Sample records for disposition project volume

  1. Legacy sample disposition project. Volume 2: Final report

    SciTech Connect (OSTI)

    Gurley, R.N.; Shifty, K.L.

    1998-02-01T23:59:59.000Z

    This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions.

  2. Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project

    SciTech Connect (OSTI)

    J. T. Beck

    2007-04-26T23:59:59.000Z

    This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities.

  3. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford nuclear reservation. Workers had to pass through metal detectors when they arrived at the plant and materials leaving the plant had to be scanned for security reasons. Whereas other high-security nuclear materials were shipped from the PFP to Savannah River, S.C. as part ofa Department of Energy (DOE) program to consolidate weapons-grade plutonium, it was determined that the SIF should remain onsite pending disposition to a national repository. Nevertheless, the SIF still requires a high level of security that the PFP complex has always provided. With the 60-year PFP mission of producing and storing plutonium concluded, the environmental cleanup plans for Hanford call for the demolition of the 63-building PFP complex. Consequently, if the SIF remained at PFP it not only would have interfered with the environmental cleanup plans, but would have required $100 million in facility upgrades to meet increased national security requirements imposed after the 9/11 terrorist attacks. A new smaller and more cost-effective area was needed to store this material, which led to the SIF Project. Once the SIF project was successfully completed and the SIF was safely removed from PFP, the existing Protected Area at PFP could be removed, and demolition could proceed more quickly without being encumbered by restrictive security requirements that an active Protected Area requires. The lightened PFP security level brought by safely removing and storing the SIF would also yield lowered costs for deactivation and demolition, as well as reduce overall life-cycle costs.

  4. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  5. Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

    SciTech Connect (OSTI)

    Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

    1993-06-01T23:59:59.000Z

    The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

  6. DOE Plutonium Disposition Study: Pu consumption in ALWRs. Volume 1, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15T23:59:59.000Z

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U0{sub 2} plant design is discussed here.

  7. DOE plutonium disposition study: Pu consumption in ALWRs. Volume 2, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15T23:59:59.000Z

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

  8. Major Risk Factors Integrated Facility Disposition Project - Oak Ridge

    Office of Environmental Management (EM)

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  9. WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |

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

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  10. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    1999-08-24T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2018 are projected based on assumption as of July 1999. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement.

  11. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    2000-08-28T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

  12. Operational waste volume projection

    SciTech Connect (OSTI)

    Koreski, G.M.

    1996-09-20T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June 1996.

  13. Major Risk Factors to the Integrated Facility Disposition Project |

    Office of Environmental Management (EM)

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  14. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  15. Evaluation of Possible Surrogates for Validation of the Oxidation Furnace for the Plutonium Disposition Project

    SciTech Connect (OSTI)

    Duncan, A.

    2007-12-31T23:59:59.000Z

    The Plutonium Disposition project (PuD) is considering an alternative furnace design for direct metal oxidation (DMO) of plutonium metal to use as a feed for potential disposition routes. The proposed design will use a retort to oxidize the feed at temperatures up to 500 C. The atmosphere will be controlled using a metered mixture of oxygen, helium and argon to control the oxidation at approximately 400 torr. Since plutonium melts at 664 C, and may potentially react with retort material to form a lower melting point eutectic, the oxidation process will be controlled by metering the flow of oxygen to ensure that the bulk temperature of the material does not exceed this temperature. A batch processing time of <24 hours is desirable to meet anticipated furnace throughput requirements. The design project includes demonstration of concept in a small-scale demonstration test (i.e., small scale) and validation of design in a full-scale test. These tests are recommended to be performed using Pu surrogates due to challenges in consideration of the nature of plutonium and operational constraints required when handling large quantities of accountable material. The potential for spreading contamination and exposing workers to harmful levels of cumulative radioactive dose are motivation to utilize non-radioactive surrogates. Once the design is demonstrated and optimized, implementation would take place in a facility designed to accommodate these constraints. Until then, the use of surrogates would be a safer, less expensive option for the validation phase of the project. This report examines the potential for use of surrogates in the demonstration and validation of the DMO furnace for PuD. This report provides a compilation of the technical information and process requirements for the conversion of plutonium metal to oxide by burning in dry environments. Several potential surrogates were evaluated by various criteria in order to select a suitable candidate for large scale demonstration. First, the structure of the plutonium metal/oxide interface was compared to potential surrogates. Second the data for plutonium oxidation kinetics were reviewed and rates for oxidation were compared with surrogates. The criteria used as a basis for recommendation was selected in order to provide a reasonable oxidation rate during the validation phase. Several reference documents were reviewed and used to compile the information in this report. Since oxidation of large monolithic pieces of plutonium in 75% oxygen is the preferable oxidizing atmosphere for the intended process, this report does not focus on the oxidation of powders, but focuses instead on larger samples in flowing gas.

  16. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09T23:59:59.000Z

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of th

  17. Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 1, Environmental Assessment

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    DOE is deactivating the PUREX plant at Hanford; this will involve the disposition of about 692,000 liters (183,000 gallons) of surplus nitric acid contaminated with low levels of U and other radionuclides. The nitric acid, designated as low specific activity, is stored in 4 storage tanks at PUREX. Five principal alternatives were evaluated: transfer for reuse (sale to BNF plc), no action, continued storage in Hanford upgraded or new facility, consolidation of DOE surplus acid, and processing the LSA nitric acid as waste. The transfer to BNF plc is the preferred alternative. From the analysis, it is concluded that the proposed disposition and transportation of the acid does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

  18. Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 2, Environmental Assessment

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    This volume consists of two appendices: public comments and DOE responses, and public comments not requiring responses.

  19. Session 35 - Panel: Remaining US Disposition Issues for Orphan or Small Volume Low Level and Low Level Mixed Waste Streams

    SciTech Connect (OSTI)

    Blauvelt, Richard [Navarro Engineering Research Inc. (United States); Small, Ken [Doe Nevada (United States); Gelles, Christine [DOE EM HQ (United States); McKenney, Dale [Fluor Hanford (United States); Franz, Bill [LATA Portsmouth (United States); Loveland, Kaylin [Energy Solutions Inc. (United States); Lauer, Mike [Waste Control Specialists (United States)

    2006-07-01T23:59:59.000Z

    Faced with closure schedules as a driving force, significant progress has been made during the last 2 years on the disposition of DOE mixed waste streams thought previously to be problematic. Generators, the Department of Energy and commercial vendors have combined to develop unique disposition paths for former orphan streams. Recent successes and remaining issues will be discussed. The session will also provide an opportunity for Federal agencies to share lessons learned on low- level and mixed low-level waste challenges and identify opportunities for future collaboration. This panel discussion was organized by PAC member Dick Blauvelt, Navarro Research and Engineering Inc who served as co-chair along with Dave Eaton from INL. In addition, George Antonucci, Duratek Barnwell and Rich Conley, AFSC were invited members of the audience, prepared to contribute the Barnwell and DOD perspective to the issues as needed. Mr. Small provide information regarding the five year 20K M3 window of opportunity at the Nevada Test Site for DOE contractors to dispose of mixed waste that cannot be received at the Energy Solutions (Envirocare) site in Utah because of activity levels. He provided a summary of the waste acceptance criteria and the process sites must follow to be certified to ship. When the volume limit or time limit is met, the site will undergo a RCRA closure. Ms. Gelles summarized the status of the orphan issues, commercial options and the impact of the EM reorganization on her program. She also announced that there would be a follow-on meeting in 2006 to the very successful St. Louis meeting of last year. It will probably take place in Chicago in July. Details to be announced. Mr. McKenney discussed progress made at the Hanford Reservation regarding disposal of their mixed waste inventory. The news is good for the Hanford site but not good for the rest of the DOE complex since shipment for out of state of both low level and low level mixed waste will continue to be prohibited until the completion of a new NEPA study. This is anticipated to take several years. Bill Franz from Portsmouth and Dave Eaton representing the INL provided the audience with information regarding some of the problematic mixed waste streams at their respective sites. Portsmouth has some unique radiological issues with isotopes such as Tc-99 while the INL is trying to deal with mixed waste in the 10-100 nCi/g range. Kaylin Loveland spoke of the new,Energy Solutions organization and provided information on mixed waste treatment capabilities at the Clive site. Mike Lauer described the licensing activities at the WCS site in Texas where they are trying to eventually have disposal capabilities for Class A, B and C mixed waste from both DOE and the commercial sector. The audience included about 75 WM'06 attendees who asked some excellent questions and provided an active and informative exchange of information on the topic. (authors)

  20. West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement

    Office of Environmental Management (EM)

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  1. Records Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1988-09-13T23:59:59.000Z

    To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its management and operating contractors. Cancels DOE O 1324.2 dated 5-28-80. Chg 1 dated 4-9-92. Canceled by DOE O 1324.2B dated 1-12-95.

  2. Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project

    SciTech Connect (OSTI)

    Reynolds, T. D.; Easterling, S. D.

    2010-10-01T23:59:59.000Z

    This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

  3. Weapons-grade plutonium dispositioning. Volume 3: A new reactor concept without uranium or thorium for burning weapons-grade plutonium

    SciTech Connect (OSTI)

    Ryskamp, J.M.; Schnitzler, B.G.; Fletcher, C.D. [and others

    1993-06-01T23:59:59.000Z

    The National Academy of Sciences (NAS) requested that the Idaho National Engineering Laboratory (INEL) examine concepts that focus only on the destruction of 50,000 kg of weapons-grade plutonium. A concept has been developed by the INEL for a low-temperature, low-pressure, low-power density, low-coolant-flow-rate light water reactor that destroys plutonium quickly without using uranium or thorium. This concept is very safe and could be designed, constructed, and operated in a reasonable time frame. This concept does not produce electricity. Not considering other missions frees the design from the paradigms and constraints used by proponents of other dispositioning concepts. The plutonium destruction design goal is most easily achievable with a large, moderate power reactor that operates at a significantly lower thermal power density than is appropriate for reactors with multiple design goals. This volume presents the assumptions and requirements, a reactor concept overview, and a list of recommendations. The appendices contain detailed discussions on plutonium dispositioning, self-protection, fuel types, neutronics, thermal hydraulics, off-site radiation releases, and economics.

  4. Records Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1980-05-28T23:59:59.000Z

    To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its operating and onsite service contractors. Cancels DOE O 1324.1 dated 7-10-78. Chg 1 dated 7-2-81. Chg 2 dated 11-9-82. Canceled by DOE O 1324.2A dated 9-13-88.

  5. Facility Disposition Projects

    Office of Environmental Management (EM)

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  6. Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 1 (CDP)

    Office of Environmental Management (EM)

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  7. Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 2 (CDP)

    Office of Environmental Management (EM)

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  8. Portsmouth Proposed Plan for the Site-wide Waste Disposition...

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

    Proposed Plan for the Site-wide Waste Disposition Evaluation Project DOE has evaluated alternatives for managing waste that would be created by decomtamination and...

  9. Nuclear carrier business volume projections, 1980-2000

    SciTech Connect (OSTI)

    Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

    1980-05-01T23:59:59.000Z

    The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U/sub 3/O/sub 8/); natural, enriched and reprocessed uranium hexafluoride (UF/sub 6/); uranium dioxide powder (UO/sub 2/); plutonium dioxide powder (PuO/sub 2/); fresh UO/sub 2/ and mixed oxide (MOX) fuel; spent UO/sub 2/ fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO/sub 2/ fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991.

  10. INDEPENDENT TECHNICAL ASSESSMENT OF MANAGEMENT OF STORMWATER AND WASTEWATER AT THE SEPARATIONS PROCESS RESEARCH UNIT (SPRU) DISPOSITION PROJECT, NEW YORK

    SciTech Connect (OSTI)

    Abitz, R.; Jackson, D.; Eddy-Dilek, C.

    2011-06-27T23:59:59.000Z

    The U.S. Department of Energy (DOE) is currently evaluating the water management procedures at the Separations Process Research Unit (SPRU). The facility has three issues related to water management that require technical assistance: (1) due to a excessive rainfall event in October, 2010, contaminated water collected in basements of G2 and H2 buildings. As a result of this event, the contractor has had to collect and dispose of water offsite; (2) The failure of a sump pump at a KAPL outfall resulted in a Notice of Violation issued by the New York State Department of Environment and Conservation (NYSDEC) and subsequent Consent Order. On-site water now requires treatment and off-site disposition; and (3) stormwater infiltration has resulted in Strontium-90 levels discharged to the storm drains that exceed NR standards. The contractor has indicated that water management at SPRU requires major staff resources (at least 50 persons). The purpose of this review is to determine if the contractor's technical approach warrants the large number of staff resources and to ensure that the technical approach is compliant and in accordance with federal, state and NR requirements.

  11. CleanFleet. Volume 2, Project Design and Implementation

    SciTech Connect (OSTI)

    NONE

    1995-12-01T23:59:59.000Z

    The CleanFleet alternative fuels demonstration project evaluated five alternative motorfuels in commercial fleet service over a two-year period. The five fuels were compressed natural gas, propane gas, California Phase 2 reformulated gasoline (RFG), M-85 (85 percent methanol and 15 percent RFG), and electric vans. Eight-four vans were operated on the alternative fuels and 27 vans were operated on gasoline as baseline controls. Throughout the demonstration information was collected on fleet operations, vehicle emissions, and fleet economics. In this volume of the CleanFleet findings, the design and implementation of the project are summarized.

  12. Breckinridge Project, initial effort. Report III, Volume 2. Specifications

    SciTech Connect (OSTI)

    none,

    1982-01-01T23:59:59.000Z

    Report III, Volume 2 contains those specifications numbered K through Y, as follows: Specifications for Compressors (K); Specifications for Piping (L); Specifications for Structures (M); Specifications for Insulation (N); Specifications for Electrical (P); Specifications for Concrete (Q); Specifications for Civil (S); Specifications for Welding (W); Specifications for Painting (X); and Specifications for Special (Y). The standard specifications of Bechtel Petroleum Incorporated have been amended as necessary to reflect the specific requirements of the Breckinridge Project and the more stringent specifications of Ashland Synthetic Fuels, Inc. These standard specifications are available for the Initial Effort (Phase Zero) work performed by all contractors and subcontractors.

  13. Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

    SciTech Connect (OSTI)

    Womack, J.C. [Westinghouse Hanford Co., Richland, WA (United States); Cramond, R. [TRW (United States); Paedon, R.J. [SAIC (United States)] [and others

    1995-03-13T23:59:59.000Z

    This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also.

  14. Revised SRC-I project baseline. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1984-01-01T23:59:59.000Z

    International Coal Refining Company (ICRC), in cooperation with the Commonwealth of Kentucky has contracted with the United States Department of Energy (DOE) to design, build and operate a first-of-its-kind plant demonstrating the economic, environmental, socioeconomic and technical feasibility of the direct coal liquefaction process known as SRC-I. ICRC has made a massive commitment of time and expertise to design processes, plan and formulate policy, schedules, costs and technical drawings for all plant systems. These fully integrated plans comprise the Project Baseline and are the basis for all future detailed engineering, plant construction, operation, and other work set forth in the contract between ICRC and the DOE. Volumes I and II of the accompanying documents constitute the updated Project Baseline for the SRC-I two-stage liquefaction plant. International Coal Refining Company believes this versatile plant design incorporates the most advanced coal liquefaction system available in the synthetic fuels field. SRC-I two-stage liquefaction, as developed by ICRC, is the way of the future in coal liquefaction because of its product slate flexibility, high process thermal efficiency, and low consumption of hydrogen. The SRC-I Project Baseline design also has made important state-of-the-art advances in areas such as environmental control systems. Because of a lack of funding, the DOE has curtailed the total project effort without specifying a definite renewal date. This precludes the development of revised accurate and meaningful schedules and, hence, escalated project costs. ICRC has revised and updated the original Design Baseline to include in the technical documentation all of the approved but previously non-incorporated Category B and C and new Post-Baseline Engineering Change Proposals.

  15. Used Fuel Disposition Campaign Preliminary Quality Assurance...

    Energy Savers [EERE]

    Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary...

  16. LIFAC sorbent injection desulfurization demonstration project. Final report, volume II: Project performance and economics

    SciTech Connect (OSTI)

    NONE

    1996-01-01T23:59:59.000Z

    This publication discusses the demonstration of the LIFAC sorbent injection technology at Richmond Power and Light`s Whitewater Valley Unit No. 2, performed under the auspices of the U.S. Department of Energy`s (DOE) Clean Coal Technology Program. LIFAC is a sorbent injection technology capable of removing 75 to 85 percent of a power plant`s SO{sub 2} emissions using limestone at calcium to sulfur molar ratios of between 2 and 2.5 to 1. The site of the demonstration is a coal-fired electric utility power plant located in Richmond, Indiana. The project is being conducted by LIFAC North America (LIFAC NA), a joint venture partnership of Tampella Power Corporation and ICF Kaiser Engineers, in cooperation with DOE, RP&L, and Research Institute (EPRI), the State of Indiana, and Black Beauty Coal Company. The purpose of Public Design Report Volume 2: Project Performance and Economics is to consolidate, for public use, the technical efficiency and economy of the LIFAC Process. The report has been prepared pursuant to the Cooperative Agreement No. DE-FC22-90PC90548 between LIFAC NA and the U.S. Department of Energy.

  17. Solid Waste Operations Complex W-113: Project cost estimate. Preliminary design report. Volume IV

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    This document contains Volume IV of the Preliminary Design Report for the Solid Waste Operations Complex W-113 which is the Project Cost Estimate and construction schedule. The estimate was developed based upon Title 1 material take-offs, budgetary equipment quotes and Raytheon historical in-house data. The W-113 project cost estimate and project construction schedule were integrated together to provide a resource loaded project network.

  18. Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

    SciTech Connect (OSTI)

    Fulton, J.C.

    1994-10-01T23:59:59.000Z

    Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II.

  19. Clean Coal Technology Programs: Completed Projects (Volume 2)

    SciTech Connect (OSTI)

    Assistant Secretary for Fossil Energy

    2003-12-01T23:59:59.000Z

    Annual report on the Clean Coal Technology Demonstration Program (CCTDP), Power Plant Improvement Initiative (PPII), and Clean Coal Power Initiative (CCPI). The report addresses the roles of the programs, implementation, funding and costs, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

  20. america project volume: Topics by E-print Network

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

    Europe Latin America & Caribbean Middle East & Central Asia Asia Pacific Africa Impact Johnson, Matthew 56 Impact Assessment and Project Appraisal September 2003 1461-551703...

  1. EM Waste and Materials Disposition & Transportation | Department...

    Office of Environmental Management (EM)

    EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

  2. Secretary's annual report to Congress. Volume III. Project summaries

    SciTech Connect (OSTI)

    None

    1981-01-01T23:59:59.000Z

    Progress and status of representative projects in each program within DOE are summarized. Subjects covered and the number of projects reported on are: conservation (2); fossil energy (11); nuclear energy (5); renewable energy resources (16); energy production and power marketing (3); general science (11); defense programs (7); contingency planning (3); and management and oversight (1). (MCW)

  3. Ukraine Kievenergo district heating project. Volume 1. Export trade information

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    This study, conducted by Joseph Technolgoy Corporation, was funded by the U.S. Trade and Development Agency. The purpose of this study was directed toward increasing the heat capacity, reducing fuel costs and import requirements, bringing about energy efficiency in the Kiev District Heating (DH) system; improving environmental conditions in affected areas; and supporting the strengthening and restructuring of Kiev, DH institutions and development of the DH sector. The report lists project risks and offers recommendations to minimize these risks. Also included are detailed cost estimates and financial analyses. The report is divided into the following sections: (1) Acknowledgement, (2) Project Summary, (3) Abbreviations, (4) I. Sector Background and Objectives, (5) II. The Project, (6) III. Implementing Agencies, (7) IV. Financial Aspects, (8) V. Project Benefits and Risks, (9) VI. Agreements to be Reached and Recommendations, (10) Annexes.

  4. Renewable Resources: a national catalog of model projects. Volume 4. Western Solar Utilization Network Region

    SciTech Connect (OSTI)

    None

    1980-07-01T23:59:59.000Z

    This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Western Solar Utilization Network Region. (WHK)

  5. Renewable Resources: a national catalog of model projects. Volume 3. Southern Solar Energy Center Region

    SciTech Connect (OSTI)

    None

    1980-07-01T23:59:59.000Z

    This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Southern Solar Energy Center Region. (WHK)

  6. Renewable Resources: a national catalog of model projects. Volume 1. Northeast Solar Energy Center Region

    SciTech Connect (OSTI)

    None

    1980-07-01T23:59:59.000Z

    This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Northeast Solar Energy Center Region. (WHK).

