and bulk density data agree within one-half to one and one-half orders of magnitude, depending on soil type. To use a particle-size distribution to estimate water retention characteristics and, subsequently, to predict unsaturated hydraulic conductivities, measurements of water-retention characteristics are necessary to determine a parameter value used in one of the models. No single method for measuring or calculating unsaturated hydraulic conductivities was found appropriate for all Hanford Site soils. Ideally, several methods should be used to take advantage of the strengths of each method, considering the data needs and resources available. 45 refs., 24 figs., 19 tabs

  14. An overview of geophysical technologies appropriate for characterization and monitoring at fractured-rock sites

    Science.gov (United States)

    Geophysical methods are used increasingly for characterization and monitoring at remediation sites in fractured-rock aquifers. The complex heterogeneity of fractured rock poses enormous challenges to groundwater remediation professionals, and new methods are needed to cost-effect...

  15. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 2, Revision 2

    International Nuclear Information System (INIS)

    Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

    1996-12-01

    This document is Volume 2 in a two-volume series that comprise the site characterization report, the Preoperational Baseline and Site Characterization Report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; preoperational baseline chemical data and aquifer test data. Five groundwater monitoring wells, six deep characterization boreholes, and two shallow characterization boreholes were drilled at the Environmental Restoration Disposal Facility (ERDF) site to directly investigate site-specific hydrogeologic conditions

  16. Final audit report of remedial action construction at the UMTRA Project Mexican Hat, Utah -- Monument Valley, Arizona, sites

    International Nuclear Information System (INIS)

    1995-10-01

    The final audit report for remedial action at the Mexican Hat, Utah, Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and QA remedial action close-out inspections performed by the US Department of Energy (DOE) and the Technical Assistance Contractor (TAC); on-site construction reviews (OSCR) performed by the US Nuclear Regulatory Commission (NRC); and a surveillance performed by the Navajo Nation. This report refers to remedial action activities performed at the Mexican Hat, Utah--Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites

  17. Transport processes investigation: A necessary first step in site scale characterization plans

    International Nuclear Information System (INIS)

    Roepke, C.; Glass, R.J.; Brainard, J.; Mann, M.; Kriel, K.; Holt, R.; Schwing, J.

    1995-01-01

    We propose an approach, which we call the Transport Processes Investigation or TPI, to identify and verify site-scale transport processes and their controls. The TPI aids in the formulation of an accurate conceptual model of flow and transport, an essential first step in the development of a cost effective site characterization strategy. The TPI is demonstrated in the highly complex vadose zone of glacial tills that underlie the Fernald Environmental Remediation Project (FEMP) in Fernald, Ohio. As a result of the TPI, we identify and verify the pertinent flow processes and their controls, such as extensive macropore and fracture flow through layered clays, which must be included in an accurate conceptual model of site-scale contaminant transport. We are able to conclude that the classical modeling and sampling methods employed in some site characterization programs will be insufficient to characterize contaminant concentrations or distributions at contaminated or hazardous waste facilities sited in such media

  18. Subsurface characterization of 67P/Churyumov-Gerasimenko's Abydos Site

    Science.gov (United States)

    Brugger, B.; Mousis, O.; Morse, A.; Marboeuf, U.; Jorda, L.; Guilbert-Lepoutre, A.; Andrews, D.; Barber, S.; Lamy, P.; Luspay-Kuti, A.; Mandt, K.; Morgan, G.; Sheridan, S.; Vernazza, P.; Wright, I. P.

    2015-12-01

    We investigate the subsurface structure of comet 67P/Churyumov-Gerasimenko at the landing site of Rosetta's descent module Philae. We use a cometary nucleus model with an optimized parametrization and assume an initial composition derived from Rosetta/ROSINA measurements. We compare the CO and CO_2 outgassing rates derived from our model with those measured in situ by the Ptolemy experiment aboard the Philae module on November 12, 2014. We find results that allow us to place two main constraints on the subsurface structure of this region: a low CO/CO_2 molar ratio is needed in the nucleus, and the dust/ice mass ratio is higher at Abydos than in the rest of the nucleus. These specific constraints on Abydos support the statement of an important heterogeneity in 67P/Churyumov-Gerasimenko's nucleus.

  19. Site characterization field manual for near surface geologic disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    McCray, J.G.; Nowatzki, E.A.

    1985-01-01

    This field manual has been developed to aid states and regions to do a detailed characterization of a proposed near-surface low-level waste disposal site. The field manual is directed at planners, staff personnel and experts in one discipline to acquaint them with the requirements of other disciplines involved in site characterization. While it can provide a good review, it is not designed to tell experts how to do their job within their own discipline

  20. Assessment of remote sensing technologies to discover and characterize waste sites

    International Nuclear Information System (INIS)

    1992-01-01

    This report presents details about waste management practices that are being developed using remote sensing techniques to characterize DOE waste sites. Once the sites and problems have been located and characterized and an achievable restoration and remediation program have been established, efforts to reclaim the environment will begin. Special problems to be considered are: concentrated waste forms in tanks and pits; soil and ground water contamination; ground safety hazards for workers; and requirement for long-term monitoring

  1. SITE CHARACTERIZATION AND ANALYSIS PENETROMETER SYSTEM(SCAPS) LAZER-INDUCED FLUORESCENCE (LIF) SENSOR AND SUPPORT SYSTEM

    Science.gov (United States)

    The Consortium for Site Characterization Technology (CSCT) has established a formal program to accelerate acceptance and application of innovative monitoring and site characterization technologies that improve the way the nation manages its environmental problems. In 1995 the CS...

  2. Site Characterization during Bridge Foundation Construction Using Electrical Resistivity Tomography

    Directory of Open Access Journals (Sweden)

    Aleksandra V. Varnavina

    2016-07-01

    Full Text Available A shallow underground water-filled cavity was encountered in limestone bedrock during the construction of a new column footing for the Gasconade River Bridge over Interstate 44. Five electrical resistivity tomography (ERT profiles and borehole control were acquired in immediate proximity to the existing and the new column footings in order to assess the integrity of the rock beneath the foundation columns and characterize the encountered cavity. Two parallel southwest- northeast trending fracture zones were identified on the acquired ERT profiles and competent rock was differentiated from more extensively fractured rock. The volumetric extent of the void was mapped based on the interpretation of the ERT, borehole and injected grout data. A conceptual model for the development of the water-filled cavity was proposed.

  3. Comprehensive characterization and hazard assessment of the DOE-Niagara Falls storage site

    International Nuclear Information System (INIS)

    Anderson, T.L.; Dettorre, J.F.; Jackson, D.R.; Ausmus, B.S.

    1981-06-01

    A comprehensive radioecological and nonradiological characterization and hazards assessment was conducted on DOE-Niagara Falls Storage Site. Pitchblende residues and other low-level nuclear waste have been stored on the site since 1944. The most highly radioactive residues were stored in four abandoned buildings, while other wastes were deposited in pits or piled on surface soils on the Site. Several ditches were constructed on the Site to facilitate drainage or excess precipitation. Results of the study will permit the US DOE to form an appropriate remedial action plan for the Site

  4. Site characterization and performance assessment for a low-level radioactive waste management site in the American Southwest

    International Nuclear Information System (INIS)

    Shott, G.J.; Sully, M.J.; Muller, C.J.; Hammermeister, D.P.; Ginanni, J.M.

    1995-01-01

    The Area 5 Radioactive Waste Management Site located in southern Nevada, has been used for the disposal of low-level radioactive waste since 1961. The site is located in the Mohave Desert of the American Southwest, an extremely arid region receiving as little as 0.1 m/yr of precipitation. Site characterization studies have measured the physical, hydrologic, and geochemical properties of core samples collected from 10 shallow boreholes and 3 deep boreholes that extend through the unsaturated zone to the uppermost aquifer. Results indicate that the unsaturated zone consists of 240 m of dry alluvial sediments and is remarkably uniform with respect to most physical parameters. Measurements of saturated hydraulic conductivity with depth showed no evidence of trends, layering, or anisotropy. Parameters for hydraulic functions were not highly variable and exhibited little trend with depth. Water potential profiles indicate that water movement in the upper alluvium is upward, except immediately following a precipitation event. Below the evaporative zone, the liquid flux was downward and of the same order of magnitude as the upward thermal vapor flux induced by the geothermal gradient. The extreme climatic conditions at the site reduce or eliminate many radionuclide release and transport mechanisms. Downward transport of radionuclides to the uppermost aquifer appears unlikely under current climatic conditions. Important radionuclide transport pathways appear to be limited to upward diffusion and advection of gases and biologically-mediated transport. Conceptual models of disposal site performance have been developed based on site characterization studies. The limited transport pathways and limited land use potential of the site provide reasonable assurance that regulatory performance objectives can be met

  5. Environmental site characterization and remediation at Lawrence Livermore National Laboratory Site 300

    International Nuclear Information System (INIS)

    Lamarre, A.L.; Ferry, R.A.

    1992-04-01

    Lawrence Livermore National Laboratory (LLNL) is a research and development laboratory owned by the US Department of Energy (DOE) and operated by the University of California. The Laboratory operates its Site 300 test facility in support of DOE's national defense programs. In support of activities, at the 300 Site numerous industrial fluids are used and various process or rinse waters and solid wastes are produced. Some of these materials are hazardous by current standards. HE rinse waters were previously discharged to inlined lagoons; they now are discharged to a permitted Class II surface impoundment Solid wastes have been deposited in nine landfills. Waste HE compounds are destroyed by open burning at a burn pit facility. As a result of these practices, environmental contaminants have been released to the soil and ground water

  6. Site characterization and validation - monitoring of head in the Stripa mine during 1988

    International Nuclear Information System (INIS)

    Persson, Ove; Olsson, Olle; Sehlstedt, Mikael

    1989-04-01

    The groundwater head has been monitored in 47 borehole sections surrounding the site which is investigated as a part of the Site Characterization and Validation project. This report contains basic data on the head monitoring system and graphical presentation of the results obtained during 1988. (authors) (1 ref., 16 tabs., 109 figs.)

  7. Advanced 3D Characterization and Reconstruction of Reactor Materials FY16 Final Report

    International Nuclear Information System (INIS)

    Fromm, Bradley; Hauch, Benjamin; Sridharan, Kumar

    2016-01-01

    A coordinated effort to link advanced materials characterization methods and computational modeling approaches is critical to future success for understanding and predicting the behavior of reactor materials that operate at extreme conditions. The difficulty and expense of working with nuclear materials have inhibited the use of modern characterization techniques on this class of materials. Likewise, mesoscale simulation efforts have been impeded due to insufficient experimental data necessary for initialization and validation of the computer models. The objective of this research is to develop methods to integrate advanced materials characterization techniques developed for reactor materials with state-of-the-art mesoscale modeling and simulation tools. Research to develop broad-ion beam sample preparation, high-resolution electron backscatter diffraction, and digital microstructure reconstruction techniques; and methods for integration of these techniques into mesoscale modeling tools are detailed. Results for both irradiated and un-irradiated reactor materials are presented for FY14 - FY16 and final remarks are provided.