  7. Final Technical Report - Kotzebue Wind Power Project - Volume II

    SciTech Connect (OSTI)

    Rana Zucchi, Global Energy Concepts, LLC; Brad Reeve, Kotzebue Electric Association; DOE Project Officer - Doug Hooker

    2007-10-31T23:59:59.000Z

    The Kotzebue Wind Power Project is a joint undertaking of the U.S. Department of Energy (DOE); Kotzebue Electric Association (KEA); and the Alaska Energy Authority (AEA). The goal of the project is to develop, construct, and operate a wind power plant interconnected to a small isolated utility grid in an arctic climate in Northwest Alaska. The primary objective of KEA’s wind energy program is to bring more affordable electricity and jobs to remote Alaskan communities. DOE funding has allowed KEA to develop a multi-faceted approach to meet these objectives that includes wind project planning and development, technology transfer, and community outreach. The first wind turbines were installed in the summer of 1997 and the newest turbines were installed in the spring of 2007. The total installed capacity of the KEA wind power project is 1.16 MW with a total of 17 turbines rated between 65 kW and 100 kW. The operation of the wind power plant has resulted in a wind penetration on the utility system in excess of 35% during periods of low loads. This document and referenced attachments are presented as the final technical report for the U.S. Department of Energy (DOE) grant agreement DE-FG36-97GO10199. Interim deliverables previously submitted are also referenced within this document and where reasonable to do so, specific sections are incorporated in the report or attached as appendices.

  8. Environmental information volume: Liquid Phase Methanol (LPMEOH{trademark}) project

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    The purpose of this project is to demonstrate the commercial viability of the Liquid Phase Methanol Process using coal-derived synthesis gas, a mixture of hydrogen and carbon monoxide. This report describes the proposed actions, alternative to the proposed action, the existing environment at the coal gasification plant at Kingsport, Tennessee, environmental impacts, regulatory requirements, offsite fuel testing, and DME addition to methanol production. Appendices include the air permit application, solid waste permits, water permit, existing air permits, agency correspondence, and Eastman and Air Products literature.

  9. SLUDGE TREATMENT PROJECT ALTERNATIVES ANALYSIS SUMMARY REPORT [VOLUME 1

    SciTech Connect (OSTI)

    FREDERICKSON JR; ROURK RJ; HONEYMAN JO; JOHNSON ME; RAYMOND RE

    2009-01-19T23:59:59.000Z

    Highly radioactive sludge (containing up to 300,000 curies of actinides and fission products) resulting from the storage of degraded spent nuclear fuel is currently stored in temporary containers located in the 105-K West storage basin near the Columbia River. The background, history, and known characteristics of this sludge are discussed in Section 2 of this report. There are many compelling reasons to remove this sludge from the K-Basin. These reasons are discussed in detail in Section1, and they include the following: (1) Reduce the risk to the public (from a potential release of highly radioactive material as fine respirable particles by airborne or waterborn pathways); (2) Reduce the risk overall to the Hanford worker; and (3) Reduce the risk to the environment (the K-Basin is situated above a hazardous chemical contaminant plume and hinders remediation of the plume until the sludge is removed). The DOE-RL has stated that a key DOE objective is to remove the sludge from the K-West Basin and River Corridor as soon as possible, which will reduce risks to the environment, allow for remediation of contaminated areas underlying the basins, and support closure of the 100-KR-4 operable unit. The environmental and nuclear safety risks associated with this sludge have resulted in multiple legal and regulatory remedial action decisions, plans,and commitments that are summarized in Table ES-1 and discussed in more detail in Volume 2, Section 9.

  10. Used Fuel Disposition Campaign Disposal Research and Development...

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

    & Publications Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign International Activities Implementation Plan Review of...

  11. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    SciTech Connect (OSTI)

    Greene, S.R.; Fisher, S.E.; Bevard, B.B. [and others

    1996-09-01T23:59:59.000Z

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

  12. FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

    SciTech Connect (OSTI)

    Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

    1996-09-01T23:59:59.000Z

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

  13. ASEAN--USAID Buildings Energy Conservation Project final report. Volume 2, Technology

    SciTech Connect (OSTI)

    Levine, M.D.; Busch, J.F. [eds.

    1992-06-01T23:59:59.000Z

    This volume reports on research in the area of energy conservation technology applied to commercial buildings in the Association of Southeast Asian Nations (ASEAN) region. Unlike Volume I of this series, this volume is a compilation of original technical papers prepared by different authors in the project. In this regard, this volume is much like a technical journal. The papers that follow report on research conducted by both US and ASEAN researchers. The authors representing Indonesia, Malaysia, Philippines, and Thailand, come from a range of positions in the energy arena, including government energy agencies, electric utilities, and universities. As such, they account for a wide range of perspectives on energy problems and the role that technology can play in solving them. This volume is about using energy more intelligently. In some cases, the effort is towards the use of more advanced technologies, such as low-emittance coatings on window glass, thermal energy storage, or cogeneration. In others, the emphasis is towards reclaiming traditional techniques for rendering energy services, but in new contexts such as lighting office buildings with natural light, or cooling buildings of all types with natural ventilation. Used in its broadest sense, the term ``technology`` encompasses all of the topics addressed in this volume. Along with the more customary associations of technology, such as advanced materials and equipment and the analysis of their performance, this volume treats design concepts and techniques, analysis of ``secondary`` impacts from applying technologies (i.e., unintended impacts, or impacts on parties not directly involved in the purchase and use of the technology), and the collection of primary data used for conducting technical analyses.

  14. Wind-electric icemaking project: Analysis and dynamometer testing. Volume 2

    SciTech Connect (OSTI)

    Holz, R.; Gervorgian, V.; Drouilhet, S.; Muljadi, E.

    1998-07-01T23:59:59.000Z

    The wind/hybrid systems group at the National Renewable Energy Laboratory has been researching the most practical and cost-effective methods for producing ice from off-grid wind-electric power systems. The first phase of the project, conducted in 1993--1994, included full-scale dynamometer and field testing of two different electric ice makers directly connected to a permanent magnet alternator. The results of that phase were encouraging and the second phase of the project was launched in which steady-state and dynamic numerical models of these systems were developed and experimentally validated. The third phase of the project was the dynamometer testing of the North Star ice maker, which is powered by a 12-kilowatt Bergey Windpower Company, Inc., alternator. This report describes both the second and third project phases. Also included are detailed economic analyses and a discussion of the future prospects of wind-electric ice-making systems. The main report is contained in Volume 1. Volume 2 consists of the report appendices, which include the actual computer programs used in the analysis and the detailed test results.

  15. Wind-electric icemaking project: Analysis and dynamometer testing. Volume 1

    SciTech Connect (OSTI)

    Holz, R.; Gervorgian, V.; Drouilhet, S.; Muljadi, E.

    1998-07-01T23:59:59.000Z

    The wind/hybrid systems group at the National Renewable Energy Laboratory has been researching the most practical and cost-effective methods for producing ice from off-grid wind-electric power systems. The first phase of the project, conducted in 1993--1994, included full-scale dynamometer and field testing of two different electric ice makers directly connected to a permanent magnet alternator. The results of that phase were encouraging and the second phase of the project was launched in which steady-state and dynamic numerical models of these systems were developed and experimentally validated. The third phase of the project was the dynamometer testing of the North Star ice maker, which is powered by a 12-kilowatt Bergey Windpower Company, Inc., alternator. This report describes both the second and third project phases. Also included are detailed economic analyses and a discussion of the future prospects of wind-electric ice-making systems. The main report is contained in Volume 1. Volume 2 consists of the report appendices, which include the actual computer programs used in the analysis and the detailed test results.

  16. Advanced Flue Gas Desulfurization (AFGD) demonstration project: Volume 2, Project performance and economics. Final technical report

    SciTech Connect (OSTI)

    NONE

    1996-04-30T23:59:59.000Z

    The project objective is to demonstrate removal of 90--95% or more of the SO{sub 2} at approximately one-half the cost of conventional scrubbing technology; and to demonstrate significant reduction of space requirements. In this project, Pure Air has built a single SO{sub 2} absorber for a 528-MWe power plant. The absorber performs three functions in a single vessel: prequencher, absorber, and oxidation of sludge to gypsum. Additionally, the absorber is of a co- current design, in which the flue gas and scrubbing slurry move in the same direction and at a relatively high velocity compared to conventional scrubbers. These features all combine to yield a state- of-the-art SO{sub 2} absorber that is more compact and less expensive than conventional scrubbers. The project incorporated a number of technical features including the injection of pulverized limestone directly into the absorber, a device called an air rotary sparger located within the base of the absorber, and a novel wastewater evaporation system. The air rotary sparger combines the functions of agitation and air distribution into one piece of equipment to facilitate the oxidation of calcium sulfite to gypsum. Additionally, wastewater treatment is being demonstrated to minimize water disposal problems inherent in many high-chloride coals. Bituminous coals primarily from the Indiana, Illinois coal basin containing 2--4.5% sulfur were tested during the demonstration. The Advanced Flue Gas Desulfurization (AFGD) process has demonstrated removal of 95% or more of the SO{sub 2} while providing a commercial gypsum by-product in lieu of solid waste. A portion of the commercial gypsum is being agglomerated into a product known as PowerChip{reg_sign} gypsum which exhibits improved physical properties, easier flowability and more user friendly handling characteristics to enhance its transportation and marketability to gypsum end-users.

  17. Integration of Environment, Safety, and Health into Facility Disposition Activities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1998-05-01T23:59:59.000Z

    Volume One of this Standard has been revised to provide a Department of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities that involve work not done within a permanent structure. Methodologies provided in this Standard are intended to be compliant with Title 10 of the Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management, Subpart B, Safety Basis Requirements. Volume Two contains the appendices that provide additional environment, safety and health (ES&H) information to complement Volume 1 of this Standard. Volume 2 of the Standard is much broader in scope than Volume 1 and satisfies several purposes. Integrated safety management expectations are provided in accordance with facility disposition requirements contained in DOE O 430.1B, Real Property Asset Management.

  18. 1980 survey and evaluation of utility conservation, load management, and solar end-use projects. Volume 3: utility load management projects. Final report

    SciTech Connect (OSTI)

    Not Available

    1982-01-01T23:59:59.000Z

    The results of the 1980 survey of electric utility-sponsored energy conservation, load management, and end-use solar energy conversion projects are described. The work is an expansion of a previous survey and evaluation and has been jointly sponsored by EPRI and DOE through the Oak Ridge National Laboratory. There are three volumes and a summary document. Each volume presents the results of an extensive survey to determine electric utility involvement in customer-side projects related to the particular technology (i.e., conservation, solar, or load management), selected descriptions of utility projects and results, and first-level technical and economic evaluations.

  19. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 3: Corrosion and data modeling

    SciTech Connect (OSTI)

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

    1995-08-01T23:59:59.000Z

    This three-volume report serves several purposes. The first volume provides an introduction to the engineered materials effort for the Yucca Mountain Site Characterization Project. It defines terms and outlines the history of selection and characterization of these materials. A summary of the recent engineered barrier materials characterization workshop is presented, and the current candidate materials are listed. The second volume tabulates design data for engineered materials, and the third volume is devoted to corrosion data, radiation effects on corrosion, and corrosion modeling. The second and third volumes are intended to be evolving documents, to which new data will be added as they become available from additional studies. The initial version of Volume 3 is devoted to information currently available for environments most similar to those expected in the potential Yucca Mountain repository. This is volume three.

  20. Major Risk Factors Integrated Facility Disposition Project -...

    Office of Environmental Management (EM)

    through private property to waters of the State of Tennessee, and its uptake by fish, plants, and other animal life. DOE, regulators, and the public need to have reasonable...

  1. Summary - Uranium233 Downblending and Disposition Project

    Office of Environmental Management (EM)

    Product EM wa in Buil to extr from 23 downb mitigat concer dispos downb WIPP condu the "ba allowin assess techno The as Techn Techn * An * C (T * Pr * O The Ele Site: O roject: 2 P...

  2. Uranium Downblending and Disposition Project Technology Readiness

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group current C3EDepartment of Energy Office ofStephanieMaterial

  3. Savannah River Site Waste Disposition Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSARDevelopmentalEfficiency |91-51-SW State SouthTerrel J. Spears

  4. Summary - Uranium233 Downblending and Disposition Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the Passing of AdmiraltheOil and LessOak Ridge,SRSTank

  5. 2015-04-10 Capital Asset Project List.xls

    Energy Savers [EERE]

    Spent Fuel Facility (ISFF) Project 9302020 On Hold Pre CD-2 CD-0 560,000,000 Idaho National Laboratory IFDP Integrated Facility Disposition Project (IFDP) 12312015 Active...

  6. Weapons Dismantlement and Disposition NNSS Capabilities

    SciTech Connect (OSTI)

    Pat Arnold

    2011-12-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

  7. Personal Property Disposition - Community Reuse Organizations...

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

    Owen (signed) Director, Office of Worker and Community Transition Department of Energy Washington, DC 20505 January 22, 2003 Disposition of Excess Personal Property...

  8. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  9. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  10. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    SciTech Connect (OSTI)

    None

    1980-12-01T23:59:59.000Z

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume.

  11. Renewable Resources: a national catalog of model projects. Volume 2. Mid-American Solar Energy Complex Region

    SciTech Connect (OSTI)

    None

    1980-07-01T23:59:59.000Z

    This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Mid-American Solar Energy Complex Region. (WHK)

  12. Naval Petroleum Reserve No. 3 Disposition Decision Analysis and...

    Energy Savers [EERE]

    Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline This Report to Congress provides a...

  13. Radium Disposition Options for the Department of Energy

    SciTech Connect (OSTI)

    Parks, D. L.; Thiel, E. C.; Seidel, B. R.

    2002-02-26T23:59:59.000Z

    The Department of Energy (DOE) has developed plans to disposition its excess nuclear materials, including radium-containing materials. Within DOE, there is no significant demand for radium at this time. However, DOE is exploring reuse options, including uses that may not exist at this time. The Nonactinide Isotopes and Sealed Sources Management Group (NISSMG) has identified 654 radium-containing items, and concluded that there are no remaining radium items that do not have a pathway to disposition. Unfortunately, most of these pathways end with disposal, whereas reuse would be preferable. DOE has a number of closure sites that must remove the radium at their sites as part of their closure activities. NISSMG suggests preserving the larger radium sources that can easily be manufactured into targets for future reuse, and disposing the other items. As alternatives to disposal, there exist reuse options for radium, especially in nuclear medicine. These options were identified by NISSMG. The NISSMG recommends that DOE set up receiver sites to store these radium materials until reuse options become available. The NISSMG recommends two pathways for dispositioning radium sources, depending on the activity and volume of material. Low activity radium sources can be managed as low level radioactive waste per DOE Order 5820.2A. Higher activity radium sources are more appropriate for reuse in nuclear medicine applications and other applications.

  14. Disposition of actinides released from high-level waste glass

    SciTech Connect (OSTI)

    Ebert, W.L.; Bates, J.K.; Buck, E.C.; Gong, M.; Wolf, S.F.

    1994-05-01T23:59:59.000Z

    A series of static leach tests was conducted using glasses developed for vitrifying tank wastes at the Savannah River Site to monitor the disposition of actinide elements upon corrosion of the glasses. In these tests, glasses produced from SRL 131 and SRL 202 frits were corroded at 90{degrees}C in a tuff groundwater. Tests were conducted using crushed glass at different glass surface area-to-solution volume (S/V) ratios to assess the effect of the S/V on the solution chemistry, the corrosion of the glass, and the disposition of actinide elements. Observations regarding the effects of the S/V on the solution chemistry and the corrosion of the glass matrix have been reported previously. This paper highlights the solution analyses performed to assess how the S/V used in a static leach test affects the disposition of actinide elements between fractions that are suspended or dissolved in the solution, and retained by the altered glass or other materials.

  15. Portsmouth Decommissioning and Decontamination Project Director...

    Office of Environmental Management (EM)

    Final Findings and Order defines the steps for identifying a range of technical alternatives for the D&D and waste disposition components of the project, and reaching...

  16. Data base on dose reduction research projects for nuclear power plants. Volume 5

    SciTech Connect (OSTI)

    Khan, T.A.; Yu, C.K.; Roecklein, A.K. [Brookhaven National Lab., Upton, NY (United States)] [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01T23:59:59.000Z

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  17. DEVELOPING AN INTEGRATED NATIONAL STRATEGY FOR THE DISPOSITION OF SPENT NUCLEAR FUEL

    SciTech Connect (OSTI)

    Gelles, C.M.

    2003-02-27T23:59:59.000Z

    This paper summarizes the Department of Energy's (DOE's) current efforts to strengthen its activities for the management and disposition of DOE-owned spent nuclear fuel (SNF). In August 2002 an integrated, ''corporate project'' was initiated by the Office of Environmental Management (EM) to develop a fully integrated strategy for disposition of the approximately {approx}250,000 DOE SNF assemblies currently managed by EM. Through the course of preliminary design, the focus of this project rapidly evolved to become DOE-wide. It is supported by all DOE organizations involved in SNF management, and represents a marked change in the way DOE conducts its business. This paper provides an overview of the Corporate Project for Integrated/Risk-Driven Disposition of SNF (Corporate SNF Project), including a description of its purpose, scope and deliverables. It also summarizes the results of the integrated project team's (IPT's) conceptual design efforts, including the identification of project/system requirements and alternatives. Finally, this paper highlights the schedule of the corporate project, and its progress towards development of a DOE corporate strategy for SNF disposition.

  18. Surplus Plutonium Disposition Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    1999-11-19T23:59:59.000Z

    In December 1996, the U.S. Department of Energy (DOE) published the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact Statement (Storage and Disposition PEIS)'' (DOE 1996a). That PEIS analyzes the potential environmental consequences of alternative strategies for the long-term storage of weapons-usable plutonium and highly enriched uranium (HEU) and the disposition of weapons-usable plutonium that has been or may be declared surplus to national security needs. The Record of Decision (ROD) for the ''Storage and Disposition PEIS'', issued on January 14, 1997 (DOE 1997a), outlines DOE's decision to pursue an approach to plutonium disposition that would make surplus weapons-usable plutonium inaccessible and unattractive for weapons use. DOE's disposition strategy, consistent with the Preferred Alternative analyzed in the ''Storage and Disposition PEIS'', allows for both the immobilization of some (and potentially all) of the surplus plutonium and use of some of the surplus plutonium as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of both the immobilized plutonium and the MOX fuel (as spent nuclear fuel) in a potential geologic repository.

  19. Evaluation of Calcine Disposition Path Forward

    SciTech Connect (OSTI)

    Birrer, S.A.; Heiser, M.B.

    2003-02-26T23:59:59.000Z

    This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

  20. Evaluation of Calcine Disposition - Path Forward

    SciTech Connect (OSTI)

    Steve Birrer

    2003-02-01T23:59:59.000Z

    This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

  1. ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Moore, E.

    2013-07-17T23:59:59.000Z

    The United States holds at least 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition of the National Nuclear Security Administration and the DOE Office of Environmental Management. Many of the items that require disposition are only partially characterized, and SRNL uses a variety of techniques to predict the isotopic and chemical properties that are important for processing through the Mixed Oxide Fuel Fabrication Facility and alternative disposition paths. Recent advances in laboratory tools, including Prompt Gamma Analysis and Peroxide Fusion treatment, provide data on the existing inventories that will enable disposition without additional, costly sampling and destructive analysis.

  2. Proposed Tenaska Washington II Generation Project : Final Environmental Impact Statement. Volume 2: Public Involvement.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    1994-01-01T23:59:59.000Z

    In regard to the proposed Tenaska Washington II Generation Project, the goal of the Bonneville Power Administration`s (BPA) Environmental Impact Statement (EIS) public involvement process is to determine the issues to be examined and pertinent analyses to be conducted and to solicit comments on the content and quality of information presented in the Draft Environmental Impact Statement (DEIS). Comments and questions are solicited from the public and government agencies during the scoping process and during the comment period and public hearing on the DEIS, to find out what is of most concern to them. The end product of the public involvement process is the Comment Report which follows in part of this volume on Public Involvement.

  3. ASEAN-USAID buildings energy conservation project. Volume 1, Energy standards: Final report

    SciTech Connect (OSTI)

    Levine, M.D.; Busch, J.F. [eds.][Lawrence Berkeley Lab., CA (United States); Deringer, J.J. [Deringer Group, Riva, MD (United States)

    1992-06-01T23:59:59.000Z

    Mandatory or voluntary energy-efficiency standards for new or existing buildings can play an important role in a national program aimed at promoting energy conservation. Building codes and standards can provide a degree of control over design and building practices throughout the construction process, and encourage awareness of energy-conscious design. Studies in developed countries indicate that efficiency standards can produce energy reductions on the order of 20 to 40% or more. Within ASEAN, analyses of the savings potential from the proposed standards suggest that if implemented, these standards would produce savings over current new design practice of 19% to 24%. In this volume we provide an overview of the ASEAN-USAID project aimed at promulgating standards for energy efficiency in commercial buildings. The process of developing and implementing energy-efficiency standards for buildings can be subdivided into two key components: policy development; and technical and economic analysis. Each of these involves a number of steps and processes, as outlined in Figure 1-1. This volume describes the technical and economic analyses used to develop the proposed energy efficiency standards for four countries (Malaysia, Thailand, the Philippines, and Indonesia), and to refine an energy standard existing in Singapore since 1979. Though oriented toward the ASEAN region, the analysis methods described here are applicable in a range of settings, provided appropriate modifications are made for local building construction, climatic, economic, and political conditions. Implementation issues are not specifically addressed here; rather this volume is oriented towards the analytical work needed to establish or revise an energy standard for buildings.

  4. Fort Irwin integrated resource assessment. Volume 3: Sitewide Energy Project identification for buildings and facilities

    SciTech Connect (OSTI)

    Keller, J.M.; Dittmer, A.L.; Elliott, D.B.; McMordie, K.L.; Richman, E.E.; Stucky, D.J.; Wahlstrom, R.R.; Hadley, D.L.

    1995-02-01T23:59:59.000Z

    The U.S. Army Forces Command (FORSCOM) has tasked the U.S. Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Irwin. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Irwin facility located near Barstow, California. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 16 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present valve (NPV) and savings-to-investment ratio (SIR) of each ERO.

  5. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 4: Project cost estimate

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. This volume represents the total estimated costs for the W113 facility. Operating Contractor Management costs have been incorporated as received from WHC. The W113 Facility TEC is $19.7 million. This includes an overall project contingency of 14.4% and escalation of 17.4%. A January 2001 construction contract procurement start date is assumed.

  6. The ADVANCE project: Formal evaluation of the targeted deployment. Volume 3

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    ADVANCE [Advanced Driver and Vehicle Advisory Navigation ConcEpt] was a public/private partnership conceived and developed by four founding parties. The founding parties include the Federal Highway Administration (FHWA), the Illinois Department of Transportation (IDOT), the University of Illinois at Chicago and Northwestern University operating together under the auspices of the Illinois Universities Transportation Research Consortium (IUTRC), and Motorola, Inc. The major responsibilities of each party are fully described in the Project agreement. Subsequently, these four were joined on the Steering Committee by the American Automobile Association (AAA). This unique blending of public sector, private sector and university interests, augmented by more than two dozen other private sector participants, provided a strong set of resources for ADVANCE. The ADVANCE test area covered over 300 square miles including portions of the City of Chicago and 40 northwest suburban communities. The Project encompasses the high growth areas adjacent to O`Hare International Airport, the Schaumbura/Hoffman Estates office and retail complexes, and the Lake-Cook Road development corridor. It also includes major sports and entertainment complexes such as the Arlington International Racecourse and the Rosemont Horizon. The population in the area is more than 750,000. This volume provides a summary of the insights and achievements made as a result of this field test, and selected appendices containing more detailed information.

  7. EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

  8. Proliferation resistance criteria for fissile material disposition

    SciTech Connect (OSTI)

    Close, D.A.; Fearey, B.L.; Markin, J.T.; Rutherford, D.A. [Los Alamos National Lab., NM (United States); Duggan, R.A.; Jaeger, C.D.; Mangan, D.L.; Moya, R.W.; Moore, L.R. [Sandia National Labs., Albuquerque, NM (United States); Strait, R.S. [Lawrence Livermore National Lab., CA (United States)

    1995-04-01T23:59:59.000Z

    The 1994 National Academy of Sciences study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This report proposes criteria for assessing the proliferation resistance of these options. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

  9. ASEAN-USAID Buildings Energy Conservation Project. Final report, Volume 3: Audits

    SciTech Connect (OSTI)

    Loewen, J.M.; Levine, M.D.; Busch, J.F. [eds.

    1992-06-01T23:59:59.000Z

    The auditing subproject of the ASEAN-USAID Buildings Energy Conservation Project has generated a great deal of auditing activity throughout the ASEAN region. Basic building characterisfic and energy consumption data were gathered for over 200 buildings and are presented in this volume. A large number of buildings were given more detailed audits and were modeled with either the ASEAM-2 computer program or the more complex DOE-2 program. These models were used to calculate the savings to be generated by conservabon measures. Specially audits were also conducted, including lighting and thermal comfort surveys. Many researchers in the ASEAN region were trained to perform energy audits in a series of training courses and seminars. The electricity intensifies of various types of ASEAN buildings have been calculated. A comparison to the electricity intensity of the US building stock tentatively concludes that ASEAN office buildings are comparable, first class hotels and retail stores are more ewctricity intensive than their US counterparts, and hospitals are less intensive. Philippine and Singapore lighting surveys indicate that illuminance levels in offices tend to be below the minimum accepted standard. Computer simulations of the energy use in various building types generally agree that for most ASEAN buildings, electricity consumption for air-conditioning (including fan power) consumes approximately 60% of total building electricity. A review of the many studies made during the Project to calculate the savings from energy conservation opportunities (ECOS) shows a median potential savings of approximately 10%, with some buildings saving as much as 50%. Singapore buildings, apparently as a result of previously implemented efficient energy-use practices, shows a lower potential for savings than the other ASEAN nations. Air-conditioning ECOs hold the greatest potential for savings.

  10. A Research Needs Assessment for waste plastics recycling: Volume 2, Project report. Final report

    SciTech Connect (OSTI)

    NONE

    1994-12-01T23:59:59.000Z

    This second volume contains detailed information on a number of specific topics relevant to the recovery/recycling of plastics.

  11. The ADVANCE project: Formal evaluation of the targeted deployment. Volume 1

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    The Advanced Driver and Vehicle Advisory Navigation ConcEpt (ADVANCE) was an invehicle advanced traveler information system (ATIS) that operated in the northwest suburbs of Chicago, Illinois. It was designed to provide origin-destination shortest-time route guidance to a vehicle based on (a) an on-board static (fixed) data base of average network link travel times by time of day, combined as available and appropriate with (b) dynamic (real-time) information on traffic conditions provided by radio frequency (RF) communications to and from a traffic information center (TIC). Originally conceived in 1990 as a major project that would have installed 3,000 to 5,000 route guidance units in privately owned vehicles throughout the test area, ADVANCE was restructured in 1995 as a {open_quotes}targeted deployment,{close_quotes} in which approximately 80 vehicles were to be equipped with the guidance units - Mobile Navigation Assistants (MNAs) - to be in full communication with the TIC while driving the ADVANCE test area road system. Volume one consists of the evaluation managers overview report, and several appendices containing test results.

  12. Disposition of intravenous radioactive acyclovir

    SciTech Connect (OSTI)

    de Miranda, P.; Good, S.S.; Laskin, O.L.; Krasny, H.C.; Connor, J.D.; Lietman, P.S.

    1981-11-01T23:59:59.000Z

    The kinetic and metabolic disposition of (8-14C)acyclovir (ACV) was investigated in five subjects with advanced malignancy. The drug was administered by 1-hr intravenous infusion at doses of 0.5 and 2.5 mg/kg. Plasma and blood radioactivity-time, and plasma concentration-time data were defined by a two-compartment open kinetic model. There was nearly equivalent distribution of radioactivity in blood and plasma. The overall mean plasma half-life and total body clearance +/- SD of ACV were 2.1 +/- 0.5 hr and 297 +/- 53 ml/min/1.73 m2. Binding of ACV to plasma proteins was 15.4 +/- 4.4%. Most of the radioactive dose excreted was recovered in the urine (71% to 99%) with less than 2% excretion in the feces and only trace amounts in the expired Co2. Analyses by reverse-phase high-performance liquid chromatography indicated that 9-(carboxymethoxymethyl)guanine was the only significant urinary metabolite of ACV, accounting for 8.5% to 14.1% of the dose. A minor metabolite (less than 0.2% of dose) had the retention time of 8-hydroxy-9-((2-hydroxyethoxy)methyl)guanine. Unchanged urinary ACV ranged from 62% to 91% of the dose. There was no indication of ACV cleavage to guanine. Renal clearance of ACV was approximately three times the corresponding creatinine clearances.

  13. Wildlife Loss Estimates and Summary of Previous Mitigation Related to Hydroelectric Projects in Montana, Volume Three, Hungry Horse Project.

    SciTech Connect (OSTI)

    Casey, Daniel

    1984-10-01T23:59:59.000Z

    This assessment addresses the impacts to the wildlife populations and wildlife habitats due to the Hungry Horse Dam project on the South Fork of the Flathead River and previous mitigation of theses losses. In order to develop and focus mitigation efforts, it was first necessary to estimate wildlife and wildlife hatitat losses attributable to the construction and operation of the project. The purpose of this report was to document the best available information concerning the degree of impacts to target wildlife species. Indirect benefits to wildlife species not listed will be identified during the development of alternative mitigation measures. Wildlife species incurring positive impacts attributable to the project were identified.

  14. PHMC Year 2000: Status reporting for mission essential Year 2000 projects. Revision 0, Volume 3

    SciTech Connect (OSTI)

    Layfield, K.A.

    1998-09-02T23:59:59.000Z

    The PHMC Year 2000 status reporting process is designed to encompass the reporting requirements of the Office of Management and Budget (OMB), DOE HQ, RL and the PHMC for mission essential Year 2000 projects. Status reporting is required for all Year 2000 projects. The Year 2000 project list will be maintained current as Year 2000 projects are modified, added or deleted. Reporting is required until a Year 2000 project has completed compliance assurance. Some projects will be identified as DOE HQ reportable. These are projects determined to be the most critical and due the attention of DOE HQ.

  15. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    NONE

    1998-02-01T23:59:59.000Z

    Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

  16. Tri-State Synfuels Project Review: Volume 12. Fluor project status. [Proposed Henderson, Kentucky coal to gasoline plant; engineering

    SciTech Connect (OSTI)

    Not Available

    1982-06-01T23:59:59.000Z

    The purpose of this report is to document and summarize activities associated with Fluor's efforts on the Tri-State Synfuels Project. The proposed facility was to be coal-to-transport fuels facility located in Henderson, Kentucky. Tri-State Synfuels Company was participating in the project as a partner of the US Department of Energy per terms of a Cooperative Agreement resulting from DOE's synfuel's program solicitation. Fluor's initial work plan called for preliminary engineering and procurement services to the point of commitment for construction for a Sasol Fischer-Tropsch plant. Work proceeded as planned until October 1981 when results of alternative coal-to-methanol studies revealed the economic disadvantage of the Synthol design for US markets. A number of alternative process studies followed to determine the best process configuration. In January 1982 Tri-State officially announced a change from Synthol to a Methanol to Gasoline (MTG) design basis. Further evaluation and cost estimates for the MTG facility eventually led to the conclusion that, given the depressed economic outlook for alternative fuels development, the project should be terminated. Official announcement of cancellation was made on April 13, 1982. At the time of project cancellation, Fluor had completed significant portions of the preliminary engineering effort. Included in this report are descriptions and summaries of Fluor's work during this project. In addition location of key project data and materials is identified and status reports for each operation are presented.

  17. Surface Environmental Surveillance Project: Locations Manual Volume 1 – Air and Water Volume 2 – Farm Products, Soil & Vegetation, and Wildlife

    SciTech Connect (OSTI)

    Fritz, Brad G.; Patton, Gregory W.; Stegen, Amanda; Poston, Ted M.

    2009-01-01T23:59:59.000Z

    This report describes all environmental monitoring locations associated with the Surface Environmental Surveillance Project. Environmental surveillance of the Hanford site and surrounding areas is conducted by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy (DOE). Sampling is conducted to evaluate levels of radioactive and nonradioactive pollutants in the Hanford environs, as required in DOE Order 450.1, Environmental Protection Program, and DOE Order 5400.5, Radiation Protection of the Public and the Environment. The environmental surveillance sampling design is described in the Hanford Site Environmental Monitoring Plan, United States Department of Energy, Richland Operation Office (DOE/RL-91-50). This document contains the locations of sites used to collect samples for the Surface Environmental Surveillance Project (SESP). Each section includes directions, maps, and pictures of the locations. A general knowledge of roads and highways on and around the Hanford Site is necessary to successfully use this manual. Supplemental information (Maps, Gazetteer, etc.) may be necessary if user is unfamiliar with local routes. The SESP is a multimedia environmental surveillance effort to measure the concentrations of radionuclides and chemicals in environmental media to demonstrate compliance with applicable environmental quality standards and public exposure limits, and assessing environmental impacts. Project personnel annually collect selected samples of ambient air, surface water, agricultural products, fish, wildlife, and sediments. Soil and vegetation samples are collected approximately every 5 years. Analytical capabilities include the measurement of radionuclides at very low environmental concentrations and, in selected media, nonradiological chemicals including metals, anions, volatile organic compounds, and total organic carbon.

  18. Excess plutonium disposition: The deep borehole option

    SciTech Connect (OSTI)

    Ferguson, K.L.

    1994-08-09T23:59:59.000Z

    This report reviews the current status of technologies required for the disposition of plutonium in Very Deep Holes (VDH). It is in response to a recent National Academy of Sciences (NAS) report which addressed the management of excess weapons plutonium and recommended three approaches to the ultimate disposition of excess plutonium: (1) fabrication and use as a fuel in existing or modified reactors in a once-through cycle, (2) vitrification with high-level radioactive waste for repository disposition, (3) burial in deep boreholes. As indicated in the NAS report, substantial effort would be required to address the broad range of issues related to deep bore-hole emplacement. Subjects reviewed in this report include geology and hydrology, design and engineering, safety and licensing, policy decisions that can impact the viability of the concept, and applicable international programs. Key technical areas that would require attention should decisions be made to further develop the borehole emplacement option are identified.

  19. Portsmouth/Paducah Project Office

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

    Aug. 23, 2013 Robert.Smith@lex.doe.gov DOE Paducah Site Demolition Debris Shipped to Utah for Disposition Twenty-eight rail cars filled with debris from a major demolition project...

  20. Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 5

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-24T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable.

  1. Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 8

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-23T23:59:59.000Z

    This supporting document has been prepared to make the FDNW civil/structural calculations for Project W-320 readily retrievable.

  2. Project W-320, 241-C-106 sluicing electrical calculations, Volume 1

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-08-07T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable.

  3. GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

    SciTech Connect (OSTI)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-11-01T23:59:59.000Z

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs.

  4. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    SciTech Connect (OSTI)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01T23:59:59.000Z

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  5. MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION

    SciTech Connect (OSTI)

    WEST LD

    2011-01-13T23:59:59.000Z

    The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m{sup 3} of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% ({approx}8,000 m{sup 3}) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

  6. Prototypical Rod Consolidation Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 2

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 2 discusses the following topics: Fuel Rod Extraction System Test Results and Analysis Reports and Clamping Table Test Results and Analysis Reports.

  7. Characterizing Surplus US Plutonium for Disposition - 13199

    SciTech Connect (OSTI)

    Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States)] [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)] [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

    2013-07-01T23:59:59.000Z

    The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

  8. Characterizing surplus US plutonium for disposition

    SciTech Connect (OSTI)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-02-26T23:59:59.000Z

    The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

  9. Disposition of surplus fissile materials via immobilization

    SciTech Connect (OSTI)

    Gray, L.W.; Kan, T.; Sutcliffe, W.G. [Lawrence Livermore National Lab., CA (United States); McKibben, J.M. [Westinghouse Savannah River Co., Aiken, SC (United States); Danker, W. [USDOE, Washington, DC (United States)

    1995-07-23T23:59:59.000Z

    In the Cold War aftermath, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long-term management options, the USDOE has undertaken a multifaceted study to select options for storage and disposition of surplus plutonium (Pu). One disposition alternative being considered is immobilization. Immobilization is a process in which surplus Pu would be embedded in a suitable material to produce an appropriate form for ultimate disposal. To arrive at an appropriate form, we first reviewed published information on HLW immobilization technologies to identify forms to be prescreened. Surviving forms were screened using multi-attribute utility analysis to determine promising technologies for Pu immobilization. We further evaluated the most promising immobilization families to identify and seek solutions for chemical, chemical engineering, environmental, safety, and health problems; these problems remain to be solved before we can make technical decisions about the viability of using the forms for long-term disposition of Pu. All data, analyses, and reports are being provided to the DOE Office of Fissile Materials Disposition to support the Record of Decision that is anticipated in Summer of 1996.

  10. Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors

    SciTech Connect (OSTI)

    Sterbentz, J.W.; Olsen, C.S.; Sinha, U.P.

    1993-06-01T23:59:59.000Z

    This study is in response to a request by the Reactor Panel Subcommittee of the National Academy of Sciences (NAS) Committee on International Security and Arms Control (CISAC) to evaluate the feasibility of using plutonium fuels (without uranium) for disposal in existing conventional or advanced light water reactor (LWR) designs and in low temperature/pressure LWR designs that might be developed for plutonium disposal. Three plutonium-based fuel forms (oxides, aluminum metallics, and carbides) are evaluated for neutronic performance, fabrication technology, and material and compatibility issues. For the carbides, only the fabrication technologies are addressed. Viable plutonium oxide fuels for conventional or advanced LWRs include plutonium-zirconium-calcium oxide (PuO{sub 2}-ZrO{sub 2}-CaO) with the addition of thorium oxide (ThO{sub 2}) or a burnable poison such as erbium oxide (Er{sub 2}O{sub 3}) or europium oxide (Eu{sub 2}O{sub 3}) to achieve acceptable neutronic performance. Thorium will breed fissile uranium that may be unacceptable from a proliferation standpoint. Fabrication of uranium and mixed uranium-plutonium oxide fuels is well established; however, fabrication of plutonium-based oxide fuels will require further development. Viable aluminum-plutonium metallic fuels for a low temperature/pressure LWR include plutonium aluminide in an aluminum matrix (PuAl{sub 4}-Al) with the addition of a burnable poison such as erbium (Er) or europium (Eu). Fabrication of low-enriched plutonium in aluminum-plutonium metallic fuel rods was initially established 30 years ago and will require development to recapture and adapt the technology to meet current environmental and safety regulations. Fabrication of high-enriched uranium plate fuel by the picture-frame process is a well established process, but the use of plutonium would require the process to be upgraded in the United States to conform with current regulations and minimize the waste streams.

  11. Water Resources Data. Ohio - Water Year 1992. Volume 1. Ohio River Basin excluding project data

    SciTech Connect (OSTI)

    H.L. Shindel; J.H. Klingler; J.P. Mangus; L.E. Trimble

    1993-03-01T23:59:59.000Z

    Water-resources data for the 1992 water year for Ohio consist of records of stage, discharge, and water quality of streams; stage and contents of lakes and reservoirs; and water levels and water quality of ground-water wells. This report, in two volumes, contains records for water discharge at 121 gaging stations, 336 wells, and 72 partial-record sites; and water levels at 312 observation wells. Also included are data from miscellaneous sites. Additional water data were collected at various sites not involved in the systematic data-collection program and are published as miscellaneous measurements and analyses. These data represent that part of the National Water Data System collected by the US Geological Survey and cooperating State and Federal agencies in Ohio. Volume 1 covers the central and southern parts of Ohio, emphasizing the Ohio River Basin. (See Order Number DE95010451 for Volume 2 covering the northern part of Ohio.)

  12. Unaccounted-for gas project. Theft Task Force. Volume 3. Final report

    SciTech Connect (OSTI)

    Cima, K.M.; Cottengim, T.L.; Wong, R.M.; Cowgill, R.M.; Grinstead, J.R.

    1990-06-01T23:59:59.000Z

    The study was aimed at determining unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric Co.'s transmission and distribution systems during 1987. The Theft Task Force analyzed the percentage of customers involved in gas theft, the average annual volume of gas stolen by a single customer, and the total number of customers and their total gas usage. Results were used in conjunction with documented customer theft to arrive at a calculation that more accurately reflected the theft contribution to UAF for 1987.