  8. Advanced 3D Characterization and Reconstruction of Reactor Materials FY16 Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Fromm, Bradley [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hauch, Benjamin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sridharan, Kumar [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-12-01

    A coordinated effort to link advanced materials characterization methods and computational modeling approaches is critical to future success for understanding and predicting the behavior of reactor materials that operate at extreme conditions. The difficulty and expense of working with nuclear materials have inhibited the use of modern characterization techniques on this class of materials. Likewise, mesoscale simulation efforts have been impeded due to insufficient experimental data necessary for initialization and validation of the computer models. The objective of this research is to develop methods to integrate advanced materials characterization techniques developed for reactor materials with state-of-the-art mesoscale modeling and simulation tools. Research to develop broad-ion beam sample preparation, high-resolution electron backscatter diffraction, and digital microstructure reconstruction techniques; and methods for integration of these techniques into mesoscale modeling tools are detailed. Results for both irradiated and un-irradiated reactor materials are presented for FY14 - FY16 and final remarks are provided.

  9. Characterizing the Mineralogy of Potential Lunar Landing Sites

    Science.gov (United States)

    Pieters, Carle; Head, James W., III; Mustard, Jack; Boardman, Joe; Buratti, Bonnie; Clark, Roger; Green, Rob; Head, James W, III; McCord, Thomas B.; Mustard, Jack; hide

    2006-01-01

    Many processes active on the early Moon are common to most terrestrial planets, including the record of early and late impact bombardment. The Moon's surface provides a record of the earliest era of terrestrial planet evolution, and the type and composition of minerals that comprise a planetary surface are a direct result of the initial composition and subsequent thermal and physical processing. Lunar mineralogy seen today is thus a direct record of the early evolution of the lunar crust and subsequent geologic processes. Specifically, the distribution and concentration of specific minerals is closely tied to magma ocean products, lenses of intruded or remelted plutons, basaltic volcanism and fire-fountaining, and any process (e.g. cratering) that might redistribute or transform primary and secondary lunar crustal materials. The association of several lunar minerals with key geologic processes is illustrated in Figure 1. The geologic history of potential landing sites on the Moon can be read from the character and context of local mineralogy.

  10. Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd{sup 3}) (2.1 million cubic meters [m{sup 3}]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd{sup 3} (15,000 m{sup 3}) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd{sup 3} (420,000 m{sup 3}). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd{sup 3} (2.58 million m{sup 3}). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations.

  11. Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

    International Nuclear Information System (INIS)

    1994-06-01

    The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd 3 ) (2.1 million cubic meters [m 3 ]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd 3 (15,000 m 3 ) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd 3 (420,000 m 3 ). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd 3 (2.58 million m 3 ). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations

  12. Use of Electrical Conductivity Logging to Characterize the Geological Context of Releases at UST Sites

    Science.gov (United States)

    Risk is the combination of hazard and exposure. Risk characterization at UST release sites has traditionally emphasized hazard (presence of residual fuel) with little attention to exposure. Exposure characterization often limited to a one-dimensional model such as the RBCA equa...

  13. Task Oriented Hydrogeological Site Characterization: A Framework and Case Study in Predicting Contaminant Arrival Time

    Science.gov (United States)

    Harken, B.; Schneidewind, U.; Kalbacher, T.; Rubin, Y.; Dietrich, P.

    2015-12-01

    Hydrogeological site characterization requirements vary with different modeling and risk assessment goals. For example, predicting contaminant transport requires characterization of the spatial structure and variability of hydraulic conductivity. In light of the costs associated with site characterization, a framework for task oriented field campaign design would be advantageous. The current work highlights a general framework for task oriented characterization design aimed at balancing cost with risk and uncertainty. Also presented is a case study focusing on predicting contaminant arrival time, which often depends on characterizing the spatial distribution of high-permeability zones. The case study highlights how the framework can enable the most efficient use of new characterization technologies which can improve modeling campaigns by providing measurements of hydraulic conductivity with high spatial resolution.

  14. Approaches in characterization of a site using agroclimatic information

    International Nuclear Information System (INIS)

    Aclan, A.P.; Centeno, H.G.S.; Kropff, M.J.

    1992-01-01

    Thirty years of daily radiation, temperature, and rainfall data from Los Banos [Laguna, Philippines] were analyzed to describe the rice growing environment in the area. An apparent graduate decline in the amount of incident radiation was insignificant. The distribution of minimum temperature was more stable than that of maximum temperature. Over the period considered, night time temperature slowly increased by as much as 1.5 deg C in Aug 1991. The results indicated that the energy supply for photosynthetic activity was unchanged, but the minimum temperatures could induce the dark respiration rate. As with many tropical areas, Los Banos had been dominated by rainfall. Distinct dry and wet seasons characterized the area. Rainfall onset varied between May 12 and until July 2, and receded in about 6 months later. Farmers could start transplanting their rice crop using 200 mm of rain which could be expected in the third decade of June with 80 percent probability. Establishing relationships between crop yields and weather is not easy. Crop yield data do not match the climatological data in time and in space. Climatological data were widely available, through quality and appropriateness for agriculture are rarely perfect. The suggested methodology offers more practical information researchers could see

  15. Site characterizations around KURT area-Geologic model (Version 1)-

    International Nuclear Information System (INIS)

    Park, Kyung Woo; Kim, Kyung Su; Koh, Yong Kwon; Kim, Geon Young

    2009-08-01

    To characterize the geologic elements around study area for high-level radioactive waste disposal research in KAERI, the several geological investigations such as geophysical surveys and borehole drillings were carried out since 1997. Especially, the KURT (KAERI Underground Research Tunnel) was constructed to understand the deep geological environments in 2006. At recent, the deep boreholes, which have 500m depth at left research module inside the KURT and 1,000m depth outside the KURT, were drilled around the KURT area to confirm and validate the geological model. The objective of this research is to construct the first version of geological model around KURT area in the point of hydro-geological view. The data in this study are based on the surface geological investigation and borehole investigations drilled in until 2005. At results, total 4 geological elements are obtained from geological analysis, which are a subsurface weathered zone, log-angled fractures zone, fracture zones and bedrock. And, the geometries of these elements are also plotted by three-dimensional model. The first version of geological model which is built in this study will be supported to construct the hydrogeological model and geochemical model

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

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    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.

  17. State of Nevada comments on the US Department of Energy site characterization plan, Yucca Mountain site, Nevada

    International Nuclear Information System (INIS)

    1989-09-01

    The following document comprises a critical evaluation of the DOE's Site Characterization Plan (SCP). The comments address a number of issues related to the scientific methods involved in the proposed procedures of site characterization, the suitability and integration of the methods, and the validity of the approach taken by the DOE in the context of the NRC regulations. The SCP contains many improvements of the Draft Environmental Assessment (DEA) and the Environmental Assessment (EA), and fewer improvements of the SCP Consultation Draft. An obvious attempt has been made to address topics that were regarded in these previous reviews as deficiencies in the study program. For example, the activity and seismogenic potential of the Quaternary faults at Yucca Mountain are treated much more realistically than orignally proposed by the DOE, even though published data has not increased significantly since the DEA and EA were released. Water is now recognized as a resource, and faults and fault breccias are recognized as potential hosts for epithermal mineralization. There has, in addition, been considerable effort to incorporate a number of alternative conceptual models (involving both cross sections of Yucca Mountain and regional tectonic models) into the realm of tectonic hypotheses. There is a little doubt that the SCP proposes an exhaustive and wide-ranging scope of investigations for the purpose of site characterization, and that many of these investigations have been included by the DOE in response to critical reviews by external groups (such as the NRC and various State of Nevada agencies)

  18. Characterizing the proton loading site in cytochrome c oxidase.

    Science.gov (United States)

    Lu, Jianxun; Gunner, M R

    2014-08-26

    Cytochrome c oxidase (CcO) uses the energy released by reduction of O2 to H2O to drive eight charges from the high pH to low pH side of the membrane, increasing the electrochemical gradient. Four electrons and protons are used for chemistry, while four more protons are pumped. Proton pumping requires that residues on a pathway change proton affinity through the reaction cycle to load and then release protons. The protonation states of all residues in CcO are determined in MultiConformational Continuum Electrostatics simulations with the protonation and redox states of heme a, a3, Cu(B), Y288, and E286 used to define the catalytic cycle. One proton is found to be loaded and released from residues identified as the proton loading site (PLS) on the P-side of the protein in each of the four CcO redox states. Thus, the same proton pumping mechanism can be used each time CcO is reduced. Calculations with structures of Rhodobacter sphaeroides, Paracoccus denitrificans, and bovine CcO derived by crystallography and molecular dynamics show the PLS functions similarly in different CcO species. The PLS is a cluster rather than a single residue, as different structures show 1-4 residues load and release protons. However, the proton affinity of the heme a3 propionic acids primarily determines the number of protons loaded into the PLS; if their proton affinity is too low, less than one proton is loaded.

  19. Third-generation site characterization: Cryogenic core collection, nuclear magnetic resonance, and electrical resistivity

    Science.gov (United States)

    Kiaalhosseini, Saeed

    In modern contaminant hydrology, management of contaminated sites requires a holistic characterization of subsurface conditions. Delineation of contaminant distribution in all phases (i.e., aqueous, non-aqueous liquid, sorbed, and gas), as well as associated biogeochemical processes in a complex heterogeneous subsurface, is central to selecting effective remedies. Arguably, a factor contributing to the lack of success of managing contaminated sites effectively has been the limitations of site characterization methods that rely on monitoring wells and grab sediment samples. The overarching objective of this research is to advance a set of third-generation (3G) site characterization methods to overcome shortcomings of current site characterization techniques. 3G methods include 1) cryogenic core collection (C3) from unconsolidated geological subsurface to improve recovery of sediments and preserving key attributes, 2) high-throughput analysis (HTA) of frozen core in the laboratory to provide high-resolution, depth discrete data of subsurface conditions and processes, 3) resolution of non-aqueous phase liquid (NAPL) distribution within the porous media using a nuclear magnetic resonance (NMR) method, and 4) application of a complex resistivity method to track NAPL depletion in shallow geological formation over time. A series of controlled experiments were conducted to develop the C 3 tools and methods. The critical aspects of C3 are downhole circulation of liquid nitrogen via a cooling system, the strategic use of thermal insulation to focus cooling into the core, and the use of back pressure to optimize cooling. The C3 methods were applied at two contaminated sites: 1) F.E. Warren (FEW) Air Force Base near Cheyenne, WY and 2) a former refinery in the western U.S. The results indicated that the rate of core collection using the C3 methods is on the order of 30 foot/day. The C3 methods also improve core recovery and limits potential biases associated with flowing sands

  20. Site characterization techniques used at a low-level waste shallow land burial field demonstration facility

    Energy Technology Data Exchange (ETDEWEB)

    Davis, E.C.; Boegly, W.J. Jr.; Rothschild, E.R.; Spalding, B.P.; Vaughan, N.D.; Haase, C.S.; Huff, D.D.; Lee, S.Y.; Walls, E.C.; Newbold, J.D.