  13. Unaccounted-for gas project. Data bases. Volume 5. Final report

    SciTech Connect (OSTI)

    Cowgill, R.; Waller, R.L.; Grinstead, J.R.

    1990-06-01T23:59:59.000Z

    The study identifies, explains, and quantifies unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric (PG E) Co.'s gas transmission and distribution systems during 1987. The results demonstrate that the UAF volumes are reasonable for determining the indirectly billed gas requirements component of the gas cost and for operating the PG E gas system. Gas leakage is a small percentage of UAF. Summaries of studies on gas leakage, gas theft, measurement inaccuracies, and accounting methodologies are presented along with recommendations for further work which could reduce or more accurately measure UAF.

  14. Unaccounted-for gas project: Summary volume. Energy delivery and control. Final report

    SciTech Connect (OSTI)

    Cima, K.M.; Cottengim, T.L.; Wong, R.M.; Cowgill, R.M.; Grinstead, J.R.

    1990-06-01T23:59:59.000Z

    The study was aimed at determining unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric Co.'s transmission and distribution systems during 1987. The Theft Task Force analyzed the percentage of customers involved in gas theft, the average annual volume of gas stolen by a single customer, and the total number of customers and their total gas usage. Results were used in conjunction with documented customer theft to arrive at a calculation that more accurately reflected the theft contribution to UAF for 1987.

  15. Validation of a 4D-PET Maximum Intensity Projection for Delineation of an Internal Target Volume

    SciTech Connect (OSTI)

    Callahan, Jason, E-mail: jason.callahan@petermac.org [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia)] [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Kron, Tomas [Department of Physical Sciences, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia) [Department of Physical Sciences, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Peter MacCallum Department of Oncology, The University of Melbourne, Melbourne (Australia); Schneider-Kolsky, Michal [Department of Medical Imaging and Radiation Science, Monash University, Clayton, Victoria (Australia)] [Department of Medical Imaging and Radiation Science, Monash University, Clayton, Victoria (Australia); Dunn, Leon [Department of Applied Physics, RMIT University, Melbourne (Australia)] [Department of Applied Physics, RMIT University, Melbourne (Australia); Thompson, Mick [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia)] [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Siva, Shankar [Department of Radiation Oncology, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia)] [Department of Radiation Oncology, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Aarons, Yolanda [Department of Radiation Oncology, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia) [Department of Radiation Oncology, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Peter MacCallum Department of Oncology, The University of Melbourne, Melbourne (Australia); Binns, David [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia)] [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Hicks, Rodney J. [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia) [Centre for Molecular Imaging, Peter MacCallum Cancer Centre, East Melbourne, Victoria (Australia); Peter MacCallum Department of Oncology, The University of Melbourne, Melbourne (Australia)

    2013-07-15T23:59:59.000Z

    Purpose: The delineation of internal target volumes (ITVs) in radiation therapy of lung tumors is currently performed by use of either free-breathing (FB) {sup 18}F-fluorodeoxyglucose-positron emission tomography-computed tomography (FDG-PET/CT) or 4-dimensional (4D)-CT maximum intensity projection (MIP). In this report we validate the use of 4D-PET-MIP for the delineation of target volumes in both a phantom and in patients. Methods and Materials: A phantom with 3 hollow spheres was prepared surrounded by air then water. The spheres and water background were filled with a mixture of {sup 18}F and radiographic contrast medium. A 4D-PET/CT scan was performed of the phantom while moving in 4 different breathing patterns using a programmable motion device. Nine patients with an FDG-avid lung tumor who underwent FB and 4D-PET/CT and >5 mm of tumor motion were included for analysis. The 3 spheres and patient lesions were contoured by 2 contouring methods (40% of maximum and PET edge) on the FB-PET, FB-CT, 4D-PET, 4D-PET-MIP, and 4D-CT-MIP. The concordance between the different contoured volumes was calculated using a Dice coefficient (DC). The difference in lung tumor volumes between FB-PET and 4D-PET volumes was also measured. Results: The average DC in the phantom using 40% and PET edge, respectively, was lowest for FB-PET/CT (DCAir = 0.72/0.67, DCBackground 0.63/0.62) and highest for 4D-PET/CT-MIP (DCAir = 0.84/0.83, DCBackground = 0.78/0.73). The average DC in the 9 patients using 40% and PET edge, respectively, was also lowest for FB-PET/CT (DC = 0.45/0.44) and highest for 4D-PET/CT-MIP (DC = 0.72/0.73). In the 9 lesions, the target volumes of the FB-PET using 40% and PET edge, respectively, were on average 40% and 45% smaller than the 4D-PET-MIP. Conclusion: A 4D-PET-MIP produces volumes with the highest concordance with 4D-CT-MIP across multiple breathing patterns and lesion sizes in both a phantom and among patients. Freebreathing PET/CT consistently underestimates ITV when compared with 4D PET/CT for a lesion affected by respiration.

  16. Unaccounted-for gas project. Leak Task Force. Volume 4. Final report

    SciTech Connect (OSTI)

    Cowgill, R.M.; Robertson, J.L.; Grinstead, J.R.; Luttrell, D.J.; Walden, E.R.

    1990-06-07T23:59:59.000Z

    The study was aimed at determining unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric Co.'s transmission and distribution systems during 1987. The Leak Task Force quantified unintentional gas losses (leakage and dig-ins). Results show that 1987 gas leakage accounted for less than 5% of the operating UAF.

  17. Unaccounted-for gas project. Measurement Task Force (orifice meter studies). Volume 2B. Final report

    SciTech Connect (OSTI)

    Godkin, B.J.; Robertson, J.D.; Wlasenko, R.G.; Cowgill, R.M.; Grinstead, J.R.

    1990-06-01T23:59:59.000Z

    The study was aimed at determining unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric Co.'s transmission and distribution systems during 1987. Activities and methods are described and results are presented for research conducted on orifice meter accuracy. The Measurement Task Force determined that orifice metering inaccuracies were the largest single contributor to 1987 UAF.

  18. New England Wind Forum: A Wind Powering America Project, Volume 1, Issue 4 -- May 2008 (Newsletter)

    SciTech Connect (OSTI)

    Grace, R. C.; Gifford, J.

    2008-05-01T23:59:59.000Z

    The New England Wind Forum electronic newsletter summarizes the latest news in wind energy development activity, markets, education, and policy in the New England region. It also features an interview with a key figure influencing New England's wind energy development. Volume 1, Issue 4 features an interview with Brian Fairbank, president and CEO of Jiminy Peak Mountain Resort.

  19. A HOLISTIC APPROACH FOR DISPOSITION OF LONG-LIVED RADIOACTIVE MATERIALS

    SciTech Connect (OSTI)

    Eriksson, Leif G.; Dials, George E.; Parker, Frank L.

    2003-02-27T23:59:59.000Z

    During the past 45 years, one of the most challenging scientific, engineering, socio-economic, and political tasks and obligations of our time has been to site and develop technical, politically acceptable, solutions to the safe disposition of long-lived radioactive materials (LLRMs). However, at the end of the year 2002, the Waste Isolation Pilot Plant (WIPP) site in the United States of America (USA) hosts the world's only operating LLRM-disposal system, which (1) is based on the LLRM-disposal principles recommended by the National Academy of Sciences (NAS) in 1957, i.e., deep geological disposal in a ''stable'' salt vault/repository, (2) complies with the nation's ''Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes'', and (3) may receive 175,584 cubic meters (m3) of transuranic radioactive waste (TRUW)a. Pending the scheduled opening of repositories for once-used nuclear fuel (OUNF) in the USA, Sweden, and Finland in the years 2010, 2015, and 2017, respectively, LLRM-disposal solutions remain the missing link in all national LLRM-disposition programs. Furthermore, for a variety of reasons, many nations with nuclear programs have chosen a ''spectator'' stance in terms of enhancing the global nuclear safety culture and the nuclear renaissance, and have either ''slow-tracked'' or deferred their LLRM-disposal programs to allow time for an informed national consensus to evolve based on LLRM-disposition experiences and solutions gained elsewhere. In the meantime, LLRMs will continue to amass in different types and levels of safeguarded storage facilities around the world. In an attempt to contribute to the enhancement of the global nuclear safety culture and the nuclear renaissance, the authors developed the sample holistic approach for synergistic disposition of LLRMs comprising LLRM-disposition components considered either ''proven'' or ''promising'' by the authors. The fundamental principles of the holistic approach are: (1) Risk minimization; (2) Minimization of the LLRM volume requiring deep geological disposal; and (3) LLRM-disposition flexibility. An integral element of these principles is to allow time for LLRM-disposition solutions to evolve/mature technically, financially, and politically. Furthermore, contingent upon the desired outcome(s), available financial, scientific, and technical resources, and political will, these components may be implemented separately or in combinations by one or a group of nations.

  20. A framework for selecting strategies to impact the success of high volume roadway projects

    E-Print Network [OSTI]

    Chabannes, Clayton C.

    2006-08-16T23:59:59.000Z

    framework for when to implement these different strategies. These strategies were identified through an in-depth literature review and through case studies conducted on highway projects that were under construction. Through the case studies the different...

  1. Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 3

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-24T23:59:59.000Z

    This supporting document has been prepared to make the FDNW civil/structural calculations for Project W-320 readily retrievable. The Equipment Removal System (ERS) has been identified by WHC as not having any safety class 1 items present in the tank pits during equipment removal activities, Documentation of this finding is provided in Letter of Instruction 3/1 Analysis Requirements for Project W-320 Equipment Removal System (REF: LOI KGS-94-013). Based on this specific direction from WHC, 3/1 analysis for any component of the Project W-320 ERS is required. No further documentation of non-safety impacting safety items is required per DOE-RL Audit finding No.90-02, and filing of this memorandum in the W-320 project files satisfies the intent of the referenced DOE observation.

  2. Projected electric power demands for the Potomac Electric Power Company. Volume 1

    SciTech Connect (OSTI)

    Estomin, S.; Kahal, M.

    1984-03-01T23:59:59.000Z

    This three-volume report presents the results of an econometric forecast of peak and electric power demands for the Potomac Electric Power Company (PEPCO) through the year 2002. Volume I describes the methodology, the results of the econometric estimations, the forecast assumptions and the calculated forecasts of peak demand and energy usage. Separate sets of models were developed for the Maryland Suburbs (Montgomery and Prince George's counties), the District of Columbia and Southern Maryland (served by a wholesale customer of PEPCO). For each of the three jurisdictions, energy equations were estimated for residential and commercial/industrial customers for both summer and winter seasons. For the District of Columbia, summer and winter equations for energy sales to the federal government were also estimated. Equations were also estimated for street lighting and energy losses. Noneconometric techniques were employed to forecast energy sales to the Northern Virginia suburbs, Metrorail and federal government facilities located in Maryland.

  3. Unaccounted-for gas project. Accounting Task Force. Volume 1. Energy delivery and control. Final report

    SciTech Connect (OSTI)

    Luttrell, D.J.; Nelson, F.A.; Peterson, J.D.; Cowgill, R.M.; Waller, R.L.

    1990-06-01T23:59:59.000Z

    The study was conducted to determine unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric (PG E) Co.'s transmission and distribution systems during 1987. The Accounting Task Force analyzed purchases and transport received, sales and transport delivered, interdepartmental sales, and gas department use to determine the effect on UAF. Findings show that accounting adjustments and cycle billing have a major impact on the 1987 operating UAF.

  4. Upper arun hydroelectric project feasibility study (phase 1). Volume 2. Appendix. Export trade information

    SciTech Connect (OSTI)

    Not Available

    1987-09-01T23:59:59.000Z

    The report was prepared for Nepal Electricity Authority (NEA). The primary objective of the study was to compare several alternative development schemes to drive an optimum development plan for exploiting the hydroelectric potential of the Upper Arun River, to be further investigated in phase 2 of the feasibility study. The report presents the result of the phase I studies investigations recommends the alternatives to be pursued to develop the Upper Arun River. Volume 2 contains tables, figures and other supporting materials.

  5. Environmental mitigation at hydroelectric projects. Volume 2, Benefits and costs of fish passage and protection

    SciTech Connect (OSTI)

    Francfort, J.E.; Rinehart, B.N.; Sommers, G.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Cada, G.F.; Jones, D.W. [Oak Ridge National Lab., TN (United States); Dauble, D.D. [Pacific Northwest Lab., Richland, WA (United States); Hunt, R.T. [Hunt (Richard) Associates, Inc., Concord, NH (United States); Costello, R.J. [Northwest Water Resources Advisory Services (United States)

    1994-01-01T23:59:59.000Z

    This study examines envirorunental mitigation practices that provide upstream and downstream fish passage and protection at hydroelectric projects. The study includes a survey of fish passage and protection mitigation practices at 1,825 hydroelectric plants regulated by the Federal Energy Regulatory Commission (FERC) to determine frequencies of occurrence, temporal trends, and regional practices based on FERC regions. The study also describes, in general terms, the fish passage/protection mitigation costs at 50 non-Federal hydroelectric projects. Sixteen case studies are used to examine in detail the benefits and costs of fish passage and protection. The 16 case studies include 15 FERC licensed or exempted hydroelectric projects and one Federally-owned and-operated hydroelectric project. The 16 hydroelectric projects are located in 12 states and range in capacity from 400 kilowatts to 840 megawatts. The fish passage and protection mitigation methods at the case studies include fish ladders and lifts, an Eicher screen, spill flows, airburst-cleaned inclined and cylindrical wedgewire screens, vertical barrier screens, and submerged traveling screens. The costs, benefits, monitoring methods, and operating characteristics of these and other mitigation methods used at the 16 case studies are examined.

  6. Surplus Plutonium Disposition (SPD) Environmental Data Summary

    SciTech Connect (OSTI)

    Fledderman, P.D.

    2000-08-24T23:59:59.000Z

    This document provides an overview of existing environmental and ecological information at areas identified as potential locations of the Savannah River Site's (SRS) Surplus Plutonium Disposition (SPD) facilities. This information is required to document existing environmental and baseline conditions from which SPD construction and operation impacts can be defined. It will be used in developing the required preoperational monitoring plan to be used at specific SPD facilities construction sites.

  7. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Lemons, T.R. [Uranium Enrichment Organization, Oak Ridge, TN (United States)

    1991-12-31T23:59:59.000Z

    Depleted uranium (DU) is produced as a by-product of the uranium enrichment process. Over 340,000 MTU of DU in the form of UF{sub 6} have been accumulated at the US government gaseous diffusion plants and the stockpile continues to grow. An overview of issues and objectives associated with the inventory management and the ultimate disposition of this material is presented.

  8. Nuclear Materials Disposition | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire3627 Federal Register /7 ThisNuclear Materials Disposition

  9. Project W-320, 241-C-106 sluicing: Civil/structural calculations. Volume 6

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-24T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable. The purpose of this calculation is to conservatively estimate the weight of equipment and structures being added over Tank 241-C-106 as a result of Project W-320 and combine these weights with the estimated weights of existing structures and equipment as calculated in Attachment 1. The combined weights will be compared to the allowable live load limit to provide a preliminary assessment of loading conditions above Tank 241-C-106.

  10. Water Resources Data Ohio: Water year 1994. Volume 1, Ohio River Basin excluding Project Data

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    The Water Resources Division of the US Geological Survey (USGS) in cooperation with State agencies, obtains a large amount of data each water year (a water year is the 12-month period from October 1 through September 30 and is identified by the calendar year in which it ends) pertaining to the water resources of Ohio. These data, accumulated during many years, constitute a valuable data base for developing an improved understanding of the water resources of the State. To make these data readily available to interested parties outside the USGS, they are published annually in this report series entitled ``Water Resources Data--Ohio.`` This report (in two volumes) includes records on surface water and ground water in the State. Specifically, it contains: (1) Discharge records for streamflow-gaging stations, miscellaneous sites, and crest-stage stations; (2) stage and content records for streams, lakes, and reservoirs; (3) water-quality data for streamflow-gaging stations, wells, synoptic sites, and partial-record sit -aid (4) water-level data for observation wells. Locations of lake-and streamflow-gaging stations, water-quality stations, and observation wells for which data are presented in this volume are shown in figures 8a through 8b. The data in this report represent that part of the National Water Data System collected by the USGS and cooperating State and Federal agencies in Ohio. This series of annual reports for Ohio began with the 1961 water year with a report that contained only data relating to the quantities of surface water. For the 1964 water year, a similar report was introduced that contained only data relating to water quality. Beginning with the 1975 water year, the report was changed to present (in two or three volumes) data on quantities of surface water, quality of surface and ground water, and ground-water levels.

  11. Project W-320, 241-C-106 sluicing HVAC calculations, Volume 4

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-30T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. The report contains the following design calculations: Cooling load in pump pit 241-AY-102; Pressure relief seal loop design; Process building piping stress analysis; Exhaust skid maximum allowable leakage criteria; and Recirculation heat, N509 duct requirements.

  12. Project W-320, 241-C-106 sluicing piping calculations, Volume 7

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-29T23:59:59.000Z

    The object of this report is to calculate the hydraulic forces imposed at the sluicer nozzle. This is required by Project W-320 waste retrieval for tank 241-C-106. The method of analysis used is Bernoulli`s momentum equation for stead flow.

  13. Seismic Safety Margins Research Program. Phase I, final report. Major structure response (Project IV). Volume 5

    SciTech Connect (OSTI)

    Benda, B. J.; Johnson, J. J.; Lo, T. Y.

    1981-05-01T23:59:59.000Z

    Task of the Major Structure Response Project within the Seismic Safety Margins Research Program (SSMRP) was to develop detailed finite element models of the Zion Nuclear Power Plant's containment building and auxiliary-fuel-turbine (AFT) complex. The resulting models served as input to the seismic methodology analysis chain.

  14. Additional public meeting on plutonium disposition on September...

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

    produce an oxide form of plutonium suitable for disposition and the use of mixed oxide (MOX) fuel fabricated from surplus plutonium in domestic commercial nuclear power reactors...

  15. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...

    Office of Environmental Management (EM)

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5...

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

    SciTech Connect (OSTI)

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

    1995-05-01T23:59:59.000Z

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

  17. Acceleration of Los Alamos National Laboratory transuranic waste disposition

    SciTech Connect (OSTI)

    O'Leary, G.A.; Palmer, B.A.; Starke, T.P.; Phelps, A.K. [Los Alamos National Security, L.L.C., Los Alamos National Laboratory, Los Alamos, NM (United States)

    2007-07-01T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuranic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dis-positioning the transuranic waste inventory requires retrieval of the containers from above and below- ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LANL does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contractor in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquarters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approach include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safely remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Reduction Fa

  18. ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

    SciTech Connect (OSTI)

    O'LEARY, GERALD A. [Los Alamos National Laboratory

    2007-01-04T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuramic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dispositioning the transuranic waste inventory requires retrieval of the containers from above and below-ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LAN L does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contract in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquaeters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approch include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safetly remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Facility and Dom

  19. BLAST FURNACE GRANULAR COAL INJECTION SYSTEM. Final Report Volume 2: Project Performance and Economics

    SciTech Connect (OSTI)

    Unknown

    1999-10-01T23:59:59.000Z

    Bethlehem Steel Corporation (BSC) requested financial assistance from the Department of Energy (DOE), for the design, construction and operation of a 2,800-ton-per-day blast furnace granulated coal injection (BFGCI) system for two existing iron-making blast furnaces. The blast furnaces are located at BSC's facilities in Burns Harbor, Indiana. The demonstration project proposal was selected by the DOE and awarded to Bethlehem in November 1990. The design of the project was completed in December 1993 and construction was completed in January 1995. The equipment startup period continued to November 1995 at which time the operating and testing program began. The blast furnace test program with different injected coals was completed in December 1998.

  20. Upper arun hydroelectric project feasibility study (phase 1). Volume 1. Report. Export trade information

    SciTech Connect (OSTI)

    Not Available

    1987-09-01T23:59:59.000Z

    The report was prepared for Nepal Electricity Authority (NEA). The primary objective of the study was to compare several alternative development schemes to drive an optimum development plan for exploiting the hydroelectric potential of the Upper Arun River, to be further investigated in phase 2 of the feasibility study. The scope of work included reviewing the original project concepts establishing development alternatives investigations in the following fields: Toposurvey Mapping; Geology Geotechnics; Hydrology; Power Market; and Plan formulations.