    1984-07-01

    The Environmental Sciences Division of the Oak Ridge National Laboratory has been investigating improved shallow land burial technology for application in the humd eastern United States. As part of this effort, a field demonstration facility (Engineered Test Facility, or ETF) has been established in Solid Waste Storage Area 6 for purposes of investigatig the ability of two trench treatments (waste grouting prior to cover emplacement and waste isolation with trench liners) to prevent water-waste contact and thus minimize waste leaching. As part of the experimental plan, the ETF site has been characterized for purposes of constructing a hydrologic model. Site characterization is an extremely important component of the waste disposal site selection process; during these activities, potential problems, which might obviate the site from further consideration, may be found. This report describes the ETF site characterization program and identifies and, where appropriate, evaluates those tests that are of most value in model development. Specific areas covered include site geology, soils, and hydrology. Each of these areas is further divided into numerous subsections, making it easy for the reader to examine a single area of interest. Site characterization is a multidiscipliary endeavor with voluminous data, only portions of which are presented and analyzed here. The information in this report is similar to that which will be required of a low-level waste site developer in preparing a license application for a potential site in the humid East, (a discussion of licensing requirements is beyond its scope). Only data relevant to hydrologic model development are included, anticipating that many of these same characterization methods will be used at future disposal sites with similar water-related problems.

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

    International Nuclear Information System (INIS)

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

    1992-08-01

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

  2. A new ground-penetrating radar system for remote site characterization

    International Nuclear Information System (INIS)

    Davis, K.C.; Sandness, G.A.

    1994-08-01

    The cleanup of waste burial sites and military bombing ranges involves the risk of exposing field personnel to toxic chemicals, radioactive materials, or unexploded munitions. Time-consuming and costly measures are required to provide protection from those hazards. Therefore, there is a growing interest in developing remotely controlled sensors and sensor platforms that can be employed in site characterization surveys. A specialized ground-penetrating radar has been developed to operate on a remotely controlled vehicle for the non-intrusive subsurface characterization of buried waste sites. Improved radar circuits provide enhanced performance, and an embedded microprocessor dynamically optimizes operation. The radar unit is packaged to survive chemical contamination and decontamination

  3. Site Characterization Plan for decontamination and decommissioning of Buildings 3506 and 3515 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-09-01

    Buildings 3506, the Waste Evaporator Facility, and 3515, the Fission Product Pilot Plant, at Oak Ridge National Laboratory (ORNL), are scheduled for decontamination and decommissioning (D and D). This Site Characterization Plan (SCP) presents the strategy and techniques to be used to characterize Buildings 3506/3515 for the purpose of planning D and D activities. The elements of the site characterization for Buildings 3506/3515 are planning and preparation, field investigation, and characterization reporting. Other level of effort activities will include management and oversight, project controls, meetings, and progress reporting. The objective of the site characterization is to determine the nature and extent of radioactive and hazardous materials and other industrial hazards in and around the buildings. This information will be used in subsequent planning to develop a detailed approach for final decommissioning of the facilities: (1) to evaluate decommissioning alternatives and design the most cost-effective D and D approach; (2) to determine the level and type of protection necessary for D and D workers; and (3) to estimate the types and volumes of wastes generated during D and D activities. The current D and D characterization scope includes the entire building, including the foundation and equipment or materials within the building. To estimate potential worker exposure from the soil during D and D, some subfoundation soil sample collection is planned. Buildings 3506/3515 are located in the ORNL main plant area, to the west and east, respectively, of the South Tank Farm. Building 3506 was built in 1949 to house a liquid waste evaporator and was subsequently used for an incinerator experiment. Partial D and D was done prior to abandonment, and most equipment has been removed. Building 3515 was built in 1948 to house fission product separation equipment. In about 1960, all entrances were sealed with concrete block and mortar. Building 3515 is expected to be

  4. Characterization of aerosol particles at the forested site in Lithuania

    Science.gov (United States)

    Rimselyte, I.; Garbaras, A.; Kvietkus, K.; Remeikis, V.

    2009-04-01

    Atmospheric particulate matter (PM), especially fine particles (particles with aerodynamic diameter less than 1 m, PM1), has been found to play an important role in global climate change, air quality, and human health. The continuous study of aerosol parameters is therefore imperative for better understanding the environmental effects of the atmospheric particles, as well as their sources, formation and transformation processes. The particle size distribution is particularly important, since this physical parameter determines the mass and number density, lifetime and atmospheric transport, or optical scattering behavior of the particles in the atmosphere (Jaenicke, 1998). Over the years several efforts have been made to improve the knowledge about the chemical composition of atmospheric particles as a function of size (Samara and Voutsa, 2005) and to characterize the relative contribution of different components to the fine particulate matter. It is well established that organic materials constitute a highly variable fraction of the atmospheric aerosol. This fraction is predominantly found in the fine size mode in concentrations ranging from 10 to 70% of the total dry fine particle mass (Middlebrook et al., 1998). Although organic compounds are major components of the fine particles, the composition, formation mechanism of organic aerosols are not well understood. This is because particulate organic matter is part of a complex atmospheric system with hundreds of different compounds, both natural and anthropogenic, covering a wide range of chemical properties. The aim of this study was to characterize the forest PM1, and investigate effects of air mass transport on the aerosol size distribution and chemical composition, estimate and provide insights into the sources and characteristics of carbonaceous aerosols through analysis ^13C/12C isotopic ratio as a function of the aerosol particles size. The measurements were performed at the Rugšteliškis integrated

  5. Environmental assessment of remedial action at the Lowman Uranium Mill Tailings Site near Lowman, Idaho. Final

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This document assesses the environmental impacts of stabilization on site of the contaminated materials at the Lowman uranium mill tailings site. The Lowman site is 0.5 road mile northeast of the unincorporated village of Lowman, Idaho, and 73 road miles from Boise, Idaho. The Lowman site consists of piles of radioactive sands, an ore storage area, abandoned mill buildings, and windblown/waterborne contaminated areas. A total of 29.5 acres of land are contaminated and most of this land occurs within the 35-acre designated site boundary. The proposed action is to stabilize the tailings and other contaminated materials on the site. A radon barrier would be constructed over the consolidated residual radioactive materials and various erosion control measures would be implemented to ensure the long-term stability of the disposal cell. Radioactive constituents and other hazardous constituents were not detected in the groundwater beneath the Lowman site. The groundwater beneath the disposal cell would not become contaminated during or after remedial action so the maximum concentration limits or background concentrations for the contaminants listed in the draft EPA groundwater protection standards would be met at the point of compliance. No significant impacts were identified as a result of the proposed remedial action at the Lowman site.

  6. Final environmental impact statement for the Nevada Test Site and off-site locations in the state of Nevada: Mitigation action plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    The DOE Notice of Availability for this environmental impact statement was published in the Federal Register on Friday, October 18, 1996 (61 FR 54437). The final environmental impact statement identifies potential adverse effects resulting from the four use alternatives evaluated and discusses measures that DOE considered for the mitigation of these potential adverse effects. The Secretary of Energy signed the Record of Decision on the management and operation of the Nevada Test Site and other DOE sites in the state of Nevada on December 9, 1996. These decisions will result in the continuation of the multipurpose, multi-program use of the Nevada Test Site, under which DOE will pursue a further diversification of interagency, private industry, and public-education uses while meeting its Defense Program, Waste Management, and Environmental Restoration mission requirements at the Nevada Test Site and other Nevada sites, including the Tonopah Test Range, the Project Shoal Site, the Central Nevada Test Area, and on the Nellis Air Force Range Complex. The Record of Decision also identifies specific mitigation actions beyond the routine day-to-day physical and administrative controls needed for implementation of the decisions. These specific mitigation actions are focused on the transportation of waste and on groundwater availability. This Mitigation Action Plan elaborates on these mitigation commitments.

  7. Final environmental impact statement for the Nevada Test Site and off-site locations in the state of Nevada: Mitigation action plan

    International Nuclear Information System (INIS)

    1997-02-01

    The DOE Notice of Availability for this environmental impact statement was published in the Federal Register on Friday, October 18, 1996 (61 FR 54437). The final environmental impact statement identifies potential adverse effects resulting from the four use alternatives evaluated and discusses measures that DOE considered for the mitigation of these potential adverse effects. The Secretary of Energy signed the Record of Decision on the management and operation of the Nevada Test Site and other DOE sites in the state of Nevada on December 9, 1996. These decisions will result in the continuation of the multipurpose, multi-program use of the Nevada Test Site, under which DOE will pursue a further diversification of interagency, private industry, and public-education uses while meeting its Defense Program, Waste Management, and Environmental Restoration mission requirements at the Nevada Test Site and other Nevada sites, including the Tonopah Test Range, the Project Shoal Site, the Central Nevada Test Area, and on the Nellis Air Force Range Complex. The Record of Decision also identifies specific mitigation actions beyond the routine day-to-day physical and administrative controls needed for implementation of the decisions. These specific mitigation actions are focused on the transportation of waste and on groundwater availability. This Mitigation Action Plan elaborates on these mitigation commitments

  8. Model driven Soil Probing, Site Assessment and Evaluation- Final results of the EU Project ModelPROBE

    Science.gov (United States)

    Kaestner, M.; Cassiani, G.; Doeberl, G.; Braeckevelt, M.