  1. Water resources data, Ohio: Water year 1991. Volume 2, St. Lawrence River Basin: Statewide project data

    SciTech Connect (OSTI)

    Shindel, H.L.; Klingler, J.H.; Mangus, J.P.; Trimble, L.E.

    1992-03-01T23:59:59.000Z

    The Water Resources Division of the US Geological Survey (USGS), in cooperation with State agencies, obtains a large amount of data pertaining to the water resources of Ohio each water year. These data, accumulated during many years, constitute a valuable data base for developing an improved understanding of the water resources of the State. To make these data readily available to interested parties outside the USGS, the data are published annually in this report series entitled ``Water Resources Data--Ohio.`` This report (in two volumes) includes records on surface water and ground water in the State. Specifically, it contains: (1) Discharge records for 131 streamflow-gaging stations, 95 miscellaneous sites; (2) stage and content records for 5 streams, lakes, and reservoirs; (3) water-quality for 40 streamflow-gaging stations, 378 wells, and 74 partial-record sites; and (4) water levels for 431 observation wells.

  2. Life cycle costs for the domestic reactor-based plutonium disposition option

    SciTech Connect (OSTI)

    Williams, K.A.

    1999-10-01T23:59:59.000Z

    Projected constant dollar life cycle cost (LCC) estimates are presented for the domestic reactor-based plutonium disposition program being managed by the US Department of Energy Office of Fissile Materials Disposition (DOE/MD). The scope of the LCC estimate includes: design, construction, licensing, operation, and deactivation of a mixed-oxide (MOX) fuel fabrication facility (FFF) that will be used to purify and convert weapons-derived plutonium oxides to MOX fuel pellets and fabricate MOX fuel bundles for use in commercial pressurized-water reactors (PWRs); fuel qualification activities and modification of facilities required for manufacture of lead assemblies that will be used to qualify and license this MOX fuel; and modification, licensing, and operation of commercial PWRs to allow irradiation of a partial core of MOX fuel in combination with low-enriched uranium fuel. The baseline cost elements used for this document are the same as those used for examination of the preferred sites described in the site-specific final environmental impact statement and in the DOE Record of Decision that will follow in late 1999. Cost data are separated by facilities, government accounting categories, contract phases, and expenditures anticipated by the various organizations who will participate in the program over a 20-year period. Total LCCs to DOE/MD are projected at approximately $1.4 billion for a 33-MT plutonium disposition mission.

  3. Process Guide for the Identification and Disposition of S/CI...

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

    Process Guide for the Identification and Disposition of SCI or Defective Items at Department of Energy Facilities Process Guide for the Identification and Disposition of SCI or...

  4. Final environmental information volume for the coke oven gas cleaning project at the Bethlehem Steel Corporation Sparrows Point Plant

    SciTech Connect (OSTI)

    Not Available

    1990-04-24T23:59:59.000Z

    Bethelehem Steel Corporation (BSC) is planning to conduct a demonstration project involving an integrated system that can be retrofitted into coke oven gas handling systems to address a variety of environmental and operational factors in a more cost-effective manner. Successful application of this technology to existing US coke plants could: (1) reduce emissions of sulfur dioxide, cyanide, and volatile organic compounds (including benzene) (2) reduce the cost and handling of processing feed chemicals, (3) disposal costs of nuisance by-products and (4) increase reliability and reduce operation/maintenance requirements for coke oven gas desulfurization systems. The proposed system will remove sulfur from the coke oven gas in the form of hydrogen sulfide using the ammonia indigenous to the gas as the primary reactive chemical. Ammonia and hydrogen cyanide are also removed in this process. The hydrogen sulfide removed from the coke oven gas in routed to a modified Claus plant for conversion to a saleable sulfur by-product. Ammonia and hydrogen cyanide will be catalytically converted to hydrogen, nitrogen, carbon dioxide, and carbon monoxide. The tail gas from the sulfur recovery unit is recycled to the coke oven gas stream, upstream of the new gas cleaning system. The proposed demonstration project will be installed at the existing coke oven facilities at BSC's Sparrows Point Plant. This volume describes the proposed actions and the resulting environmental impacts. 21 refs., 19 figs., 9 tabs.

  5. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

  6. Study of the 1991 unaccounted-for gas volume at the Southern California Gas Company. Final report, January 1991-December 1992. Volume 1. Project summary

    SciTech Connect (OSTI)

    Meshkati, S.; Groot, J.; Law, E.; Ozenne, D.

    1993-01-01T23:59:59.000Z

    A study of unaccounted-for gas (UAF), performed by the Southern California Gas Company (SoCalGas) to determine the UAF gas volume in the SoCalGas system, to identify the factors contributing to UAF, and to estimate the gas volume associated with each factor, is described. It was found that measurement-related effects contributed more than 80% of SoCalGas' 1991 UAF volume. Less than 3% is associated with adjustments to SoCalGas' accounting system, and approximately 6% is associated with losses due to theft. Testing showed that the leakage element contributed only 8% of the UAF volume.

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

    SciTech Connect (OSTI)

    None

    1982-11-01T23:59:59.000Z

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

  8. Plutonium Disposition Program | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeeding accessPeptoidLabPhysics PhysicsPlatinumPlatinumDisposition

  9. Material Disposition | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your Home andDisposition | National Nuclear Security

  10. Petroleum supply annual 1995: Volume 1

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    The {ital Petroleum Supply Annual} contains information on supply and disposition of crude oil and petroleum products. It reflects data collected from the petroleum industry during 1995 through monthly surveys, and it is divided into 2 volumes. This volume contains three sections: summary statistics, detailed statistics, and selected refinery statistics, each with final annual data. (The other volume contains final statistics for each month and replaces data previously published in the {ital Petroleum Supply Monthly}).

  11. Project W-320, 241-C-106 sluicing: Piping calculations. Volume 4

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-07-24T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable. The objective of this calculation is to perform the structural analysis of the Pipe Supports designed for Slurry and Supernate transfer pipe lines in order to meet the requirements of applicable ASME codes. The pipe support design loads are obtained from the piping stress calculations W320-27-I-4 and W320-27-I-5. These loads are the total summation of the gravity, pressure, thermal and seismic loads. Since standard typical designs are used for each type of pipe support such as Y-Stop, Guide and Anchors, each type of support is evaluated for the maximum loads to which this type of supports are subjected. These loads are obtained from the AutoPipe analysis and used to check the structural adequacy of these supports.

  12. SOLERAS - Solar Controlled Environment Agriculture Project. Final report, Volume 5. Science Applications, Incorporated system requirements definition

    SciTech Connect (OSTI)

    Not Available

    1985-01-01T23:59:59.000Z

    This report sets forth the system requirements for a Solar Controlled-Environment Agriculture System (SCEAS) Project. In the report a conceptual baseline system description for an engineering test facility is given. This baseline system employs a fluid roof/roof filter in combination with a large storage tank and a ground water heat exchanger in order to provide cooling and heating as needed. Desalination is accomplished by pretreatment followed by reverse osmosis. Energy is provided by means of photovoltaics and wind machines in conjunction with storage batteries. Site and climatic data needed in the design process are given. System performance specifications and integrated system design criteria are set forth. Detailed subsystem design criteria are presented and appropriate references documented.

  13. Project W-320, 241-C-106 sluicing electrical calculations, Volume 2

    SciTech Connect (OSTI)

    Bailey, J.W.

    1998-08-07T23:59:59.000Z

    This supporting document has been prepared to make the FDNW calculations for Project W-320, readily retrievable. These calculations are required: To determine the power requirements needed to power electrical heat tracing segments contained within three manufactured insulated tubing assemblies; To verify thermal adequacy of tubing assembly selection by others; To size the heat tracing feeder and branch circuit conductors and conduits; To size protective circuit breaker and fuses; and To accomplish thermal design for two electrical heat tracing segments: One at C-106 tank riser 7 (CCTV) and one at the exhaust hatchway (condensate drain). Contents include: C-Farm electrical heat tracing; Cable ampacity, lighting, conduit fill and voltage drop; and Control circuit sizing and voltage drop analysis for the seismic shutdown system.

  14. Breckinridge Project, initial effort. Report VII, Volume II. Environmental baseline report

    SciTech Connect (OSTI)

    none,

    1982-01-01T23:59:59.000Z

    Ashland Synthetic Fuels, Inc. (ASFI) and Airco Energy Company, Inc. (AECI) have recently formed the Breckinridge Project and are currently conducting a process and economic feasibility study of a commercial scale facility to produce synthetic liquid fuels from coal. The coal conversion process to be used is the H-COAL process, which is in the pilot plant testing stage under the auspices of the US Department of Energy at the H-COAL Pilot Plant Project near Catlettsburg, Kentucky. The preliminary plans for the commercial plant are for a 18,140 metric ton/day (24,000 ton/day) nominal coal assumption capacity utilizing the abundant high sulfur Western Kentucky coals. The Western Kentucky area offers a source of the coal along with adequate water, power, labor, transportation and other factors critical to the successful siting of a plant. Various studies by federal and state governments, as well as private industry, have reached similar conclusions regarding the suitability of such plant sites in western Kentucky. Of the many individual sites evaluated, a site in Breckinridge County, Kentucky, approximately 4 kilometers (2.5 miles) west of the town of Stephensport, has been identified as the plant location. Actions have been taken to obtain options to insure that this site will be available when needed. This report contains an overview of the regional setting and results of the baseline environmental studies. These studies include collection of data on ambient air and water quality, sound, aquatic and terrestrial biology and geology. This report contains the following chapters; introduction, review of significant findings, ambient air quality monitoring, sound, aquatic ecology, vegetation, wildlife, geology, soils, surface water, and ground water.

  15. Greater-than-Class C low-level waste characterization. Appendix I: Impact of concentration averaging low-level radioactive waste volume projections

    SciTech Connect (OSTI)

    Tuite, P.; Tuite, K.; O`Kelley, M.; Ely, P.

    1991-08-01T23:59:59.000Z

    This study provides a quantitative framework for bounding unpackaged greater-than-Class C low-level radioactive waste types as a function of concentration averaging. The study defines the three concentration averaging scenarios that lead to base, high, and low volumetric projections; identifies those waste types that could be greater-than-Class C under the high volume, or worst case, concentration averaging scenario; and quantifies the impact of these scenarios on identified waste types relative to the base case scenario. The base volume scenario was assumed to reflect current requirements at the disposal sites as well as the regulatory views. The high volume scenario was assumed to reflect the most conservative criteria as incorporated in some compact host state requirements. The low volume scenario was assumed to reflect the 10 CFR Part 61 criteria as applicable to both shallow land burial facilities and to practices that could be employed to reduce the generation of Class C waste types.

  16. The Laconia, New Hampshire bottom ash paving project: Volume 3, Physical Performance Testing Report

    SciTech Connect (OSTI)

    NONE

    1996-03-01T23:59:59.000Z

    Bottom ash is the principal waste stream from the combustion of municipal solid waste (MSW). It is comprised of grate ash (97%), the slag material discharged at the end of the grate system, and grate sifting (3%), the material that melts or falls through the grate structure. This project was conducted to demonstrate the feasibility of using municipal solid waste grate ash as an aggregate substitute in the construction of a pavement binder course for a portion of Rt. 3 in Laconia, New Hampshire. The research was conducted over a two year period during 1993 and 1994. This study is the culmination of an earlier two year characterization study between 1990 and 1992 that documented the physical and environmental characteristics of the bottom ash as it was produced at the Concord, N.H. waste-to-energy (@) facility and used in an asphaltic binder course. Together, these two studies provide a complete evaluation of the potential for using grate ash or bottom ash in asphalt binder course or as recycled asphalt pavement (RAP) in base courses in pavements.

  17. Electric and Magnetic Fields (EMF) RAPID Program Engineering Project 8: FINAL REPORT, Evaluation of Field Reduction Technologies, Volume 1 (Report) and Volume 2 (Appendices)

    SciTech Connect (OSTI)

    Commonwealth Associates, Inc.; IIT Research Institute

    1997-08-01T23:59:59.000Z

    This draft report consists of two volumes. Volume 1, the main body, contains an introducto~ sectionj an overview of magnetic fields sectio~ and field reduction technology evaluation section. Magnetic field reduction methods are evalpated for transmission lines, distribution Iines,sulxtations, building wiring applkmd machinery, and transportation systems. The evaluation considers effectiveness, co% and other ftiors. Volume 2 contains five appendices, Append~ A presents magnetic field shielding information. Appendices B and C present design assumptions and magnetic field plots for transmission and distribution lines, respectively. Appendices D and E present cost estimate details for transmission and distribution limes, respectively.

  18. Summary - Preliminary TRA of the Calcine Disposition Project

    Office of Environmental Management (EM)

    calcine through an am go treatment by . The HIP proc he calcine to a and leach rates glass. The ca n the conceptua ecision-1 (CD- preliminary de ypically recom be at a Techno...

  19. Performance Based Trending of Waste Disposition Project Data...

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

    Full-Waveform Inversion of 3D-9C VSP data from Bradys EGS Site and Update of the Brady Reservoir Scale Model Lessons Learned Quarterly Report Cumulative Index Better Buildings...

  20. Major Risk Factors Integrated Facility Disposition Project - Oak Ridge |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732on

  1. Assessment of the Integrated Facility Disposition Project at Oak Ridge

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'s ReplyApplication of Training April 30,WindAssessment ofASSESSMENTNational

  2. CXD 4607, Disposition of Kerr Hollow Quarry Shredder Project (4607)

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z C o . C l a r8.0 -CURRICULUM9831 Wall

  3. Uranium Downblending and Disposition Project Technology Readiness Assessment

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium TransferonUS-India EnergyUnlocking CustomerOutreachReport onEducation

  4. Master EM Project Definition Rating Index - Facility Disposition Definitions

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment3311, 3312), October 20122 DOE Hydrogenis Winding theremoved3243

  5. Major Risk Factors to the Integrated Facility Disposition Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions forCheney suggesting a billVehiclesJune59Products28,Into Service ToTech

  6. Summary - Preliminary TRA of the Calcine Disposition Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the Passing of AdmiraltheOil and LessOak Ridge, TNCalcine

  7. Proliferation resistance criteria for fissile material disposition issues

    SciTech Connect (OSTI)

    Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A. [Los Alamos National Lab., NM (United States); Tolk, K.M.; Mangan, D.L. [Sandia National Labs., Albuquerque, NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

    1995-09-01T23:59:59.000Z

    The 1994 National Acdaemy of Sciences study ``Management and Disposition of Excess Weapons Plutonium`` defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ``Standards`` from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

  8. Petroleum supply annual 1993. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1993 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1993, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Below is a description of each section in Volume 1 of the PSA.

  9. Petroleum supply annual 1994. Volume 1

    SciTech Connect (OSTI)

    NONE

    1995-05-22T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1994 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1994, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Below is a description of each section in Volume 1 of the PSA.

  10. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Not Available

    1990-12-01T23:59:59.000Z

    Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

  11. Petroleum supply annual 1993. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This publication contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1993 through annual and monthly surveys. This second volume contains final statistics for each month of 1993.

  12. Natural gas annual 1994: Volume 2

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. This report, Volume 2, presents historical data fro the Nation from 1930 to 1994, and by State from 1967 to 1994.

  13. Americium/Curium Disposition Life Cycle Planning Study

    SciTech Connect (OSTI)

    Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

    1998-04-30T23:59:59.000Z

    At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS).

  14. EIS-0327: Disposition of Scrap Metals Programmatic EIS

    Broader source: Energy.gov [DOE]

    This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

  15. A Study of Cattle Disposition: Exploring QTL Associated with Temperament

    E-Print Network [OSTI]

    Boldt, Clayton Ryan

    2008-05-16T23:59:59.000Z

    In any production setting, cattle disposition (temperament) has a great impact on handling and performance. Thus, behavior can be economically important, yielding the rationale for study. Wegenhoft (2005) previously identified several quantitative...

  16. Highly enriched uranium (HEU) storage and disposition program plan

    SciTech Connect (OSTI)

    Arms, W.M.; Everitt, D.A.; O`Dell, C.L.

    1995-01-01T23:59:59.000Z

    Recent changes in international relations and other changes in national priorities have profoundly affected the management of weapons-usable fissile materials within the United States (US). The nuclear weapon stockpile reductions agreed to by the US and Russia have reduced the national security requirements for these fissile materials. National policies outlined by the US President seek to prevent the accumulation of nuclear weapon stockpiles of plutonium (Pu) and HEU, and to ensure that these materials are subjected to the highest standards of safety, security and international accountability. The purpose of the Highly Enriched Uranium (HEU) Storage and Disposition Program Plan is to define and establish a planned approach for storage of all HEU and disposition of surplus HEU in support of the US Department of Energy (DOE) Fissile Material Disposition Program. Elements Of this Plan, which are specific to HEU storage and disposition, include program requirements, roles and responsibilities, program activities (action plans), milestone schedules, and deliverables.

  17. SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP

    SciTech Connect (OSTI)

    Allender, J.; Mcclard, J.; Christopher, J.

    2012-06-08T23:59:59.000Z

    The U.S. Department of Energy (DOE) is preparing a Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (SEIS). Included in the evaluation are up to 6 metric tons (MT) of plutonium in the form of impure oxides and metals for which a disposition plan has not been decided, among options that include preparation as feed for the Mixed Oxide Fuel Fabrication Facility; disposing to high-level waste through the Savannah River Site (SRS) HB Line and H Canyon; can-in-canister disposal using the SRS Defense Waste Processing Facility; and preparation for disposal at the Waste Isolation Pilot Plant (WIPP). DOE and SRS have identified at least 0.5 MT of plutonium that, because of high levels of chemical and isotopic impurities, is impractical for disposition by methods other than the WIPP pathway. Characteristics of these items and the disposition strategy are discussed.

  18. 1. What did you do for your research project? My research project was titled "The Marcellus Shale Environmental Review." It focuses on High Volume

    E-Print Network [OSTI]

    1. What did you do for your research project? My research project was titled "The Marcellus Shale. This is a process of obtaining energy through the propagation of fractures within the Marcellus Shale

  19. 2015-03-09 Capital Asset Project List.xls

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

    9302020 On Hold Pre CD-2 CD-0 560,000,000 Idaho National Laboratory IFDP Integrated Facility Disposition Project (IFDP) 12312015 Active CD-1 14,130,000,000 Oak Ridge...

  20. Natural gas annual 1992: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-11-22T23:59:59.000Z

    This document provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and education institutions. The 1992 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production top its end use. Tables summarizing natural gas supply and disposition from 1988 to 1992 are given for each Census Division and each State. Annual historical data are shown at the national level. Volume 2 of this report presents State-level historical data.

  1. TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Beams, J.; Sanders, K.; Myers, L.

    2013-07-16T23:59:59.000Z

    Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

  2. Documentation of key factors for successful reconstruction of high volume roadways: two case study projects in Michigan

    E-Print Network [OSTI]

    De Las Casas Moncloa, Rodrigo

    2001-01-01T23:59:59.000Z

    identified factors and practices that contributed to the success of highway concrete rehabilitation and reconstruction projects. The research was conducted on four specific topics related to highway projects: constructibility, contracting, scheduling...

  3. Petroleum supply annual, 1997. Volume 1

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 48 tabs.

  4. Petroleum supply annual 1998: Volume 1

    SciTech Connect (OSTI)

    NONE

    1999-06-01T23:59:59.000Z

    The ``Petroleum Supply Annual`` (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1998, and replaces data previously published in the PSA. The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 59 tabs.

  5. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Volume 1, Calculations, Final design for construction

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    Volume one contains calculations for: embankment design--embankment material properties; Union Carbide site--bedrock contours; vicinity properties--origin of contamination; North Continent and Union Carbide sites contaminated materials--excavation quantities; and demolition debris--quantity estimate.

  6. TVA coal-gasification commercial demonstration plant project. Volume 5. Plant based on Koppers-Totzek gasifier. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-11-01T23:59:59.000Z

    This volume presents a technical description of a coal gasification plant, based on Koppers-Totzek gasifiers, producing a medium Btu fuel gas product. Foster Wheeler carried out a conceptual design and cost estimate of a nominal 20,000 TPSD plant based on TVA design criteria and information supplied by Krupp-Koppers concerning the Koppers-Totzek coal gasification process. Technical description of the design is given in this volume.