    2012-04-01

    Conventional techniques for site characterization are time consuming, cost intensive, and do often not support decision making. Therefore, new techniques for a step by step site characterization strategy with smart feedback loops were developed in the framework of the ModelPROBE project: advanced geophysical site characterization techniques combined with new types of vegetation analysis (tree core monitoring), including integrated statistical analysis and modelling. Based on these non- to low invasive surveys, the extension of sources, contamination levels and soil heterogeneities can be localized. Hot spots can then be investigated by new direct push probing systems integrated with geophysical & hydrogeological methods, and combined with chemical & isotopic contaminant analysis for source localization and identification. The actually occurring bioprocesses, such as contaminant degradation or precipitation/mobilization processes, can be assessed using biosensors, in situ microcosms, and stable isotope and biomarker analysis. Some of these new techniques and tools were successfully evaluated against best practice of conventional methods at the fully equipped and characterized European reference sites available in the project. Beside scientific publications, the methods and techniques developed in the project will be provided in the form of an operation guideline handbook that will be published in September 2012. ModelPROBE (Grant No. 213161) is an EU project under the theme 6.3 Environmental Technologies 2007, 3.1.2.2.

  9. Characterization and remediation of soil prior to construction of an on-site disposal facility at Fernald

    International Nuclear Information System (INIS)

    Hunt, A.; Jones, G.; Nelson, K.

    1998-03-01

    During the production years at the Feed Materials Production Center (FMPC), the soil of the site and the surrounding areas was surficially impacted by airborne contamination. The volume of impacted soil is estimated at 2.2 million cubic yards. During site remediation, this contamination will be excavated, characterized, and disposed of. In 1986 the US Environmental Protection Agency (EPA) and the Department of Energy (DOE) entered into a Federal Facility Compliance Agreement (FFCA) covering environmental impacts associated with the FMPC. A site wide Remedial Investigation/Feasibility Study (RI/FS) was initiated pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act (CERCLA). The DOE has completed the RI/FS process and has received approval of the final Records of Decision. The name of the facility was changed to the Fernald Environmental Management Project (FEMP) to emphasize the change in mission to environmental restoration. Remedial actions which address similar scopes of work or types of contaminated media have been grouped into remedial projects for the purpose of managing the remediation of the FEMP. The Soil Characterization and Excavation Project (SCEP) will address the remediation of FEMP soils, certain waste units, at- and below-grade material, and will certify attainment of the final remedial limits (FRLs) for the FEMP. The FEMP will be using an on-site facility for low level radioactive waste disposal. The facility will be an above-ground engineered structure constructed of geological material. The area designated for construction of the base of the on-site disposal facility (OSDF) is referred to as the footprint. Contaminated soil within the footprint must be identified and remediated. Excavation of Phase 1, the first of seven remediation areas, is complete

  10. Site characterization progress report: Yucca Mountain, Nevada, April 1, 1991--September 30, 1991, Number 5

    International Nuclear Information System (INIS)

    1992-06-01

    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

  11. Argonne's Expedited Site Characterization: An integrated approach to cost- and time-effective remedial investigation

    International Nuclear Information System (INIS)

    Burton, J.C.; Walker, J.L.; Aggarwal, P.K.; Meyer, W.T.

    1995-01-01

    Argonne National Laboratory has developed a methodology for remedial site investigation that has proven to be both technically superior to and more cost- and time-effective than traditional methods. This methodology is referred to as the Argonne Expedited Site Characterization (ESC). Quality is the driving force within the process. The Argonne ESC process is abbreviated only in time and cost and never in terms of quality. More usable data are produced with the Argonne ESC process than with traditional site characterization methods that are based on statistical-grid sampling and multiple monitoring wells. This paper given an overview of the Argonne ESC process and compares it with traditional methods for site characterization. Two examples of implementation of the Argonne ESC process are discussed to illustrate the effectiveness of the process in CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) and RCRA (Resource Conservation and Recovery Act) programs

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

    International Nuclear Information System (INIS)

    1994-02-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-08-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-02-01

    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.

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-08

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

  17. Final report of fugitive and diffuse emissions evaluations at the Hanford Site, CY 1994

    International Nuclear Information System (INIS)

    Gleckler, B.P.; Schmidt, J.W.

    1995-01-01

    The objective of this study was to evaluate several of Hanford's major diffuse emission sources and evaluate the effectiveness of monitoring these sources individually versus collectively. The results from this evaluation may also be utilized to demonstrate Westinghouse's compliance status with the applicable air emissions regulations and determine if additional studies and/or evaluations are necessary. Air sampling results from four waste handling and storage facilities were collected for a one week period and analyzed. The following is a list of the selected sampling sites: Plutonium Finishing Plant; 241-BY Tank Farm; 1301-N Trench; 300 Area Trenches and North Ponds. These sites were chosen as being representative of most of the Hanford waste sites, which are known to be diffuse emission sites. The sites were evaluated on the following criteria: physical size, surface contamination levels, geology, vegetation density, surface cover, potential for occupational exposure, and potential for public exposure. The selected sites vary greatly with the selection criteria parameters, and as a result should provide representative data for most of Hanford's waste sites

  18. West Siberian Basin hydrogeology: Site characterization of Mayak, Tomsk-7, and Krasnoyarsk-26

    International Nuclear Information System (INIS)

    Hoover, K.A.; Foley, M.G.; Allen, E.A.; Alexander, L.J.; McKinley, M.I.

    1997-01-01

    The former Soviet Union has extensive defense-related nuclear production facilities that have released large amounts of hazardous and radioactive waste materials into the air, surface water, and ground water in areas surrounding the production sites. The key sites of concern are Mayak, Tomsk-7, and Krasnoyarsk-26, all located within the West siberian Basin. The Pacific Northwest National Laboratory (PNNL), in cooperation with the Russian Ministry of Atomic Energy (Minatom), has been conducted contaminant-migration studies of Mayak, Tomsk-7, and Krasnoyarsk-26 in Western Siberia since 1993. The intent of this program is to maximize use of US and Russian site characterization, contaminant transport modeling, and remediation technology for the benefit of DOE and Minatom site-cleanup activities. Site characterization activities conducted during FY 1996 comprised evaluating the existing database, developing methods for synthesizing missing data, and designing an effective means of data and technology transfer. Comparison of the database, most of the contents of which have been acquired remotely with contaminant transport modeling data requirements allowed the authors to evaluate the utility of data acquired remotely for modeling purposes, and to identify gaps in the characterization of Russian waste-disposal sites. Identifying these gaps led to the second activity, which was to develop methods for synthesizing missing data from an evaluation of existing data. The authors tested these methods by evaluating geologic fracturing at the Mayak site. The third activity was the development of an effective procedure for data and technology transfer. The goal was to provide the site characterization database to Russian modelers in such a way that the data were easily transported, viewed, and manipulated for use in their models. This report summarizes the results of the three site characterization activities performed during FY 1996

  19. Use of Historical Pump-and-Treat Data to Enhance Site Characterization and Remediation Performance Assessment.

    Science.gov (United States)

    Brusseau, Mark L

    2013-10-01

    Groundwater withdrawal and contaminant concentration data are routinely collected for pump-and-treat operations conducted at hazardous waste sites. These data sets can be mined to produce a wealth of information to support enhanced site characterization, optimization of remedial system operations, and improved decision making regarding long-term site management and closure. Methods that may be used to analyze and interpret pump-and-treat data to produce such assessments are presented, along with a brief illustration of their application to a site. The results presented herein illustrate that comprehensive analysis of pump-and-treat data is a powerful, cost-effective method for providing higher-resolution, value-added characterization of contaminated sites.

  20. Energy conserving site design case study-Radisson, New York. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kaminsky, Jacob; Hrabak, Robert; Jacobs, Robert; Ryder, Richard; Schultz, Robert; Reimann, Robert G.; Paulo, Frances X.; Crandall, David B.; Belle, John; Pavliv, Mark; Seanor, Arthur; Chandler, Marty; Till, Howard B.; Lester, William; O' Brien, Michael; Rediowski, Jan; Phillips, Howard; Cahill, Michael; Matteson, Eric; Cathey, John

    1979-12-01

    A case study of project planning and design for energy conservation at Radisson New Community, Baldwinsville, New York is described. The new community includes a 95-acre residential site and a 51-acre town center. Energy-conserving plans developed for both sites have focused on passive measures to reduce energy use for space heating. Utility systems options have been identified for both sites. The case study overview contains data on location, climatology, local meteorology. Development plans for both the residential and town center areas are described. After a description of the team structure, methodological considerations, and impediments to implementation, the implementation program is given. (MCW)

  1. Geological characterization of contaminated sites near the city of Horsens, Denmark

    DEFF Research Database (Denmark)

    Andersen, Theis Raaschou; Poulsen, Søren Erbs; Thomsen, Peter

    ) filtration by means of water saturated, rapid biofilters. Consequently, there is a focus on identifying and locating contaminated sites on a national level. Insufficient knowledge about the geology and hydrology at the sites poses a significant challenge for remediation efforts. The lack of information about...... characterization of three contaminated sites situated in urban and semi-urban areas around the city of Horsens in corporation with authorities. The existing data from the three field sites include lithological profiles from boreholes. In order to increase the data density, Electrical Resistivity Tomography (ERT...

  2. Final ecosystem goods and services enhance societal relevance of contaminated-site remediation

    Science.gov (United States)

    Background/Question/Methods Exposure to environmental stressors can adversely affect both human health and ecological receptors and impacts on the latter influence the community's overall vulnerability. Risk assessment guidance promotes conceptual site models to integrate multip...

  3. An economic analysis of a monitored retrievable storage site for Tennessee. Final report and appendices

    Energy Technology Data Exchange (ETDEWEB)

    Fox, W.F.; Mayo, J.W.; Hansen, L.T.; Quindry, K.E.

    1985-12-17

    The United States Department of Energy is charged with the task of identifying potential sites for a Monitored Retrievable Storage (MRS) Facility and reporting the results of its analysis to Congress by January 1986. DOE chose three finalist sites from 11 sites DOE analysts evaluated earlier. All three are in Tennessee, including two in Oak Ridge and one in Trousdale/Smith Counties. This paper is a summary of research undertaken on the economic effects of establishing the MRS facility in Tennessee. All three locations were considered in the analysis, but on some occasions attention is focused on the site preferred by DOE. The research was undertaken by the Center for Business and Economic Research (CBER), College of Business Administration, the University of Tennessee, Knoxville, under contract with the Tennessee Department of Economic and Community Development.

  4. Environmental assessment of remedial action at the Gunnison Uranium Mill Tailings Site near Gunnison, Colorado. Final

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    The presence of contaminated uranium mill tailings adjacent to the city of Gunnison has been a local concern for many years. The following issues were identified during public meetings that were held by the DOE prior to distribution of an earlier version of this EA. Many of these issues will require mitigation. Groundwater contamination; in December 1989, a herd of 105 antelope were introduced in an area that includes the Landfill disposal site. There is concern that remedial action-related traffic in the area would result in antelope mortality. The proposed Tenderfoot Mountain haul road may restrict antelope access to their water supply; a second wildlife issue concerns the potential reduction in sage grouse use of breeding grounds (leks) and nesting habitat; the proposed Tenderfoot Mountain haul road would cross areas designated as wetlands by US Army Corps of Engineers (COE); the proposed disposal site is currently used for grazing by cattle six weeks a year in the spring. Additional concerns were stated in comments on a previous version of this EA. The proposed action is to consolidate and remove all contaminated materials associated with the Gunnison processing site to the Landfill disposal site six air miles east of Gunnison. All structures on the site (e.g., water tower, office buildings) were demolished in 1991. The debris is being stored on the site until it can be incorporated into the disposal cell at the disposal site. All contaminated materials would be trucked to the Landfill disposal site on a to-be-constructed haul road that crosses BLM-administered land.

  5. Energy-conserving site-design case study, Radisson, New York. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    Radisson is a 2,950-acre new community currently being developed by the New York State Urban Development Corporation and located in central New York, 12 miles north-west of Syracuse. Case-study sites selected for this project are a 95-acre residential site and the 51-acre Town Center of the new community. Development on the Residential Site is a low-density (2.8 dwelling units/acre) mixture of single-family, townhouse and multi-family units. Development on the Town Center site is a mixture of small-scale commercial use (144,000 sq. ft.) and 330+ multi-family dwelling units. Energy-conserving plans developed for both sites have focused on passive measures to reduce energy use for space heating. Utility-system options have been identified for both sites, but require further study as to feasibility and cost. This report summarizes energy savings and cost differentials due to passive measures incorporated in both the residential and Town Center Plans. The future implementation schedule, also discussed, summarizes the procedures an schedule required for implementation of the passive measures, as well as further study required for the development of utility-system options. 4 tables.

  6. Understanding brittle deformation at the Olkiluoto site. Literature compilation for site characterization and geological modelling

    International Nuclear Information System (INIS)

    Millnes, A.G.

    2006-07-01

    The present report arose from the belief that geological modelling at Olkiluoto, Finland, where an underground repository for spent nuclear fuel is at present under construction, could be significantly improved by an increased understanding of the phenomena being modelled, in conjunction with the more sophisticated data acquisition and processing methods which are now being introduced. Since the geological model is the necessary basis for the rock engineering and hydrological models, which in turn provide the foundation for identifying suitable rock volumes underground and for demonstrating longterm safety, its scientific basis is of critical importance. As a contribution to improving this scientific basis, the literature on brittle deformation in the Earth's crust has been reviewed, and key references chosen and arranged, with the particular geology of the Olkiluoto site in mind. The result is a compilation of scientific articles, reports and books on some of the key topics, which are of significance for an improved understanding of brittle deformation of hard, crystalline rocks, such as those typical for Olkiluoto. The report is subdivided into six Chapters, covering (1) background information, (2) important aspects of the fabric of intact rock, (3) fracture mechanics and brittle microtectonics, (4) fracture data acquisition and processing, for the statistical characterisation and modelling of fracture systems, (5) the characterisation of brittle deformation zones for deterministic modelling, and (6) the regional geological framework of the Olkiluoto site. The Chapters are subdivided into a number of Sections, and each Section into a number of Topics. The citations are mainly collected under each Topic, embedded in a short explanatory text or listed chronologically without comment. The systematic arrangement of Chapters, Sections and Topics is such that the Table of Contents can be used to focus quickly on the theme of interest without the necessity of looking

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-06-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    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.

  9. Surface structural-chemical characterization of a single-site d0 heterogeneous arene hydrogenation catalyst having 100% active sites

    Science.gov (United States)

    Williams, Linda A.; Guo, Neng; Motta, Alessandro; Delferro, Massimiliano; Fragalà, Ignazio L.; Miller, Jeffrey T.; Marks, Tobin J.

    2013-01-01

    Structural characterization of the catalytically significant sites on solid catalyst surfaces is frequently tenuous because their fraction, among all sites, typically is quite low. Here we report the combined application of solid-state 13C-cross-polarization magic angle spinning nuclear magnetic resonance (13C-CPMAS-NMR) spectroscopy, density functional theory (DFT), and Zr X-ray absorption spectroscopy (XAS) to characterize the adsorption products and surface chemistry of the precatalysts (η5-C5H5)2ZrR2 (R = H, CH3) and [η5-C5(CH3)5]Zr(CH3)3 adsorbed on Brønsted superacidic sulfated alumina (AlS). The latter complex is exceptionally active for benzene hydrogenation, with ∼100% of the Zr sites catalytically significant as determined by kinetic poisoning experiments. The 13C-CPMAS-NMR, DFT, and XAS data indicate formation of organozirconium cations having a largely electrostatic [η5-C5(CH3)5]Zr(CH3)2+···AlS− interaction with greatly elongated Zr···OAlS distances of ∼2.35(2) Å. The catalytic benzene hydrogenation cycle is stepwise understandable by DFT, and proceeds via turnover-limiting H2 delivery to surface [η5-C5(CH3)5]ZrH2(benzene)+···AlS− species, observable by solid-state NMR and XAS. PMID:23269836

  10. Analytical methods for characterization of explosives-contaminated sites on U.S. Army installations

    Science.gov (United States)

    Jenkins, Thomas F.; Walsh, Marianne E.; Thorne, Philip G.

    1995-10-01

    The U.S. Army manufactures munitions at facilities throughout the United States. Many of these facilities are contaminated with residues of explosives from production, disposal of off- specification, and out-of-data munitions. The first step in remediating these sites is careful characterization. Currently sites are being characterized using a combination of on-site field screening and off-site laboratory analysis. Most of the contamination is associated with TNT (2,4,6-trinitrotoluene) and RDX (hexahydro-1,3,5-tri-nitro-1,3,5-triazine) and their manufacturing impurities and environmental transformation products. Both colorimetric and enzyme immunoassay-based field screening methods have been used successfully for on-site characterization. These methods have similar detection capabilities but differ in their selectivity. Although field screening is very cost-effective, laboratory analysis is still required to fully characterize a site. Laboratory analysis for explosives residues in the United States is generally conducted using high-performance liquid chromatography equipped with a UV detector. Air-dried soils are extracted with acetonitrile in an ultrasonic bath. Water is analyzed directly if detection limits in the range of 10 - 20 (mu) g/L are acceptable, or preconcentrated using either salting-out solvent extraction with acetonitrile or solid phase extraction.

  11. Development of a Hydrologic Characterization Technology for Fault Zones Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Karasaki, Kenzi [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Onishi, Celia Tiemi [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Doughty, Christine [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Conrad, Mark [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Gasperikova, Erika [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Cook, Paul [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Ulrich, Craig [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-03-31

    This is the final report for the five-year program of the NUMO-LBNL collaborative project (hereafter called the Project): Development of Hydrologic Characterization Technology for Fault Zones, under a NUMO-DOE/LBNL collaboration agreement. Detailed results from the past four years of study can be found in the each year’s year-end report (Karasaki et al., 2008, 2009, 2010, and 2011; Kiho et al., 2008, 2009, 2010, and 2011). In this report, we discuss the results of the studies conducted in FY2011. We also give a summary of the overall results and findings, as well as the lessons learned during the course of the Project.

  12. Wave Resource Characterization at US Wave Energy Converter (WEC) Test Sites

    Science.gov (United States)

    Dallman, A.; Neary, V. S.

    2016-02-01

    The US Department of Energy's (DOE) Marine and Hydrokinetic energy (MHK) Program is supporting a diverse research and development portfolio intended to accelerate commercialization of the marine renewable industry by improving technology performance, reducing market barriers, and lowering the cost of energy. Wave resource characterization at potential and existing wave energy converter (WEC) test sites and deployment locations contributes to this DOE goal by providing a catalogue of wave energy resource characteristics, met-ocean data, and site infrastructure information, developed utilizing a consistent methodology. The purpose of the catalogue is to enable the comparison of resource characteristics among sites to facilitate the selection of test sites that are most suitable for a developer's device and that best meet their testing needs and objectives. It also provides inputs for the design of WEC test devices and planning WEC tests, including the planning of deployment and operations and maintenance. The first edition included three sites: the Pacific Marine Energy Center (PMEC) North Energy Test Site (NETS) offshore of Newport, Oregon, the Kaneohe Bay Naval Wave Energy Test Site (WETS) offshore of Oahu, HI, and a potential site offshore of Humboldt Bay, CA (Eureka, CA). The second edition was recently finished, which includes five additional sites: the Jennette's Pier Wave Energy Converter Test Site in North Carolina, the US Army Corps of Engineers (USACE) Field Research Facility (FRF), the PMEC Lake Washington site, the proposed PMEC South Energy Test Site (SETS), and the proposed CalWave Central Coast WEC Test Site. The operational sea states are included according to the IEC Technical Specification on wave energy resource assessment and characterization, with additional information on extreme sea states, weather windows, and representative spectra. The methodology and a summary of results will be discussed.

  13. Final environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Framework for the resource management plan, Volume 2

    International Nuclear Information System (INIS)

    1996-08-01

    The purpose of this document is to publicize how the U.S. Department of Energy Nevada Operations Office (DOE/NV) proposes to develop and use a Resource Management Plan for the Nevada Test Site (NTS) so the public could comment on and assist in the following activities: (1) Developing the methods for creating and using the plan; (2) Identifying the values people place on manmade and natural resources found on the NTS; (3) Developing the goals the DOE/NV will use to guide the conservation and use of those resources; (4) Identifying the management actions needed to meet constraints and resource management goals; and (5) Incorporating the principles of ecosystem management into land and resource management on the NTS. This framework for the Resource Management Plan was developed in conjunction with the Environmental Impact Statement for the Nevada Test Site and off-site locations in the state of Nevada (NTS EIS) to take advantage of the extensive data collection and public participation activities associated with the National Environmental Policy Act. After public input was received during the comment period for the Draft NTS EIS, DOE/NV revised this description of the Resource Management Plan and published it with the NTS Final EIS. This revision includes the goals DOE/NV has developed for managing resources and land-use constraints. It also includes the final plans for developing the Resource Management Plan. These plans will guide DOE/NV as it develops a Resource Management Plan in the coming years

  14. Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Watkins, D.R.; Ammons, J.T.; Branson, J.L.

    1993-10-01

    This report presents, evaluates, and documents data and results obtained in the Background Soil Characterization Project (BSCP). It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program. The objectives of the BSCP consist of the following: determine background concentrations of organics, metals, and radionuclides in natural soils that are key to environmental restoration projects; provide remediation projects with 100% validated data on background concentrations, which are technically and legally defensible; and quantify baseline risks from background constituents for comparison of risks associated with contaminated sites

  15. Social and economical aspects in the selection of the site for the final Goiania waste repository

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Tranjan Filho, A.; Rosenthal, J.J.