  7. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT X COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-11-15T23:59:59.000Z

    The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is the preferred option for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium in the late 1990's. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Recent FY05 studies have further investigated the LaBS Frit B formulation as well as development of a newer LaBS formulation denoted as LaBS Frit X. The objectives of this present task were to fabricate plutonium loaded LaBS Frit X glass and perform corrosion testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit X composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was thoroughly characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL using quenched Pu Frit X glass with varying exposed surface areas. Effects of isothermal and can-in-canister heat treatments on the Pu Frit X glass were also investigated. Another series of PCTs were performed on these different heat-treated Pu Frit X glasses. Leachates from all these PCTs were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation.

  8. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-04-24T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

  9. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Carter, J.

    2011-01-03T23:59:59.000Z

    The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

  10. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Jones, R.; Carter, J.

    2010-10-13T23:59:59.000Z

    The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

  11. Independent Assessment of the Savannah River Site High-Level Waste Salt Disposition Alternatives Evaluation

    SciTech Connect (OSTI)

    J. T. Case (DOE-ID); M. L. Renfro (INEEL)

    1998-12-01T23:59:59.000Z

    This report presents the results of the Independent Project Evaluation (IPE) Team assessment of the Westinghouse Savannah River Company High-Level Waste Salt Disposition Systems Engineering (SE) Team's deliberations, evaluations, and selections. The Westinghouse Savannah River Company concluded in early 1998 that production goals and safety requirements for processing SRS HLW salt to remove Cs-137 could not be met in the existing In-Tank Precipitation Facility as currently configured for precipitation of cesium tetraphenylborate. The SE Team was chartered to evaluate and recommend an alternative(s) for processing the existing HLW salt to remove Cs-137. To replace the In-Tank Precipitation process, the Savannah River Site HLW Salt Disposition SE Team downselected (October 1998) 140 candidate separation technologies to two alternatives: Small-Tank Tetraphenylborate (TPB) Precipitation (primary alternative) and Crystalline Silicotitanate (CST) Nonelutable Ion Exchange (backup alternative). The IPE Team, commissioned by the Department of Energy, concurs that both alternatives are technically feasible and should meet all salt disposition requirements. But the IPE Team judges that the SE Team's qualitative criteria and judgments used in their downselection to a primary and a backup alternative do not clearly discriminate between the two alternatives. To properly choose between Small-Tank TPB and CST Ion Exchange for the primary alternative, the IPE Team suggests the following path forward: Complete all essential R and D activities for both alternatives and formulate an appropriate set of quantitative decision criteria that will be rigorously applied at the end of the R and D activities. Concurrent conceptual design activities should be limited to common elements of the alternatives.

  12. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1, Volume 3. Calculations, Final design for construction

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    Volume three contains calculations for: site hydrology--rainfall intensity, duration, and frequency relations; site hydrology-- probable maximum precipitation; erosion protection--rock quality evaluation; erosion protection--embankment top and side slope; erosion protection--embankment toe apron; erosion protection-- gradations and layer thicknesses; Union Carbide site--temporary drainage ditch design; Union Carbide site--retention basin sediment volume; Union Carbide site--retention basin sizing; Burro Canyon site temporary drainage--temporary drainage facilities; and Union Carbide site temporary drainage--water balance.

  13. Fissile material disposition program final immobilization form assessment and recommendation

    SciTech Connect (OSTI)

    Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1997-10-03T23:59:59.000Z

    Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

  14. Wildlife Impact Assessment and Summary of Previous Mitigation Related to Hydroelectric Projects in Montana, Volume One, Libby Dam Project, Operator, U.S. Army Corps of Engineers.

    SciTech Connect (OSTI)

    Yde, Chris A.

    1984-10-01T23:59:59.000Z

    This assessment addresses the impacts to the wildlife populations and wildlife habitats due to the Libby Dam project on the Kootenai River and previous mitigation of these losses. The current assessment documents the best available information concerning the impacts to the wildlife populations inhabiting the project area prior to construction of the dam and creation of the reservoir. Many of the impacts reported in this assessment differ from those contained in the earlier document compiled by the Fish and Wildlife Service; however, this document is a thorough compilation of the available data (habitat and wildlife) and, though conservative, attempts to realistically assess the impacts related to the Libby Dam project. Where appropriate the impacts resulting from highway construction and railroad relocation were included in the assessment. This was consistent with the previous assessments.

  15. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Volume 2, Calculations, Final design for construction

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    Volume two contains calculations for: embankment design--slope stability analysis; embankment design--excavation stability; embankment design--settlement and cover cracking analysis; radon barrier design--statistical analysis of ra-226 concentrations for North Continent and Union Carbide sites; radon barrier design--RAECOM input data; radon barrier design--design thickness; and cover design--frost penetration depth.

  16. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1, Volume 4. Calculations, Final design for construction

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    Volume four contains calculations for: Borrow areas--site evaluation; temporary facilities--material quantities; embankment quantities--excavation and cover materials; Burro Canyon site excavation quantities--rippable and unrippable materials; site restoration--earthwork quantities and seeding; and bid schedule quantities and material balance.

  17. Plutonium stabilization and disposition focus area, FY 1999 and FY 2000 multi-year program plan

    SciTech Connect (OSTI)

    NONE

    1998-03-01T23:59:59.000Z

    Consistent with the Environmental Management`s (EM`s) plan titled, ``Accelerating Cleanup: Paths to Closure``, and ongoing efforts within the Executive Branch and Congress, this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects are effectively managed and measured. The Plutonium Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization of nuclear materials and their subsequent safe storage and final disposition. The scope of PFA activities includes the complete spectrum of plutonium materials, special isotopes, and other fissile materials. The PFA enables solutions to site-specific and complex-wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999 and FY 2000 is provided.

  18. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-06-22T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

  19. Materials and process engineering projects for the Sandia National Laboratories/Newly Independent States Industrial Partnering Program. Volume 2

    SciTech Connect (OSTI)

    Zanner, F.J.; Moffatt, W.C.

    1995-07-01T23:59:59.000Z

    In July, 1994, a team of materials specialists from Sandia and US. Industry traveled to Russia and the Ukraine to select and fund projects in materials and process technology in support of the Newly Independent States/Industrial Partnering Program (NIS/IPP). All of the projects are collaborations with scientists and Engineers at NIS Institutes. Each project is scheduled to last one year, and the deliverables are formatted to supply US. Industry with information which will enable rational decisions to be made regarding the commercial value of these technologies. This work is an unedited interim compilation of the deliverables received to date.

  20. Materials and process engineering projects for the Sandia National Laboratories/Newly Independent States Industrial Partnering Program. Volume 1

    SciTech Connect (OSTI)

    Zanner, F.J.; Moffatt, W.C.

    1995-07-01T23:59:59.000Z

    In July, 1994, a team of materials specialists from Sandia and U S Industry traveled to Russia and the Ukraine to select and fund projects in materials and process technology in support of the Newly Independent States/Industrial Partnering Program (NIS/IPP). All of the projects are collaborations with scientists and Engineers at NIS Institutes. Each project is scheduled to last one year, and the deliverables are formatted to supply US Industry with information which will enable rational decisions to be made regarding the commercial value of these technologies. This work is an unedited interim compilation of the deliverables received to date.

  1. California Institute of Technology Records Retention and Disposition Policy

    E-Print Network [OSTI]

    of the Records Retention and Disposition Policy is to establish and maintain a uniform records management policy activities and are subject to records management review and evaluation prior to any decisions regarding of Technology Records Retention Schedule ("Retention Schedule"). Department and division management should

  2. Evaluation of the Energy-Related Inventions Program. Volume 1. Analysis of case studies of supported projects

    SciTech Connect (OSTI)

    Rorke, M.G.; Bronfman, L.M.; Soderstrom, E.J.

    1983-02-01T23:59:59.000Z

    This volume reports the analysis of the results of 30 case studies of grantees funded by the Energy-Related Inventions Program (ERIP). ERIP is one of several federal programs supporting invention and innovation in the private sector. It is a relatively small program with an annual budget of $5 to 6 million that focuses its attention on the independent inventor or small business with an energy-related invention. Support to the inventory or small business comes primarily in the form of a grant. The overall goal of the program is to stimulate innovation by individuals and small businesses and to assist in the development of promising energy-related inventions for eventual commercialization. This volume is an aggregation and synthesis of the data gathered in the case studies. (Volume 2 contains the case studies.) The case studies explore in-depth the characteristics, perceptions, and experiences of inventors and agency personnel who have participated in the ERIP. Thus they are a rich source of information for use in evaluating the process by which the program's goals and objectives are implemented and for evaluating the program;s usefulness in producing the results intended by the legislative mandate.

  3. FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

  4. Cost-effective facility disposition planning with safety and health lessons learned and good practices from the Oak Ridge Decontamination and Decommissioning Program

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    An emphasis on transition and safe disposition of DOE excess facilities has brought about significant challenges to managing worker, public, and environmental risks. The transition and disposition activities involve a diverse range of hazardous facilities that are old, poorly maintained, and contain radioactive and hazardous substances, the extent of which may be unknown. In addition, many excess facilities do not have historical facility documents such as operating records, plant and instrumentation diagrams, and incident records. The purpose of this report is to present an overview of the Oak Ridge Decontamination and Decommissioning (D and D) Program, its safety performance, and associated safety and health lessons learned and good practices. Illustrative examples of these lessons learned and good practices are also provided. The primary focus of this report is on the safety and health activities and implications associated with the planning phase of Oak Ridge facility disposition projects. Section 1.0 of this report provides the background and purpose of the report. Section 2.0 presents an overview of the facility disposition activities from which the lessons learned and good practices discussed in Section 3.0 were derived.

  5. Wadter Resources Data Ohio: Water year 1994. Volume 2, St. Lawrence River Basin and Statewide Project Data

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    The Water Resources Division of the US Geological Survey (USGS), in cooperation with State agencies, obtains a large amount of data each water year (a water year is the 12-month period from October 1 through September 30 and is identified by the calendar year in which it ends) pertaining to the water resources of Ohio. These data, accumulated during many years, constitute a valuable data base for developing an improved understanding of the water resources of the State. To make these data readily available to interested parties outside the USGS, they are published annually in this report series entitled ``Water Resources Data--Ohio.`` This report (in two volumes) includes records on surface water and ground water in the State. Specifically, it contains: (1) Discharge records for streamflow-gaging stations, miscellaneous sites, and crest-stage stations; (2) stage and content records for streams, lakes, and reservoirs; (3) water-quality data for streamflow-gaging stations, wells, synaptic sites, and partial-record sites; and (4) water-level data for observation wells. Locations of lake- and streamflow-gaging stations, water-quality stations, and observation wells for which data are presented in this volume are shown in figures ga through 8b. The data in this report represent that part of the National Water Data System collected by the USGS and cooperating State and Federal agencies in Ohio. This series of annual reports for Ohio began with the 1961 water year with a report that contained only data relating to the quantities of surface water. For the 1964 water year, a similar report was introduced that contained only data relating to water quality. Beginning with the 1975 water year, the report was changed to present (in two to three volumes) data on quantities of surface water, quality of surface and ground water, and ground-water levels.

  6. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 3, Model parameters: Sandia WIPP Project

    SciTech Connect (OSTI)

    Not Available

    1992-12-29T23:59:59.000Z

    This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter.

  7. Unaccounted-for gas project. Measurement Task Force (non-orifice meter studies). Volume 2A. Final report

    SciTech Connect (OSTI)

    Luttrell, D.J.; Noistering, R.H.; Peterson, J.D.; Cowgill, R.M.; Waller, R.L.

    1990-06-01T23:59:59.000Z

    The study was conducted to determine unaccounted-for (UAF) gas volumes resulting from operating Pacific Gas and Electric Co.'s transmission and distribution systems during 1987. The Measurement Task Force identified the amount of UAF attributable to measurement inaccuracies. Results show that the major residential measurement-related UAF elements, fixed-factor temperature and elevation/barometric pressure effects, contribute to UAF due to assumptions inherent in the billing calculation for average temperature and elevation which are then applied to all residential customers.

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

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-08-17T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1995-05-01T23:59:59.000Z

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

  10. Sweet Lake geopressured-geothermal project, Magma Gulf-Technadril/DOE Amoco fee. Volume III. Final report. Annual report, February 1982-March 1985

    SciTech Connect (OSTI)

    Durham, C.O. Jr.; O'Brien, F.D.; Rodgers, R.W. (eds.) [eds.

    1985-01-01T23:59:59.000Z

    This report presents the results of the testing of Sand 3 (15,245 to 15,280 feet in depth) which occurred from November 1983 to March 1984 and evaluates these new data in comparison to results from the testing of Sand 5 (15,385 to 15,415 feet in depth) which occurred from June 1981 to February 1982. It also describes the reworking of the production and salt water disposal wells preparatory to the Sand 3 testing as well as the plug and abandon procedures requested to terminate the project. The volume contains two parts: Part 1 includes the text and accompanying plates, figures and tables; Part 2 consists of the appendixes including auxiliary reports and tabulations.

  11. Disposition of Radioisotope Thermoelectric Generators Currently Located at the Oak Ridge National Laboratory - 12232

    SciTech Connect (OSTI)

    Glenn, J. [U.S. Department of Energy, Oak Ridge Operations Office, 200 Administrative Road, Oak Ridge, TN 37830 (United States); Patterson, J.; DeRoos, K. [SEC Federal Services Corporation (SEC), 2800 Solway Road, Knoxville, TN 37931 (United States); Patterson, J.E.; Mitchell, K.G. [Strata-G, LLC, 2027 Castaic Lane, Knoxville, TN 37932 (United States)

    2012-07-01T23:59:59.000Z

    Under the American Recovery and Reinvestment Act (ARRA), the U.S. Department of Energy (DOE) awarded SEC Federal Services Corporation (SEC) a 34-building demolition and disposal (D and D) project at the Oak Ridge National Laboratory (ORNL) that included the disposition of six Strontium (Sr-90) powered Radioisotope Thermoelectric Generators (RTGs) stored outside of ORNL Building 3517. Disposition of the RTGs is very complex both in terms of complying with disposal facility waste acceptance criteria (WAC) and U.S. Department of Transportation (DOT) requirements for packaging and transportation in commerce. Two of the RTGs contain elemental mercury which requires them to be Land Disposal Restrictions (LDR) compliant prior to disposal. In addition, all of the RTGs exceed the Class C waste concentration limits under Nuclear Regulatory Commission (NRC) Waste Classification Guidelines. In order to meet the LDR requirements and Nevada National Security Site (NNSS) WAC, a site specific treatability variance for mercury was submitted to the U.S. Environmental Protection Agency (EPA) to allow macro-encapsulation to be an acceptable treatment standard for elemental mercury. By identifying and confirming the design configuration of the mercury containing RTGs, the SEC team proved that the current configuration met the macro-encapsulation standard of 40 Code of Federal Regulations (CFR) 268.45. The SEC Team also worked with NNSS to demonstrate that all radioisotope considerations are compliant with the NNSS low-level waste (LLW) disposal facility performance assessment and WAC. Lastly, the SEC team determined that the GE2000 Type B cask met the necessary size, weight, and thermal loading requirements for five of the six RTGs. The sixth RTG (BUP-500) required a one-time DOT shipment exemption request due to the RTG's large size. The DOT exemption justification for the BUP-500 relies on the inherent robust construction and material make-up of the BUP- 500 RTG. DOE-ORO, SEC, and the entire SEC RTG team are nearing the conclusion of the Sr-90 RTG disposition challenge - a legacy now 50 years in the making. Over 600,000 Ci of Sr-90 waste await disposal and its removal from ORNL will mark an historical moment in the clean-up of the cold-war legacy in the ORNL central industrial area. Elimination (i.e., removal) of the RTGs will reduce security risks at ORNL and disposal will permanently eliminate security risks. The RTGs will eventually decay to benign levels within a reasonable timeframe relative to radiological risks posed by long-lived isotopes. The safety authorization basis at ORNL Building 3517 will be reduced enabling greater operational flexibility in future clean-out and D and D campaigns. Upon disposition the Department of Energy will realize reduced direct and indirect surveillance and maintenance costs that can be reapplied to accelerated and enhanced clean-up of the Oak Ridge Reservation. At present, waste profiles for the RTGs are developed and under review by NNSS RWAP staff and approval authorities. Disposition schedule is driven by the availability of compliant shipping casks necessary to safely transport the RTGs from ORNL to NNSS. The first disposal of the RCA RTG is expected in April 2012 and the remaining RTGs disposed in 2012 and 2013. (authors)

  12. Alaska Regional Energy Resources Planning Project. Phase 2: coal, hydroelectric and energy alternatives. Volume I. Beluga Coal District Analysis

    SciTech Connect (OSTI)

    Rutledge, G.; Lane, D.; Edblom, G.

    1980-01-01T23:59:59.000Z

    This volume deals with the problems and procedures inherent in the development of the Beluga Coal District. Socio-economic implications of the development and management alternatives are discussed. A review of permits and approvals necessary for the initial development of Beluga Coal Field is presented. Major land tenure issues in the Beluga Coal District as well as existing transportation routes and proposed routes and sites are discussed. The various coal technologies which might be employed at Beluga are described. Transportation options and associated costs of transporting coal from the mine site area to a connecting point with a major, longer distance transportation made and of transporting coal both within and outside (exportation) the state are discussed. Some environmental issues involved in the development of the Beluga Coal Field are presented. (DMC)

  13. SNM measurement uncertainites: potential impacts for materials disposition

    SciTech Connect (OSTI)

    Fearey, B.L.; Burr, T.L.; Pickrell, M.M.

    1996-09-01T23:59:59.000Z

    A discussion of nuclear material measurement uncertainties and impacts to the Materials Disposition (MD) Program is presented. Many of the options under consideration by the disposition program present new measurement challenges include significant material processing throughputs, a variety of material forms, unique waste streams, and difficult-to-measure matrices. There are also some questions regarding the ability to achieve International Atomic Energy Agency (IAEA) verification requirements and to achieve measurement uncertainties that are small enough to meet the IAEA loss detection goals. We present a detailed formalism for determining the measurement error for nondestructive assay systems applied to the MD Program, which is an essential component for planning the safeguards and security of these systems.

  14. Plutonium disposition via immobilization in ceramic or glass

    SciTech Connect (OSTI)

    Gray, L.W.; Kan, T.; Shaw, H.F.; Armantrout, A.

    1997-03-05T23:59:59.000Z

    The management of surplus weapons plutonium is an important and urgent task with profound environmental, national, and international security implications. In the aftermath of the Cold War, Presidential Policy Directive 13, and various analyses by renown scientific, technical, and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths for the long term disposition of surplus weapons- usable plutonium. The central goal of this effort is to render surplus weapons plutonium as inaccessible and unattractive for reuse in nuclear weapons as the much larger and growing stock of plutonium contained in spent fuel from civilian reactors. One disposition option being considered for surplus plutonium is immobilization, in which the plutonium would be incorporated into a glass or ceramic material that would ultimately be entombed permanently in a geologic repository for high-level waste.

  15. Joint U.S./Russian plutonium disposition study: Nonproliferation issues

    SciTech Connect (OSTI)

    Jaeger, C. [Sandia National Labs., Albuquerque, NM (United States); Erkkila, B.; Fearey, B. [Los Alamos National Lab., NM (United States); Ehinger, M. [Oak Ridge National Lab., TN (United States); McAllister, S. [Lawrence Livermore National Lab., CA (United States); Chitaykin, V. [Inst. of Physics and Power Engineering, Obninsk (Russian Federation); Ptashny, V. [Inst. of Technical Physics, Snezhinsk (Russian Federation)

    1996-07-01T23:59:59.000Z

    In an effort to establish joint activities in the disposition of fissile materials from nuclear materials, the US and Russia agreed to conduct joint work to develop consistent comparisons of various alternatives for the disposition of weapons-grade plutonium. Joint working groups were established for the analysis of alternatives for plutonium management for water reactors, fast reactors, storage, geological formations, immobilization and stabilization of solutions and other forms. In addition cross-cutting working groups were established for economic analysis and nonproliferation (NP). This paper reviews the activities of the NP working group in support of these studies. The NP working group provided integrated support in the area of nuclear NP to the other US/Russian Study teams. It involved both domestic safeguards and security and international safeguards. The analysis of NP involved consideration of the resistance to theft or diversion and resistance to retrieval, extraction or reuse.