    2000-01-01

    Site selection criteria for low and intermediate level waste repositories are usually well established as far as the technological and scientific bases are concerned. However, social, cultural and economical aspects need to be examined on a case by case basis because there are many situations to be faced before succeeding to convince the public and authorities that a waste repository is to be built at any chosen site. In the specific case of Goiania there is an ongoing process that started several years ago, to make the repository accepted by local, state and national authorities, and to answer legitimate questions raised by significant segments of the population. This paper will summarise those more relevant aspects concerning the site selection process for the Goiania repository. (author)

  16. State of Nevada comments on the US Department of Energy site characterization plan, Yucca Mountain site, Nevada

    International Nuclear Information System (INIS)

    1989-01-01

    We find the Site Characterization Plan: Yucca Mountain Site, Nevada Research and Development Area (DOE/RW-0160) seriously deficient, in terms of establishing an investigative program to confidently characterize hydrogeologic and closely-related aspects of the proposed repository, in the vadose zone at Yucca Mountain. Most hydrogeological licensing criteria indirectly measure waste isolation provided by the geologic environment during pre- and post-closure conditions. We believe the Site Characterization Plan (SCP) generally fails to establish scientifically sound and feasible programs of investigation that will, in a timely and confident manner, resolve most of the hydrogeologic and geochemical licensing issues that have been recognized since the vadose-zone repository was first proposed at this location in 1982. The SCP generally fails in its responsibility because it does not objectively set aside the DOE conceptual model of a ''dry'' repository environment with extremely slow flow of water confined to the rock matrix. In the SCP, the DOE fails to establish a scientifically sound investigative program that seriously tests for hydrogeologic conditions based on the range of existing data and general knowledge. Rather, the DOE builds a probabilistic program upon a preconceived conceptual model, without designing a field-data collection program with the power to test the validity of the conceptual model. This is unacceptable in that the DOE program, as described in the SCP, plans to build numerical model after numerical model upon untested conceptual models, in attempts to ''resolve'' the fundamental licensing issues of waste isolation by the geologic barrier. If executed as planned, these analyses will have only a series of assumptions of their foundation and, therefore, can not resolve licensing issues. 12 refs., 3 figs

  17. Tooele Army Depot Revised Final Site-Wide Ecological Risk Assessment. Volume IV.

    Science.gov (United States)

    1998-02-01

    o © Q , ©. ©. z S z z O O ig§i§§!sgi§s!is!! sissi &gs|§i © ■* © ©© — ©^ — ^ÄÄ _ QOODOODSSD299 ©z^zz^^zSS^S22©ltH...rare and/or endangered plants. The field reconnaissance to be conducted by walking or driving survey. 2. Any rare/endangered plants discovered during...Methodology used was as described in the task list. Each of the sites was visited by automobile, and the sites were surveyed by walking through the

  18. Final Report - Independent Verification Survey Activities at the Seperations Process Research Unit Sites, Niskayuna, New York

    Energy Technology Data Exchange (ETDEWEB)

    Evan Harpenau

    2011-03-15

    The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

  19. Characterization of Landslide Sites in Puerto Rico after Hurricanes Irma and María

    Science.gov (United States)

    Hughes, K. S.; Morales Vélez, A. C.

    2017-12-01

    Thousands of landslides in Puerto Rico and the U.S. Virgin Islands were triggered by the passage of Hurricanes Irma (Sep. 6) and María (Sep. 20) in 2017. Both were classified as Category 5 hurricanes on the Saffir-Simpson scale before making landfall. Most of the mass wasting occurred in the rugged mountainous regions of Puerto Rico and—along with bridge collapse, flooding, and the threat of dam failure—left many communities isolated for up to a month or longer. Aerial photography collected by FEMA and the Civil Air Patrol have allowed for the rapid inventory of landslide sites across the archipelago by the USGS and other groups. Using this dataset and other local information, we identified a list of priority sites that were documented in detail as part of a NSF-GEER (Geotechnical Extreme Event Reconnaissance) mission. The juvenile landscape and short-wavelength topography in most of Puerto Rico present considerable landslide risk that is exaggerated during heavy rainfall events like Hurricane María. Our preliminary work shows that natural escarpments, de-vegetated pastureland in mountainous areas, and road cuts along incised river valleys were areas of concentrated failures during these storms. Notably, the northern karst area suffered fewer failures than the arc basement rocks exposed elsewhere in the island. In addition to previously active landslides at specific sites on the island, new landslides along PR-143 in the municipality of Barranquitas, PR-431 in the municipality of Lares, and PR-109 in the municipality of Añasco are among important mass wasting events that were a focus of the GEER team and remain important in our ongoing research. A team of undergraduate and graduate students led by faculty at the University of Puerto Rico in Mayagüez are working to characterize the complete inventory of landslides in terms of underlying geology, soil type, slope, curvature, rain fall amounts during both atmospheric events, and other local geomorphic and

  20. Site characterization

    Energy Technology Data Exchange (ETDEWEB)

    Brown, W.S.; Green, S.J.; Hustrulid, W.A. (comps.)

    1976-01-01

    The papers presented at the Conference discussed the topics of modelling and analysis, coal recovery, oil and gas applications, surface structures and slope stability, underground opening design, geothermal energy recovery, in-situ methods, near surface underground opening design, blasting design, rock mechanics, and ground support. Abstracts were prepared for selected papers. (JSR)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

    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 and 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

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

    International Nuclear Information System (INIS)

    1999-06-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1999-06-01

    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.

  4. Geomorphic stability field reconnaissance site visit, Canonsburg, Pennsylvania, December 1992. Final report

    International Nuclear Information System (INIS)

    1993-05-01

    To license the Canonsburg site, the US Nuclear Regulatory Commission (NRC) has required that geomorphic stability be demonstrated for the stream banks and slopes around the perimeter of the site for 200 years. Based on a study of the stream channel and slopes, it has been determined that due to recent human intervention, the required geomorphic stability cannot now be achieved without installation of erosion protection works and continued monitoring of the site. The Pittsburgh District Corps of Engineers has plans to channelize Chartiers Creek and install erosion protection rock within the next 5 or 6 years, if local government agencies raise the necessary matching funds. Much of the stream bank and slope adjacent to the ''fenced in'' western area of the site is anticipated to remain geomorphically stable for more than 20 years, but less than 200 years without human intervention. Therefore in much of this area, the Corps of Engineers will have adequate time to perform its work without jeopardizing the integrity of the controlled area. In contrast, two approximately 200-foot (ft) (60-meter [m]) long portions of the stream channel located north-northwest of the encapsulation area are subject to active stream erosion that threatens the integrity of the controlled area. These areas should be fixed by installation of erosion protection rock within the next 2 years

  5. 78 FR 75913 - Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site...

    Science.gov (United States)

    2013-12-13

    ... Alternatives 2 through 6 and the sub- alternatives within them, the contents of the cesium (Cs) and strontium... Water Act at the fence line of the FFTF facility. Short-term impacts for the land, water, transportation... of cesium and strontium capsules, on-site interim storage of IHLW and the concept of risk-based...

  6. Final Work Plan for CO2 Sparging Proof of Concept Test, LCP Chemical Site

    Science.gov (United States)

    September 11, 2012 plan to address concerns on a pilot test of carbon dioxide sparging to neutralize pH and reduce the density of the Caustic Brine Pool (CBP) at the LCP Chemicals Superfund Site, GA. Region ID: 04 DocID: 10903388, DocDate: 09-11-2012

  7. Final environmental impact assessment of the Paducah Gaseous Diffusion Plant site, Paducah, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    1982-08-01

    This document considers: the need for uranium enrichment facilities; site location; plant description; and describes the power generating facilities in light of its existing environment. The impacts from continuing operations are compared with alternatives of shutdown, relocation, and alternative power systems. (PSB)

  8. 75 FR 61174 - Warner Valley Comprehensive Site Plan, Final Environmental Impact Statement, Lassen Volcanic...

    Science.gov (United States)

    2010-10-04

    ... electronic version was posted at both Lassen Volcanic National Park's Web site http://www.nps.gov/lavo... Control Board, the Northern Sierra Air Quality District, the Almanor Basin Fire Safe Council, and assorted... headquarters and at local public libraries, and an electronic version will also be posted on the Lassen...

  9. Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-09-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-01-25

    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

  11. Assessment of remote sensing technologies to discover and characterize waste sites

    International Nuclear Information System (INIS)

    1992-01-01

    This report presents details about waste management practices that are being developed using remote sensing techniques to characterize DOE waste sites. Once sites and problems have been located and an achievable restoration and remediation program have been established, efforts to reclaim the environment will begin. Special problems to be considered are: concentrated wastes in tanks and pits; soil and ground water contamination; ground safety hazards for workers; and requirements for long-term monitoring

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    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.

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

    International Nuclear Information System (INIS)

    1997-10-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    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.

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

    International Nuclear Information System (INIS)

    1994-10-01

    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

  16. Area 5 Site Characterization Project: Report of hydraulic property analysis through August 1993

    Energy Technology Data Exchange (ETDEWEB)

    Estrella, R.; Tyler, S.; Chapman, J.; Miller, M.

    1993-12-01

    The Area 5 Site Characterization Project is designed to determine the suitability of the Radioactive Waste Management Site (RWMS) for disposal of low-level waste (LLW), mixed waste (MW) and transuranic waste (TRU). The Desert Research Institute (DRI) has supported the Area 5 Site Characterization Project for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division (ERWM), Waste Operations Branch (WOB). The purpose of DRI`s Area 5 Site Characterization project is to characterize important properties of the upper vadose zone which influence infiltration and redistribution of water and transport of solutes as well as to characterize the water quality and hydrologic conditions of the uppermost aquifer. This report describes methods and presents a summary of all data and results from laboratory physical and chemical testing from Pilot Wells and Science Trench borehole samples through August 1993. DRI laboratories performed soil water content, soil water potential, soil bulk density, soil water extract isotope analyses and soil water chemistry analyses.

  17. Final rubbery state characterization using a hollow cylinder dynamic shear sample on DMA7

    Directory of Open Access Journals (Sweden)

    Vilaiporn Luksameevanish

    2004-09-01

    Full Text Available Dynamic properties of raw natural rubber were examined using a hollow cylinder shaped samplesubjected to shear deformation on a laboratory Dynamic Mechanical Analyser. According to Cox-Merz’s study, dynamic complex viscosity obtained by this method showed a good agreement with shear flow viscosity measured by capillary rheometer. A master curve derived from the dynamic properties were then characterized. A crossing point of storage modulus (G’ and loss modulus (G’’ curves in the master curves was used to identify the final rubbery state, which indicated the transition of rubbery state and molten state. The position of this point depends on quantities and types of reinforcing or non-reinforcing fillers. The final rubbery state was shifted to higher frequency or lower temperature. It was found that the final rubbery state of CaCO3-filled rubber compounds was shifted to higher frequency or lower temperature by approximately 4 decades, while the translation of carbon black-filled rubber compounds was lower than unfilled rubber by about 1 decade. This phenomenon can be used to explain rubber elasticity, i.e. a decreasing of die swell of CaCO3 filled compounds at any high processing temperature. On the other hand, high magnitude of die swell for carbon black filled compound was still obtained.

  18. Final Oak Ridge National Laboratory Site Assessment Report on the Storage of 233U

    International Nuclear Information System (INIS)

    Bereolos, P.J.; Yong, L.K.

    1999-01-01

    This assessment characterizes the 233 U inventories and storage facility at Oak Ridge National Laboratory (ORNL). This assessment is a commitment in the U.S. Department of Energy (DOE) Implementation Plan (IP), ''Safe Storage of Uranium-233,'' in response to the Defense Nuclear Facilities Safety Board's Recommendation 97-1

  19. Multi-agency radiation survey and site investigation manual (MARSIM). Final report

    International Nuclear Information System (INIS)

    1997-12-01

    The MARSSIM provides information on planning, conducting, evaluating, and documenting building surface and surface soil final status radiological surveys for demonstrating compliance with dose or risk-based regulations or standards. The MARSSIM is a multi-agency consensus document that was developed collaboratively by four Federal agencies having authority and control over radioactive materials: Department of Defense (DOD), Department of Energy (DOE), Environmental Protection Agency (EPA), and Nuclear Regulatory Commission (NRC). The MARSSIM's objective is to describe a consistent approach for planning, performing, and assessing building surface and surface soil final status surveys to meet established dose or risk-based release criteria, while at the same time encouraging an effective use of resources

  20. Multi-agency radiation survey and site investigation manual (MARSIM). Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The MARSSIM provides information on planning, conducting, evaluating, and documenting building surface and surface soil final status radiological surveys for demonstrating compliance with dose or risk-based regulations or standards. The MARSSIM is a multi-agency consensus document that was developed collaboratively by four Federal agencies having authority and control over radioactive materials: Department of Defense (DOD), Department of Energy (DOE), Environmental Protection Agency (EPA), and Nuclear Regulatory Commission (NRC). The MARSSIM`s objective is to describe a consistent approach for planning, performing, and assessing building surface and surface soil final status surveys to meet established dose or risk-based release criteria, while at the same time encouraging an effective use of resources.

  1. Final disposal of spent nuclear fuel in Finnish bedrock - Romuvaara site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy (Finland); Ahokas, H. [Fintact Oy (Finland); Front, K. [VTT Communities and Infrastructure, Espoo (Finland)] [and others

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Romuvaara. The bedrock of Romuvaara belongs to the Archean basement complex, whose oldest parts date back over 2800 million years. The bedrock consists mainly of migmatitic banded gneisses (tonalite, leucotonalite and mica gneiss), which are cut by granodiorite and metadiabase dykes. The rocks, excluding the metadiabase, have undergone a polyphase Archaean deformation. Altogether 31 bedrock structures (R-structures) have been modelled at the investigation site, most of them representing steeply dipping fracture zones. The rock mass between the fracture zones represents what is termed `intact rock`, which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 1.6 x 10{sup -7} m{sup 2}/s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval is 8 x 10{sup -12} m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found, for both the R-structures and the intact rock. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater of Romuvaara is classified as fresh water and the Total Dissolved Solids (TDS) and chloride contents increase with depth. The chemically

  2. Site planning for a final nuclear disposal site without rights of action? On the actual draft for a site selection law

    International Nuclear Information System (INIS)

    Wollenteit, Ulrich

    2013-01-01

    'Good' and 'substantial' grounds for determining the location of a Federal final repository by law are not apparent. The acceleration argument from the Stendal decision is not available. The legitimacy argument provides no substantial reason for believing that the implementation of an administrative planning permission hearing or approval procedure is associated with significant disadvantages for the common weal. Thus, there is no justifiable reason for a reduction of legal protection. However, the fundamental right to legal protection guarantee requires that the expropriation may be examined comprehensively on its legality in factual and legal relationship by means of the judiciary power.

  3. Cost and Performance Report for the Tri-Service Site Characterization and Analysis Penetrometer System (SCAPS) Hydrosparge Volatile Organic Compound Sensor

    National Research Council Canada - National Science Library

    Costanza, Jed

    2001-01-01

    Site characterization for subsurface contaminants is time consuming and costly. The Hydrosparge VOC sensor was developed for the Tri-Services Site characterization and Analysis Penetrometer System (SCAPS...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

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

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

    International Nuclear Information System (INIS)

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

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

  6. Radiological surveillance of Remedial Action activities at the processing site, Falls City, Texas. Final report

    International Nuclear Information System (INIS)

    1993-04-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Falls City, Texas. This surveillance was conducted March 22--26, 1993. No findings were identified during the surveillance. Three site-specific observations and three programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Falls City, Texas, remedial action program are performed adequately. However, some of the observations identify that there is potential for improving certain aspects of the occupational radiological air sampling, ensuring analytical data quality, and in communicating with the DOE and TAC on the ore sampling methods. The TAC has also received and is currently reviewing the RAC's responses regarding the observations identified during the radiological surveillance performed October 29--30, 1992

  7. Solar-collector-materials exposure to the IPH site environment. Volume 1. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Morris, V.L.

    1982-01-01

    In-situ environmental exposure tests were conducted at nine proposed intermediate-temperature Industrial Process Heat (IPH) sites. Three types of reflector materials were evaluated for survivability at the nine sites: second-surface silvered glass, aluminized acrylic FEK-244 film on aluminumsubstrate and Alzak (electropolished aluminum) on aluminium substrate. Black chrome absorber material and low-iron float glass were evaluated for thermal, photochemical, and environmental degradation. The reflector specimens were monitored for decreases in specular and hemispherical reflectance due to soil buildup. The absorber material was evaluated for changes in solar absorptivity and emissivity, and the float glass was monitored for changes in transmissivity. Surface and subsurface defects on all materials were examined microscopically and, where deemed of note, were documented photographically.

  8. Final environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendices A-F

    International Nuclear Information System (INIS)

    1996-08-01

    This sitewide EIS evaluates the potential environmental impacts of four possible land-use alternatives being considered for the Nevada Test Site (NTS), the Tonopah Test Range, and the formerly operated DOE sites in the state of Nevada: the Project Shoal Area, the Central Nevada Test Area, and portions of the Nellis Air Force Range Complex. Three additional sites in Nevada-Eldorado Valley, Dry Lake Valley, and Coyote Spring Valley-are evaluated for collocation of solar energy production facilities. The four alternatives include Continue Current Operations (No Action, continue to operate at the level maintained for the past 3 to 5 years); Discontinue Operations 1 (discontinue operations and interagency programs); Expanded Use (increased use of NTS and its resources to support defense and nondefense programs); and Alternate Use of Withdrawn Lands (discontinue all defense-related activities at NTS; continue waste management operations in support of NTS environmental restoration efforts; expand nondefense research). Environmental impacts were assessed for each alternative by analyzing, to the extent possible, the discrete and cumulative environmental impacts associated with Defense Waste Management, Environmental Restoration, Nondefense Research and Development, and Work for Others Programs. A framework for a Resource Management Plan is included as Volume 2 of this EIS and represents the development of an ecosystem based planning process closely integrated with the National Environmental Policy Act process. This EIS, among other things, analyzed the impacts of transportation of low level waste, and site characterization activities related to the Yucca Mountain Project but did not analyze the suitability of the site as a repository. This EIS does not analyze the suitability of the Yucca Mountain site as a repository as this is an action beyond the scope of the EIS. Volume 3 of this EIS contains the public comments and the responses to the comments

  9. Final environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Chapters 1-9

    International Nuclear Information System (INIS)

    1996-08-01

    This sitewide EIS evaluates the potential environmental impacts of four possible land-use alternatives being considered for the Nevada Test Site (NTS), the Tonopah Test Range, and the formerly operated DOE sites in the state of Nevada: the Project Shoal Area, the Central Nevada Test Area, and portions of the Nellis Air Force Range Complex. Three additional sites in Nevada-Eldorado Valley, Dry Lake Valley, and Coyote Spring Valley-are evaluated for collocation of solar energy production facilities. The four alternatives include Continue Current Operations (No Action, continue to operate at the level maintained for the past 3 to 5 years); Discontinue Operations 1 (discontinue operations and interagency programs); Expanded Use (increased use of NTS and its resources to support defense and nondefense programs); and Alternate Use of Withdrawn Lands (discontinue all defense-related activities at NTS; continue waste management operations in support of NTS environmental restoration efforts; expand nondefense research). Environmental impacts were assessed for each alternative by analyzing, to the extent possible, the discrete and cumulative environmental impacts associated with Defense Waste Management, Environmental Restoration, Nondefense Research and Development, and Work for Others Programs. A framework for a Resource Management Plan is included as Volume 2 of this EIS and represents the development of an ecosystem based planning process closely integrated with the National Environmental Policy Act process. This EIS, among other things, analyzed the impacts of transportation of low level waste, and site characterization activities related to the Yucca Mountain Project but did not analyze the suitability of the site as a repository. This EIS does not analyze the suitability of the Yucca Mountain site as a repository as this is an action beyond the scope of the EIS. Volume 3 of this EIS contains the public comments and the responses to the comments

  10. Barometric pressure transient testing applications at the Nevada Test Site: formation permeability analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, J.M.

    1984-12-01

    The report evaluates previous investigations of the gas permeability of the rock surrounding emplacement holes at the Nevada Test Site. The discussion sets the framework from which the present uncertainty in gas permeability can be overcome. The usefulness of the barometric pressure testing method has been established. Flow models were used to evaluate barometric pressure transients taken at NTS holes U2fe, U19ac and U20ai. 31 refs., 103 figs., 18 tabs. (ACR)

  11. Barometric pressure transient testing applications at the Nevada Test Site: formation permeability analysis. Final report

    International Nuclear Information System (INIS)

    Hanson, J.M.

    1984-12-01

    The report evaluates previous investigations of the gas permeability of the rock surrounding emplacement holes at the Nevada Test Site. The discussion sets the framework from which the present uncertainty in gas permeability can be overcome. The usefulness of the barometric pressure testing method has been established. Flow models were used to evaluate barometric pressure transients taken at NTS holes U2fe, U19ac and U20ai. 31 refs., 103 figs., 18 tabs

  12. Botanical inventory of the Rocky Flats AEC site. Final report, April 29, 1976--July 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Webber, P.J.