  16. Update of the Used Fuel Disposition Campaign Implementation Plan

    SciTech Connect (OSTI)

    Jens Birkholzer; Robert MacKinnon; Kevin McMahon; Sylvia Saltzstein; Ken Sorenson; Peter Swift

    2014-09-01T23:59:59.000Z

    This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.

  17. Proposed Tenaska Washington II Generation Project : Final Environmental Impact Statement. Volume 1: Environmental Analysis and Technical Appendices.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    1994-01-01T23:59:59.000Z

    BPA is considering whether to purchase electrical power from a proposed privately-owned combustion-turbine electrical generation plant in Washington. The plant would be fired by natural gas and would use combined-cycle technology to generate 240 average megawatts (aMW) of energy. The plant would be developed, owned, and operated by Tenaska Washington Partners II, L.P. The project would be located about 19 kilometers (12 miles) southeast of downtown Tacoma in the Frederickson Industrial Area, Pierce County. The proposed plant would occupy about half of a 6.4-hectare (16-acre) parcel and would be consistent with the industrial character of its surroundings. The proposed site is currently undeveloped and zoned for industrial use by the county. Main environmental concerns identified in the scoping process and in comments on the Draft Environmental Impact Statement (EIS) include: (1) potential air quality impacts, such as emissions and their contribution to the {open_quotes}greenhouse{close_quotes} effect; (2) potential health and safety impacts, such as nuisance odors, plant safety, visibility and heat-emission systems which may affect low-flying planes and potential health effects of electric and magnetic fields; and (3) potential water quality and quantity impacts, such as the amount of wastewater to be discharged, the source and amount of water required for plant operation. These and other issues are discussed in detail in the EIS. The proposed project already includes many features designed to reduce environmental impacts. Based on investigations performed for the EIS, no significant unavoidable adverse environmental impacts associated with the proposed project were identified, and no evidence emerged to suggest that the proposed action is controversial. The EIS is being mailed to numerous agencies, groups, and individuals (see Section 8.0). There will be a 30-day no-action period before any decisions are made and the Record of Decision is signed.

  18. MPC&A for plutonium disposition in the Russian federation

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1995-08-08T23:59:59.000Z

    The issue of what to do with excess fissile materials from dismantled nuclear weapons has been discussed for a number of years. The options or alternatives commanding the most attention were identified by the American National Academy of Sciences. For plutonium these options are: (1) the fabrication and use of mixed-oxide (MOX) reactor fuel followed by the disposal of the spent fuel, or (2) vitrification (immobilization) of plutonium combined with highly radioactive material followed by direct disposal. The Academy report also identified the alternative of disposal in a deep borehole as requiring further study before being eliminated or accepted. The report emphasized security of nuclear materials as a principal factor in considering management and disposition decisions. Security of materials is particularly important in the near term-now-long before ultimate disposition can be accomplished. The MOX option was the subject of a NATO workshop held at Obninsk, Russia in October 1994. Hence this paper does not deal with the MOX alternative in detail. It deals with the following: materials protection, control, and accounting (MPC&A) for immobilization and disposal; the immobilization vs MOX alternatives; the security of disposed plutonium; the need to demonstrate MTC&A for plutonium disposition; and, finally, a recommended investment to quickly and inexpensively improve the protection of fissile materials in Russia. It is the author`s view that near-term management is of overriding importance. That is, with respect to the ultimate disposition of excess nuclear materials, how we get there is more important than where we are going.

  19. Preliminary siting characterization Salt Disposition Facility - Site B

    SciTech Connect (OSTI)

    Wyatt, D.

    2000-01-04T23:59:59.000Z

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

  20. Processing and Disposition of Special Actinide Target Materials - 13138

    SciTech Connect (OSTI)

    Robinson, Sharon M.; Patton, Brad D. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Allender, Jeffrey S. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

    2013-07-01T23:59:59.000Z

    The Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960's through the 1980's by irradiating targets in high-flux reactors at the Savannah River Site (SRS) to produce special heavy isotopes for DOE programmatic use, scientific research, and industrial and medical applications. Among the products were californium-252, heavy curium (including Cm-246 through Cm-248), and plutonium-242 and -244. Many of the isotopes are still in demand today, and they can be recovered from the remaining targets previously irradiated at SRS or produced from the recovered isotopes. Should the existing target materials be discarded, the plutonium (Pu) and curium (Cm) isotopes cannot be replaced readily with existing production sources. Some of these targets are stored at SRS, while other target material is stored at Oak Ridge National Laboratory (ORNL) at several stages of processing. The materials cannot be stored in their present form indefinitely. Their long-term management involves processing items for beneficial use and/or for disposition, using storage and process facilities at SRS and ORNL. Evaluations are under way for disposition options for these materials, and demonstrations of improved flow sheets to process the materials are being conducted at ORNL and the Savannah River National Laboratory (SRNL). The disposition options and a management evaluation process have been developed. Processing demonstrations and evaluations for these unique materials are under way. (authors)

  1. Safeguards and security issues for the disposition of fissile materials

    SciTech Connect (OSTI)

    Jaeger, C.D.; Moya, R.W.; Duggan, R.A.; Mangan, D.L.; Tolk, K.M. [Sandia National Labs., Albuquerque, NM (United States); Rutherford, D.; Fearey, B. [Los Alamos National Lab., NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

    1995-07-01T23:59:59.000Z

    The Department of Energy`s Office of Fissile Material Disposition (FMD) is analyzing long-term storage and disposition options for surplus weapons-usable fissile materials, preparing a programmatic environmental impact statement (PEIS), preparing for a record of decision (ROD) regarding this material and conducting other activities. The primary security objectives of this program are to reduce major security risks and strengthen arms reduction and nonproliferation (NP). To help achieve these objectives, a safeguards and security (S&S) team consisting of participants from Sandia, Los Alamos, and Lawrence Livermore National Laboratories was established. The S&S activity for this program is a cross-cutting task which addresses all of the FMD program options. It includes both domestic and international safeguards and includes areas such as physical protection, nuclear materials accountability and material containment and surveillance. This paper will discuss the activities of the Fissile Materials Disposition Program (FMDP) S&S team as well as some specific S&S issues associated with various FMDP options/facilities. Some of the items to be discussed include the threat, S&S requirements, S&S criteria for assessing risk, S&S issues concerning fissile material processing/facilities, and international and domestic safeguards.

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

    SciTech Connect (OSTI)

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

    1987-09-01T23:59:59.000Z

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

  3. Final programmatic environmental impact statement for the uranium mill tailings remedial action ground water project. Volume II

    SciTech Connect (OSTI)

    none,

    1996-10-01T23:59:59.000Z

    Volume II of the programmatic environmental impact statement (PElS) is a comment and response document; it is the collection of the comments received on the draft PElS. The U.S. Department of Energy's (DOE) response to each comment is provided after each comment. If the comment resulted in a change to the PElS, the affected section number of the PElS is provided in the response. Comments 1 through 259 were received at public hearings. The name of the hearing at which the comment was received is listed after each comment. Comments were recorded on flip charts and by notetakers. DOE representatives were present to hear the comments and respond to them. The DOE's written response is provided after each comment. Comments 260 through 576 were received in writing at the hearings, and from various federal, tribal, and state agencies and from individuals during the public comment period. Copies of the written comments follow the comments and responses.

  4. Update to the Fissile Materials Disposition program SST/SGT transportation estimation

    SciTech Connect (OSTI)

    John Didlake

    1999-11-15T23:59:59.000Z

    This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

  5. Final programmatic environmental impact statement for the uranium mill tailings remedial action ground water project. Volume I

    SciTech Connect (OSTI)

    None

    1996-10-01T23:59:59.000Z

    This programmatic environmental impact statement (PElS) was prepared for the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project to comply with the National Environmental Policy Act (NEPA). This PElS provides an analysis of the potential impacts of the alternatives and ground water compliance strategies as well as potential cumulative impacts. On November 8, 1978, Congress enacted the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law, codified at 42 USC §7901 et seq. Congress found that uranium mill tailings " ... may pose a potential and significant radiation health hazard to the public, and that every reasonable effort should be made to provide for stabilization, disposal, and control in a safe, and environmentally sound manner of such tailings in order to prevent or minimize other environmental hazards from such tailings." Congress authorized the Secretary of Energy to designate inactive uranium processing sites for remedial action by the U.S. Department of Energy (DOE). Congress also directed the U.S. Environmental Protection Agency (EPA) to set the standards to be followed by the DOE for this process of stabilization, disposal, and control. On January 5, 1983, EPA published standards (40 CFR Part 192) for the disposal and cleanup of residual radioactive materials. On September 3, 1985, the U.S. Court of Appeals for the Tenth Circuit set aside and remanded to EPA the ground water provisions of the standards. The EPA proposed new standards to replace remanded sections and changed other sections of 40 CFR Part 192. These proposed standards were published in the Federal Register on September 24, 1987 (52 FR 36000). Section 108 of the UMTRCA requires that DOE comply with EPA's proposed standards in the absence of final standards. The Ground Water Project was planned under the proposed standards. On January 11, 1995, EPA published the final rule, with which the DOE must now comply. The PElS and the Ground Water Project are in accordance with the final standards. The EPA reserves the right to modify the ground water standards, if necessary, based on changes in EPA drinking water standards. Appendix A contains a copy of the 1983 EPA ground water compliance standards, the 1987 proposed changes to the standards, and the 1995 final rule. Under UMTRA, DOE is responsible for bringing the designated processing sites into compliance with the EPA ground water standards and complying with all other applicable standards and requirements. The U.S. Nuclear Regulatory Commission (NRC) must concur with DOE's actions. States are full participants in the process. The DOE also must consult with any affected Indian tribes and the Bureau of Indian Affairs. Uranium processing activities at most of the inactive mill sites resulted in the contamination of ground water beneath and, in some cases, downgradient of the sites. This contaminated ground water often has elevated levels of constituents such as but not limited to uranium and nitrates. The purpose of the UMTRA Ground Water Project is to eliminate or reduce to acceptable levels the potential health and environmental consequences of milling activities by meeting the EPA ground water standards.

  6. USDOE Innovative Clean Coal Technology Demonstration Project: Passamaquoddy Technology Recovery Scrubber{trademark}. Final report: Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    This Final Report provides available design, operational, and maintenance information, and marketing plans, on the Passamaquoddy Technology Recovery Scrubber{trademark} demonstration Project at the Dragon Products company`s cement plant at Thomaston, Maine. In addition, data on pollutant removal efficiencies and system economics are reviewed. The Recovery Scrubber was developed to simultaneously address the emission of acid gas pollutants and the disposal of alkaline solid waste at a cement plant. The process, however, has general application to other combustion processes including waste or fossil fuel fired boilers. Selected chemistry of the exhaust gas, (before and after treatment by the Recovery Scrubber), selected chemistry of the cement plant kiln baghouse dust catch (before and after treatment by the Recovery Scrubber), and Dragon cement plant economics are presented. current marketing efforts and potential markets for the Recovery Scrubber in several industries are discussed.

  7. LIFAC Demonstration at Richmond Power and Light Whitewater Valley Unit No. 2 Volume II: Project Performance and Economics

    SciTech Connect (OSTI)

    None

    1998-04-01T23:59:59.000Z

    The C1ean Coal Technology (CCT) Program has been recognized in the National Energy Strategy as a major initiative whereby coal will be able to reach its full potential as a source of energy for the nation and the international marketplace. Attainment of this goal depends upon the development of highly efficient, environmentally sound, competitive coal utilization technologies responsive to diverse energy markets and varied consumer needs. The CCT Program is an effort jointly funded by government and industry whereby the most promising of the advanced coal-based technologies are being moved into the marketplace through demonstration. The CCT Program is being implemented through a total of five competitive solicitations. LIFAC North America, a joint venture partnership of ICF Kaiser Engineers, Inc., and Tampella Power Corporation, is currently demonstrating the LIFAC flue gas desulfurization technology developed by Tampella Power. This technology provides sulfur dioxide emission control for power plants, especially existing facilities with tight space limitations. Sulfur dioxide emissions are expected to be reduced by up to 85% by using limestone as a sorbent. The LIFAC technology is being demonstrated at Whitewater Valley Unit No. 2, a 60-MW coal-fired power plant owned and operated by Richmond Power and Light (RP&L) and located in Richmond, Indiana. The Whitewater plant consumes high-sulfur coals, with sulfur contents ranging from 2.0-2.9 $ZO. The project, co-funded by LIFAC North America and DOE, is being conducted with the participation of Richmond Power and Light, the State of Indiana, the Electric Power Research Institute (EPRI), and the Black Beauty Coal Company. The project has a total cost of $21.4 million and a duration of 48 months from the preliminary design phase through the testing program.

  8. Site selection for the Salt Disposition Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Bowers, J.A.

    2000-01-03T23:59:59.000Z

    The purpose of this report is to identify, assess, and rank potential sites for the proposed Salt Disposition Facility (SDF) at the Savannah River Site.

  9. Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc

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

    1, 2012 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and...

  10. EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials

    Broader source: Energy.gov [DOE]

    The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition.

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

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-12-13T23:59:59.000Z

    The purpose of this study is to identify, assess, and rank potential sites for the proposed Surplus Plutonium Disposition Facilities complex at the Savannah River Site.

  12. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSHILICATE FRIT X COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-11-21T23:59:59.000Z

    The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is the preferred option for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium in the late 1990's. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Recent FY05 studies have further investigated the LaBS Frit B formulation as well as development of a newer LaBS formulation denoted as LaBS Frit X. The objectives of this present task were to fabricate plutonium loaded LaBS Frit X glass and perform corrosion testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit X composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was thoroughly characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL using quenched Pu Frit X glass with varying exposed surface areas. Effects of isothermal and can-in-canister heat treatments on the Pu Frit X glass were also investigated. Another series of PCTs were performed on these different heat-treated Pu Frit X glasses. Leachates from all these PCTs were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation. Characterization of the quenched Pu Frit X glass prior to testing revealed that some crystalline plutonium oxide was present in the glass. The crystalline particles had a disklike morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar results had also been observed in previous Pu Frit B studies. Isothermal 1250 C heat-treated Pu Frit X glasses showed two different crystalline phases (PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7}), as well as a peak shift in the XRD spectra that is likely due to a solid solution phase PuO{sub 2}-HfO{sub 2} formation. Micrographs of this glass showed a clustering of some of the crystalline phases. Pu Frit X glass subjected to the can-in-canister heating profile also displayed the two PuO{sub 2} and Nd{sub 2}Hf{sub 2}O{sub 7} phases from XRD analysis. Additional micrographs indicate crystalline phases in this glass were of varying forms (a spherical PuO{sub 2} phase that appeared to range in size from submicron to {approx}5 micron, a dendritic-type phase that was comprised of mixed lanthanides and plutonium, and a minor phase that contained Pu and Hf), and clustering of the phases was also observed.

  13. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT B COMPOSITION FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Marra, J

    2006-01-19T23:59:59.000Z

    The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Therefore, the objectives of this present task were to fabricate plutonium loaded LaBS Frit B glass and perform additional testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL) and for additional performance testing at Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). The glass was characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL with varying exposed surface area and test durations. The leachates from these tests were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation. The leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to identify the formation of alteration phases on the glass surface. Characterization of the glass prior to testing revealed that some undissolved plutonium oxide was present in the glass. The undissolved particles had a disk-like morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar disk-like PuO{sub 2} phases were observed in previous LaBS glass testing at PNNL. In that work, researchers concluded that plutonium formed with this morphology as a result of the leaching process. It was more likely that the presence of the plutonium oxide crystals in the PNNL testing was a result of glass fabrication. A series of PCTs were conducted at 90 C in ASTM Type 1 water. The PCT-Method A (PCT-A) was conducted to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT-A test has a strict protocol and is designed to specifically be used to evaluate whether the chemical durability and elemental release characteristics of a nuclear waste glass have been consistently controlled during production and, thus, meet the repository acceptance requirements. The PCT-A results on the Pu containing LaBS Frit B glass showed that the glass was very durable with a normalized elemental release value for boron of approximately 0.02 g/L. This boron release value was better than two orders of magnitude better from a boron release standpoint than the current Environmental Assessment (EA) glass used for repository acceptance. The boron release value for EA glass is 16.7 g/L.

  14. Guidelines for the verification and validation of expert system software and conventional software: Project summary. Volume 1

    SciTech Connect (OSTI)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A. [Science Applications International Corp., McLean, VA (United States)

    1995-03-01T23:59:59.000Z

    This eight-volume report presents guidelines for performing verification and validation (V&V) on Artificial Intelligence (Al) systems with nuclear applications. The guidelines have much broader application than just expert systems; they are also applicable to object-oriented programming systems, rule-based systems, frame-based systems, model-based systems, neural nets, genetic algorithms, and conventional software systems. This is because many of the components of AI systems are implemented in conventional procedural programming languages, so there is no real distinction. The report examines the state of the art in verifying and validating expert systems. V&V methods traditionally applied to conventional software systems are evaluated for their applicability to expert systems. One hundred fifty-three conventional techniques are identified and evaluated. These methods are found to be useful for at least some of the components of expert systems, frame-based systems, and object-oriented systems. A taxonomy of 52 defect types and their delectability by the 153 methods is presented. With specific regard to expert systems, conventional V&V methods were found to apply well to all the components of the expert system with the exception of the knowledge base. The knowledge base requires extension of the existing methods. Several innovative static verification and validation methods for expert systems have been identified and are described here, including a method for checking the knowledge base {open_quotes}semantics{close_quotes} and a method for generating validation scenarios. Evaluation of some of these methods was performed both analytically and experimentally. A V&V methodology for expert systems is presented based on three factors: (1) a system`s judged need for V&V (based in turn on its complexity and degree of required integrity); (2) the life-cycle phase; and (3) the system component being tested.

  15. Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

    1987-04-01T23:59:59.000Z

    The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

  16. River Protection Project Integrated safety management system phase II verification report, volumes I and II - 8/19/99

    SciTech Connect (OSTI)

    SHOOP, D.S.

    1999-09-10T23:59:59.000Z

    The Department of Energy policy (DOE P 450.4) is that safety is integrated into all aspects of the management and operations of its facilities. In simple and straightforward terms, the Department will ''Do work safely.'' The purpose of this River Protection Project (RPP) Integrated Safety Management System (ISMS) Phase II Verification was to determine whether ISMS programs and processes are implemented within RFP to accomplish the goal of ''Do work safely.'' The goal of an implemented ISMS is to have a single integrated system that includes Environment, Safety, and Health (ES&H) requirements in the work planning and execution processes to ensure the protection of the worker, public, environment, and federal property over the RPP life cycle. The ISMS is comprised of the (1) described functions, components, processes, and interfaces (system map or blueprint) and (2) personnel who are executing those assigned roles and responsibilities to manage and control the ISMS. Therefore, this review evaluated both the ''paper'' and ''people'' aspects of the ISMS to ensure that the system is implemented within RPP. Richland Operations Office (RL) conducted an ISMS Phase I Verification of the TWRS from September 28-October 9, 1998. The resulting verification report recommended that TWRS-RL and the contractor proceed with Phase II of ISMS verification given that the concerns identified from the Phase I verification review are incorporated into the Phase II implementation plan.

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

    SciTech Connect (OSTI)

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

    1995-08-01T23:59:59.000Z

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

  18. Salt Lake City Area Integrated Projects Electric Power Marketing. Draft environmental impact statement: Volume 2, Sections 1-16

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    The Salt Lake City Area Office of the Western Area Power Administration (Western) markets electricity produced at hydroelectric facilities operated by the Bureau of Reclamation. The facilities are known collectively as the Salt Lake City Area Integrated Projects (SLCA/IP) and include dams equipped for power generation on the Green, Gunnison, Rio Grande, and Colorado rivers and on Deer and Plateau creeks in the states of Wyoming, Utah, Colorado, Arizona, and New Mexico. Of these facilities, only the Glen Canyon Unit, the Flaming Gorge Unit, and the Aspinall Unit (which includes Blue Mesa, Morrow Point, and Crystal dams;) are influenced by Western power scheduling and transmission decisions. The EIS alternatives, called commitment-level alternatives, reflect combinations of capacity and energy that would feasibly and reasonably fulfill Westerns firm power marketing responsibilities, needs, and statutory obligations. The viability of these alternatives relates directly to the combination of generation capability of the SLCA/IP with energy purchases and interchange. The economic and natural resource assessments in this environmental impact statement (EIS) include an analysis of commitment-level alternatives. Impacts of the no-action alternative are also assessed. Supply options, which include combinations of electrical power purchases and hydropower operational scenarios reflecting different operations of the dams, are also assessed. The EIS evaluates the impacts of these scenarios relative to socioeconomics, air resources, water resources, ecological resources, cultural resources, land use, recreation, and visual resources.