    1979-04-01

    The present plant life of the Rocky Flats site and surrounding area was documented. This documentation is intended as a base-line description which may be used by researchers and managers. The analysis of natural vegetation, including plant species inventory, vegetation composition study, and identification of major environmental control factors at the Rocky Flats site provides a data base on which future environmental decisions concerning, for example, future construction and handling of disturbance on this site can be made. The establishment of morphological norms for potential plant indicators of mutagenic hazards serves as a start for development of a vegetation-based system for detection of possible changes in plant life induced by accidental plutonium release around the plant. This study is not directed towards assessing any past or present industrial impacts of plutonium processing. The principal products from the contract are a list of vascular plants, bryophytes, and lichens, a 1:12,000 color vegetation map, five large scale (1:500) maps of special study and experimental areas, and a description of the morphological norms of two common vascular plant species.

  13. Learning to forecast wind at remote sites for wind energy applications. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Notis, C.; Trettel, D.W.; Aquino, J.T.; Piazza, T.R.; Taylor, L.E.; Trask, D.C.; Wegley, H.L.; Miller, A.H.

    1983-01-01

    Observed wind patterns are correlated with synoptic or mescoscale weather systems. Six sites selected for analysis include Montauk Point, New York; Boone, North Carolina; Ludington, Michigan; Clayton, New Mexico; Amarillo, Texas; and San Gorgonio Pass, California. Objectives of the analysis are: to identify synoptic and/or mesoscale weather patterns that are associated with recognizable wind events at the sites; to define a set of criteria that uniquely describes such weather patterns; to estimate the reliability (accuracy) of forecasting rules derived from the association of weather patterns and site winds; and to attempt to separate any mesoscale effects of local topography from the synoptic-scale effects. One-to-one mapping of wind regimes onto synoptic types was not found. It was concluded that four factors should be examined when stratifying wind regimes: synoptic situation, descriptive climatology, pressure gradient vector, and winds aloft. The wind forecasting approach developed was intended for forecasting hourly average winds out to the 24 hour or possibly 36 hour time horizon. (LEW)

  14. Evaluation of the need, feasibility, and siting of the MRS in Tennessee. Draft final report

    Energy Technology Data Exchange (ETDEWEB)

    Colglazier, E.W. Jr. [Tennessee Univ., Knoxville, TN (United States)

    1985-12-16

    This summary report outlines the results of an independent assessment of the need, feasibility, and siting of the proposed Monitored Retrievable Storage (MRS) facility. The detailed reports of this assessment are included as appendices to the summary report. The Department of Energy (DOE) has concluded that the MRS is not absolutely necessary, but preferred, in order to manage and move spent fuel from reactors to a repository. The team has attemped to assess ``need`` by comparing to advantages and disadvantages of various systems, with and without the MRS. ``Feasibility has been assessed by comparing the technical and economic advantages and disadvantages. The team was not asked to recommend a preferred system. That choice will depend on the importance that are used to compare alternatives. The five key criteria selected by the team for comparing alternate systems were: economic cost, radiological risk, non-radiological transportation impacts, the likelihood of successful implementation and operation of the system, and the likelihood of meeting the schedule in the Nuclear Waste Policy Act. The team compared twelve different systems and modeled the transportation impacts and risks with three repository sites and two MRS sites.

  15. Energy conserving site design case study, Burke Center, Virginia. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    The pattern of energy consumption within a modern suburban community, Burke Center, is examined. A variety of actions that could be incorporated to reduce its future energy demands is proposed. Recommendations have been limited to those that are technically feasible today, are reasonably cost-effective, and that should generate little or no market resistance. Findings are that: of the total energy consumed by the Burke Center Community, 57% will go to off-site transportation needs; energy conserving site planning generally coincides with cost-effective site planning; water-to-air heat pumps proved to be the most efficient and cost-effective method available today in the study area for reducing heating and cooling costs in buildings; certain public services such as the collection of solid waste, mail pick-up and delivery, and other routine activities can be made more energy efficient; and the use of available water saving devices in residential and commercial buildings can reduce a community's total utility energy consumption by as much as 20%. (MCW)

  16. Site operator program final report for fiscal years 1992 through 1996

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.E. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.; Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Birasco, S. [Los Angeles Dept. of Water and Power, CA (United States)] [and others

    1998-01-01

    The Site Operator Program was an electric vehicle testing and evaluation program sponsored by US Department of Energy and managed at the Idaho National Engineering and Environmental Laboratory. The Program`s goals included the field evaluation of electric vehicles in real-world applications and environments; the support of electric vehicle technology advancement; the development of infrastructure elements necessary to support significant electric vehicle use; and increasing the awareness and acceptance of electric vehicles. This report covers Program activities from 1992 to 1996. The Site Operator Program ended in September 1996, when it was superseded by the Field Operations Program. Electric vehicle testing included baseline performance testing, which was performed in conjunction with EV America. The baseline performance parameters included acceleration, braking, range, energy efficiency, and charging time. The Program collected fleet operations data on electric vehicles operated by the Program`s thirteen partners, comprising electric utilities, universities, and federal agencies. The Program`s partners had over 250 electric vehicles, from vehicle converters and original equipment manufacturers, in their operating fleets. Test results are available via the World Wide Web site at http://ev.inel.gov/sop.

  17. Pilot-scale incineration of comtaminated soils from the drake chemical superfund site. Final report

    International Nuclear Information System (INIS)

    King, C.; Lee, J.W.; Waterland, L.R.

    1993-03-01

    A series of pilot-scale incineration tests were performed at the U.S. Environmental Protection Agency's (EPA's) Incineration Research Facility to evaluate the potential of incineration as an option to treat contaminated soils from the Drake Chemical Superfund site in Lock Haven, Pennsylvania. The soils at the Drake site are reported to be contaminated to varying degrees with various organic constituents and several hazardous constituent trace metals. The purpose of the test program was to evaluate the incinerability of selected site soils in terms of the destruction of contaminant organic constituents and the fate of contaminant trace metals. All tests were conducted in the rotary kiln incineration system at the IRF. Test results show that greater than 99.995 percent principal organic hazardous constituent (POHC) destruction and removal efficiencies (DRE) can be achieved at kiln exit gas temperatures of nominally 816 C (1,500 F) and 538 C (1,000 F). Complete soil decontamination of semivolatile organics was achieved; however, kiln ash levels of three volatile organic constituents remained comparable to soil levels

  18. Surface and subsurface characterization of uranium contamination at the Fernald environmental management site

    International Nuclear Information System (INIS)

    Schilk, A.J.; Perkins, R.W.; Abel, K.H.; Brodzinski, R.L.

    1993-04-01

    The past operations of uranium production and support facilities at several Department of Energy (DOE) sites have occasionally resulted in the local contamination of some surface and subsurface soils, and the three-dimensional distribution of the uranium at these sites must be thoroughly characterized before any effective remedial protocols can be established. To this end, Pacific Northwest Laboratory (PNL) has been tasked by the DOE's Office of Technology Development with adapting, developing, and demonstrating technologies for the measurement of uranium in surface and subsurface soils at the Fernald Uranium in Soils Integrated Demonstration site. These studies are detailed in this report

  19. Atmospheric Characterization of the US Offshore Sites and Impact on Turbine Performance (Poster)

    Energy Technology Data Exchange (ETDEWEB)

    Arora, Dhiraj [Alstom Renewable US LLC; Ehrmann, Robert [Alstom Renewable US LLC; Zuo, Delong [Texas Tech University; Xiao, Jingting [Texas Tech University

    2016-10-25

    Reliable, long term offshore atmospheric data is critical to development of the US offshore wind industry. There exists significant lack of meteorological, oceanographic, and geological data at potential US offshore sites. Assessment of wind resources at heights in the range of 25-200m is needed to understand and characterize offshore wind turbine performance. Data from the US Department of Energy owned WindSentinel buoy from two US offshore sites and one European site is analyzed. Low Level Jet (LLJ) phenomena and its potential impact on the performance of an offshore wind turbine is investigated.

  20. Site characterization progress report, April 1, 1994--September 30, 1994: Yucca Mountain, Nevada. Volume 11

    International Nuclear Information System (INIS)

    1995-03-01

    The Civil Radioactive Waste Management Program was restructured to provide a new approach to the evaluation of the site for development as a repository and to its licensing. Funding was increased for FY 95, with most of the increase going to the Yucca Mountain site characterization project. During this period, significant progress was made in surface-based testing, advanced conceptual design, performance assessment, planning, licensing support system development activities, and construction of the Exploratory Studies Facility. The report is divided into the following sections: introduction, programmatic activities, site programs, repository design, waste package, performance assessment, and exploratory studies facility design/construction

  1. Final disposal of spent nuclear fuel in Finnish bedrock. Olkiluoto site report

    International Nuclear Information System (INIS)

    Anttila, P.; Ahokas, H.; Front, K.

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Haestholmen in Loviisa, Kivetty in Aeaenekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto. The bedrock of the Olkiluoto site consists of Svecofennian metasediments and platonic rocks, 1800-1900 million years in age. Migmatitic mica gneiss is the most abundant rock type, and is intruded by foliated tonalites and granodiorites and massive coarse-grained granites and pegmatites. Five successive plastic deformation phases have been defined. In total, 30 bedrock structures (R-structures) have been modelled at the site. Most of these represent steeply dipping fracture zones, but several sub-horizontal zones, gently dipping to the SE, have also been identified. The rock mass between the fracture zones represents what is termed 'intact rock', which is typically hard, unweathered and sparsely fractured. The R-structures are generally hydraulically more conductive than the intact rock and their mean transmissivity is 3 x 10 -7 m 2 /s. The corresponding mean of the hydraulic conductivity values for the intact rock measured using a 2 m packer interval, is 8 x 10 -13 m/s, if a lognormal distribution for all measured values is assumed. A clear decrease in hydraulic conductivity with depth has been found for the intact rock, and there seems to be a parallel decrease in the transmissivity of structures. In addition, the hydraulically conductive fractures seem to be more frequent and their transmissivities higher in the uppermost 100 - 200 m of the bedrock than at greater depths. The groundwater chemistry reflects the postglacial

  2. Final disposal of spent nuclear fuel in Finnish bedrock. Olkiluoto site report

    Energy Technology Data Exchange (ETDEWEB)

    Anttila, P. [Fortum Engineering Oy, Vantaa (Finland); Ahokas, H. [Fintact Oy, Helsinki (Finland); Front, K. [VTT Communication and Infrastructure, Espoo (Finland)] [and others

    1999-06-01

    Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of S