  19. Salt Lake City Area Integrated Projects Electric Power Marketing. Draft environmental impact statement: Volume 3, Appendix A

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    The Salt Lake City Area Office of the Western Area Power Administration (Western) markets electricity produced at hydroelectric facilities operated by the Bureau of Reclamation. The facilities are known collectively as the Salt Lake City Area Integrated Projects (SLCA/IP) and include dams equipped for power generation on the Green, Gunnison, Rio Grande, and Colorado rivers and on Deer and Plateau creeks in the states of Wyoming, Utah, Colorado, Arizona, and New Mexico. Of these facilities, only the Glen Canyon Unit, the Flaming Gorge Unit, and the Aspinall Unit (which includes Blue Mesa, Morrow Point, and Crystal dams;) are influenced by Western power scheduling and transmission decisions. The EIS alternatives, called commitment-level alternatives, reflect combinations of capacity and energy that would feasibly and reasonably fulfill Westerns firm power marketing responsibilities, needs, and statutory obligations. The viability of these alternatives relates directly to the combination of generation capability of the SLCA/IP with energy purchases and interchange. The economic and natural resource assessments in this environmental impact statement (EIS) include an analysis of commitment-level alternatives. Impacts of the no-action alternative are also assessed. Supply options, which include combinations of electrical power purchases and hydropower operational scenarios reflecting different operations of the dams, are also assessed. The EIS evaluates the impacts of these scenarios relative to socioeconomics, air resources, water resources, ecological resources, cultural resources, land use, recreation, and visual resources.

  20. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from April 30, 1998 through June 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

  1. Petroleum supply annual 1996: Volume 1

    SciTech Connect (OSTI)

    NONE

    1997-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1996 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Capacity; each with final annual data. The summary statistics section show 16 years of data depicting the balance between supply, disposition and ending stocks for various commodities including crude oil, motor gasoline, distillate fuel oil, residual fuel oil, jet fuel propane/propylene, and liquefied petroleum gases. The detailed statistics section provide 1996 detailed statistics on supply and disposition, refinery operations, imports and exports, stocks, and transportation of crude oil and petroleum products. The refinery capacity contain listings of refineries and associated crude oil distillation and downstream capacities by State, as of January 1, 1997, as well as summaries of corporate refinery capacities and refinery storage capacities. In addition, refinery receipts of crude oil by method of transportation for 1996 are provided. Also included are fuels consumed at refineries, and lists of shutdowns, sales, reactivations, and mergers during 1995 and 1996. 16 figs., 59 tabs.

  2. History of the US weapons-usable plutonium disposition program leading to DOE`s record of decision

    SciTech Connect (OSTI)

    Spellman, D.J.; Thomas, J.F.; Bugos, R.G.

    1997-04-01T23:59:59.000Z

    This report highlights important events and studies concerning surplus weapons-usable plutonium disposition in the United States. Included are major events that led to the creation of the U.S. Department of Energy (DOE) Office of Fissile Materials Disposition in 1994 and to that DOE office issuing the January 1997 Record of Decision for the Storage and Disposition of Weapons-Useable Fissile Materials Final Programmatic Environmental Impact Statement. Emphasis has been given to reactor-based plutonium disposition alternatives.

  3. Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    1999-05-14T23:59:59.000Z

    On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested services. The procurement process included the environmental review specified in DOE's NEPA regulations in 10 CFR 1021.216. The six reactors selected are Catawba Nuclear Station Units 1 and 2 in South Carolina McGuire Nuclear Station Units 1 and 2 in North Carolina, and North Anna Power Station Units 1 and 2 in Virginia. The Supplement describes the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published.

  4. EIS-0240: Disposition of Surplus Highly Enriched Uranium

    Broader source: Energy.gov [DOE]

    The Department proposes to eliminate the proliferation threat of surplus highly enriched uranium (HEU) by blending it down to low enriched uranium (LEU), which is not weapons-usable. The EIS assesses the disposition of a nominal 200 metric tons of surplus HEU. The Preferred Alternative is, where practical, to blend the material for use as LEU and use overtime, in commercial nuclear reactor field to recover its economic value. Material that cannot be economically recovered would be blended to LEU for disposal as low-level radioactive waste.

  5. Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-09-29T23:59:59.000Z

    As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The disposition phase of a facility's life cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

  6. Disposition of plutonium as non-fertile fuel for water reactors

    SciTech Connect (OSTI)

    Chidester, K.; Eaton, S.L.; Ramsey, K.B.

    1998-11-01T23:59:59.000Z

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The original intent of this project was to investigate the possible use of a new fuel form as a means of dispositioning the declared surplus inventory of weapons-grade plutonium. The focus soon changed, however, to managing the larger and rapidly growing inventories of plutonium arising in commercial spent nuclear fuel through implementation of a new fuel form in existing nuclear reactors. LANL embarked on a parallel path effort to study fuel performance using advanced physics codes, while also demonstrating the ability to fabricate a new fuel form using standard processes in LANL's Plutonium Facility. An evolutionary fuel form was also examined which could provide enhanced performance over standard fuel forms, but which could be implemented in a much shorter time frame than a completely new fuel form. Recent efforts have focused on implementation of results into global energy models and development of follow-on funding to continue this research.

  7. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect (OSTI)

    Ann M. Beauchesne

    2000-01-01T23:59:59.000Z

    Through the National Governors Association (NGA) project ``Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from October 1, 1999 through January 31, 2000, under the NGA grant. The work accomplished by the NGA project team during the past three months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; convened and facilitated the October 6--8 NGA FFCA Task Force Meeting in Oak Ridge, Tennessee; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and the Department.

  8. INFORMATION: Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides

    SciTech Connect (OSTI)

    None

    2010-04-01T23:59:59.000Z

    The Administration and the Congress, through policy statements and passage of the American Recovery and Reinvestment Act of 2009 (Recovery Act), have signaled that they hope that proactive actions by agency Inspectors General will help ensure that Federal Recovery Act activities are transparent, effective and efficient. In that context, the purpose of this management alert is to share with you concerns that have been raised to the Office of Inspector General regarding the planned disposition of the Savannah River Site's (SRS) inventory of Depleted Uranium (DU) oxides. This inventory, generated as a by-product of the nuclear weapons production process and amounting to approximately 15,600 drums of DU oxides, has been stored at SRS for decades. A Department source we deem reliable and credible recently came to the Office of Inspector General expressing concern that imminent actions are planned that may not provide for the most cost effective disposition of these materials. During April 2009, the Department chose to use funds provided under the Recovery Act to accelerate final disposition of the SRS inventory of DU oxides. After coordination with State of Utah regulators, elected officials and the U.S. Nuclear Regulatory Commission, the Department initiated a campaign to ship the material to a facility operated by EnergySolutions in Clive, Utah. Although one shipment of a portion of the material has already been sent to the EnergySolutions facility, the majority of the product remains at SRS. As had been planned, both for the shipment already made and those planned in the near term, the EnergySolutions facility was to have been the final disposal location for the material. Recently, a member of Congress and various Utah State officials raised questions regarding the radioactive and other constituents present in the DU oxides to be disposed of at the Clive, Utah, facility. These concerns revolved around the characterization of the material and its acceptability under existing licensing criteria. As a consequence, the Governor of Utah met with Department officials to voice concerns regarding further shipments of the material and to seek return of the initial shipment of DU oxides to SRS. Utah's objections and the Department's agreement to accede to the State's demands effectively prohibit the transfer of the remaining material from South Carolina to Utah. In response, the Department evaluated its options and issued a draft decision paper on March 1, 2010, which outlined an alternative for temporary storage until the final disposition issue could be resolved. Under the terms of the proposed option, the remaining shipments from SRS are to be sent on an interim basis to a facility owned by Waste Control Specialists (WCS) in Andrews, Texas. Clearly, this choice carries with it a number of significant logistical burdens, including substantial additional costs for, among several items, repackaging at SRS, transportation to Texas, storage at the interim site, and, repackaging and transportation to the yet-to-be-determined final disposition point. The Department source expressed the concern that the proposal to store the material on an interim basis in Texas was inefficient and unnecessary, asserting: (1) that the materials could remain at SRS until a final disposition path is identified, and that this could be done safely, securely and cost effectively; and, (2) that the nature of the material was not subject to existing compliance agreements with the State of South Carolina, suggesting the viability of keeping the material in storage at SRS until a permanent disposal site is definitively established. We noted that, while the Department's decision paper referred to 'numerous project and programmatic factors that make it impractical to retain the remaining inventory at Savannah River,' it did not outline the specific issues involved nor did it provide any substantive economic or environmental analysis supporting the need for the planned interim storage action. The only apparent driver in this case was a Recovery Act-related goal esta

  9. Petroleum supply annual, 1997. Volume 2

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  10. Petroleum supply annual 1998: Volume 2

    SciTech Connect (OSTI)

    NONE

    1999-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. This second volume contains final statistics for each month of 1998, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  11. Petroleum supply annual 1994, Volume 2

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1994 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1994, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary.

  12. Petroleum supply annual 1996: Volume 2

    SciTech Connect (OSTI)

    NONE

    1997-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1996 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Capacity; each with final annual data. The second volume contains final statistics for each month of 1996, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  13. Petroleum supply annual 1995: Volume 2

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1995 through monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and selected Refinery Statistics each with final annual data. The second volume contains final statistics for each month of 1995, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary.

  14. A comparative assessment of the economics of plutonium disposition

    SciTech Connect (OSTI)

    Williams, K.A.; Miller, J.W.; Reid, R.L.

    1997-04-01T23:59:59.000Z

    The US Department of Energy office of Fissile Materials Disposition (DOE/MD) has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted by DOE/MD and its national laboratory contractors. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. A secondary intent of the paper is to discuss major technical and economic issues that impact cost and schedule. To evaluate the economics of these technologies on an equitable basis, a set of cost-estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

  15. Chemical Safety Vulnerability Working Group report. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site.

  16. An Overview of Project Planning for Hot-Isostatic Pressure Treatment of High-Level Waste Calcine for the Idaho Cleanup Project - 12289

    SciTech Connect (OSTI)

    Nenni, Joseph A.; Thompson, Theron J. [CH2M-WG Idaho, LLC, Idaho Cleanup Project, Idaho Falls, Idaho 83403 (United States)

    2012-07-01T23:59:59.000Z

    The Calcine Disposition Project is responsible for retrieval, treatment by hot-isostatic pressure, packaging, and disposal of highly radioactive calcine stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Laboratory Site in southeast Idaho. In the 2009 Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement the Department of Energy documented the selection of hot-isostatic pressure as the technology to treat the calcine. The Record of Decision specifies that the treatment results in a volume-reduced, monolithic waste form suitable for transport outside of Idaho by a target date of December 31, 2035. That target date is specified in the 1995 Idaho Settlement Agreement to treat and prepare the calcine for transport out of Idaho in exchange for allowing storage of Navy spent nuclear fuel at the INL Site. The project is completing the design of the calcine-treatment process and facility to comply with Record of Decision, Settlement Agreement, Idaho Department of Environmental Quality, and Department of Energy requirements. A systems engineering approach is being used to define the project mission and requirements, manage risks, and establish the safety basis for decision making in compliance with DOE O 413.3B, 'Program and Project Management for the Acquisition of Capital Assets'. The approach draws heavily on 'design-for-quality' tools to systematically add quality, predict design reliability, and manage variation in the earliest possible stages of design when it is most efficient. Use of these tools provides a standardized basis for interfacing systems to interact across system boundaries and promotes system integration on a facility-wide basis. A mass and energy model was developed to assist in the design of process equipment, determine material-flow parameters, and estimate process emissions. Data generated from failure modes and effects analysis and reliability, availability, maintainability, and inspectability analysis were incorporated into a time and motion model to validate and verify the capability to complete treatment of the calcine within the required schedule. The Calcine Disposition Project systems engineering approach, including use of industry-proven design-for-quality tools and quantitative assessment techniques, has strengthened the project's design capability to meet its intended mission in a safe, cost-effective, and timely manner. Use of these tools has been particularly helpful to the project in early design planning to manage variation; improve requirements and high-consequence risk management; and more effectively apply alternative, interface, failure mode, RAMI, and time and motion analyses at the earliest possible stages of design when their application is most efficient and cost effective. The project is using these tools to design and develop HIP treatment of highly radioactive calcine to produce a volume-reduced, monolithic waste form with immobilization of hazardous and radioactive constituents. (authors)

  17. GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE GLASS FOR PLUTONIUM DISPOSITION

    SciTech Connect (OSTI)

    Crawford, C; James Marra, J; Ned Bibler, N

    2007-02-12T23:59:59.000Z

    The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) in Aiken, SC, to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. The objectives of this present task were to fabricate plutonium-loaded lanthanide borosilicate (LaBS) Frit B glass and perform testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the proposed Federal Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support glass durability testing via the ASTM Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was characterized with X-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. This characterization revealed some crystalline PuO{sub 2} inclusions with disk-like morphology present in the as fabricated, quench-cooled glass. A series of PCTs was conducted at SRNL with varying exposed surface area and test durations. Filtered leachates from these tests were analyzed to determine the dissolved concentrations of key elements. The leachate solutions were also ultrafiltered to quantify colloid formation. Leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to investigate formation of alteration phases on the glass surface. A series of PCTs was conducted at 90 C in ASTM Type 1 water to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT (7-day static test with powdered glass) results on the Pu-containing LaBS Frit B glass at SA/V of {approx} 2000 m{sup -1} showed that the glass was very durable with an average normalized elemental release value for boron of 0.013 g/m{sup 2}. This boron release value is {approx} 640X lower than normalized boron release from current Environmental Assessment (EA) glass used for repository acceptance. The PCT-B (7, 14, 28 and 56-day, static test with powdered glass) normalized elemental releases were similar to the normalized elemental release values from PCT-A testing, indicating that the LaBS Frit B glass is very durable as measured by the PCT. Normalized plutonium releases were essentially the same within the analytical uncertainty of the ICP-MS methods used to quantify plutonium in the 0.45 {micro}m-filtered leachates and ultra-filtered leachates, indicating that colloidal plutonium species do not form under the PCT conditions used in this study.

  18. R&D plan for immobilization technologies: fissile materials disposition program. Revision 1.0

    SciTech Connect (OSTI)

    Shaw, H.F.; Armantrout, G.A.

    1996-09-01T23:59:59.000Z

    In the aftermath of the Cold War, the US and Russia have agreed to large reductions in nuclear weapons. To aid in the selection of long- term fissile material management options, the Department of Energy`s Fissile Materials Disposition Program (FMDP) is conducting studies of options for the storage and disposition of surplus plutonium (Pu). One set of alternatives for disposition involve immobilization. The immobilization alternatives provide for fixing surplus fissile materials in a host matrix in order to create a solid disposal form that is nuclear criticality-safe, proliferation-resistant and environmentally acceptable for long-term storage or disposal.

  19. Disposition of clorazepate in dogs after single- and multiple-dose oral administration

    E-Print Network [OSTI]

    Forrester, Sharon Dru

    1989-01-01T23:59:59.000Z

    to compare single-dose disposition values with multiple-dose disposition values. The paired t test was also used to compare body weight on day 0 with that on day 21. Analysis of variance with repeated measures was used to evaluate results of routine... on both sets of parameters, comparing single-dose with multiple-dose disposition. Hecause the values for Vd(ss)/F from trapezoidal analysis were not normally distributed, nonparametric statistical analysis (ie, Wilcoxon rank sum test) was used...

  20. An Evaluation of Single Phase Ceramic Formulations for Plutonium Disposition

    SciTech Connect (OSTI)

    Stennett, Martin C.; Hyatt, Neil C. [Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD (United Kingdom); Maddrell, Ewan R.; Scales, Charlie R. [Nexia Solutions Ltd., Sellafield, Seascale, CA20 1PG (United Kingdom); Livens, Francis R.; Gilbert, Matthew [Chemistry, University of Manchester, Oxford Road, Manchester, M13 9PL (United Kingdom)

    2007-07-01T23:59:59.000Z

    Ceramics are promising potential hosts for the immobilization of actinide containing wastes. Work has been reported in the literature on multiphase systems, such as SYNROC [1], and on single phase systems such as pyrochlores [2] and zirconia [3], but assessment of the different waste-forms by direct comparison of literature data is not always easy due to the different processing and fabrication routes employed. In this study a potential range of different ceramic systems were investigated for plutonium disposition using the same processing scheme. Durable actinide containing minerals exist in nature and provided excellent target phases for the titanate, zirconate, silicate and phosphate based formulations examined here [4]. The Ce solid solution limits for each particular substitution mechanism were established and the processing parameters required to produce high quality ceramic specimens were optimised. Importantly, this was achieved within the constraints of a generic processing route suitable for fabrication of Pu bearing samples. (authors)

  1. Analysis of disposition alternatives for radioactively contaminated scrap metal

    SciTech Connect (OSTI)

    Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

    1997-01-01T23:59:59.000Z

    Millions of tonnes of slightly radioactive, scrap iron and steel, stainless steel, and copper are likely to become available as nuclear and other facilities and equipment are withdrawn from service. Disposition of this material is an international policy issue under consideration currently. The major alternatives for managing this material are to either develop a regulatory process for decontamination and recycling that will safeguard human health or to dispose of the scrap and replace the metal stocks. To evaluate the alternatives, we estimate quantities of scrap arising from nuclear power plant decommissioning, evaluate potential price impacts of recycling on regional markets, and assess the health and environmental impacts of the management alternatives. We conclude that decontaminating and recycling the scrap is the superior alternative.

  2. Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues

    SciTech Connect (OSTI)

    Greene, S.R.

    1999-07-17T23:59:59.000Z

    The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track approach to rendering approximately 50 metric tons of plutonium inaccessible for use in nuclear weapons. One track involves immobilizing the plutonium by combining it with high-level radioactive waste in glass or ceramic ''logs''. The other method, referred to as reactor-based disposition, converts plutonium into mixed oxide (MOX) fuel for nuclear reactors. The U.S. and Russia are moving ahead rapidly to develop and demonstrate the technology required to implement the MOX option in their respective countries. U.S. MOX fuel research and development activities were started in the 1950s, with irradiation of MOX fuel rods in commercial light water reactors (LWR) from the 1960s--1980s. In all, a few thousand MOX fuel rods were successfully irradiated. Though much of this work was performed with weapons-grade or ''near'' weapons-grade plutonium--and favorable fuel performance was observed--the applicability of this data for licensing and use of weapons-grade MOX fuel manufactured with modern fuel fabrication processes is somewhat limited. The U.S. and Russia are currently engaged in an intensive research, development, and demonstration program to support implementation of the MOX option in our two countries. This paper focuses on work performed in the U.S. and provides a brief summary of joint U.S./Russian work currently underway.

  3. Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2005-06-30T23:59:59.000Z

    In October 2002, DOE issued the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (Final EIS) (DOE 2002) that provided an analysis of the potential environmental consequences of alternatives/options for the management and disposition of Sodium Bearing Waste (SBW), High-Level Waste (HL W) calcine, and HLW facilities at the Idaho Nuclear Technology and Engineering Center (INTEC) located at the Idaho National Engineering and Environmental Laboratory (INEEL), now known as the Idaho National Laboratory (INL) and referred to hereafter as the Idaho Site. Subsequent to the issuance of the Final EIS, DOE included the requirement for treatment of SBW in the Request for Proposals for Environmental Management activities on the Idaho Site. The new Idaho Cleanup Project (ICP) Contractor identified Steam Reforming as their proposed method to treat SBW; a method analyzed in the Final EIS as an option to treat SBW. The proposed Steam Reforming process for SBW is the same as in the Final EIS for retrieval, treatment process, waste form and transportation for disposal. In addition, DOE has updated the characterization data for both the HLW Calcine (BBWI 2005a) and SBW (BBWI 2004 and BBWI 2005b) and identified two areas where new calculation methods are being used to determine health and safety impacts. Because of those changes, DOE has prepared this supplement analysis to determine whether there are ''substantial changes in the proposed action that are relevant to environmental concerns'' or ''significant new circumstances or information'' within the meaning of the Council of Environmental Quality and DOE National Environmental Policy Act (NEPA) Regulations (40 CFR 1502.9 (c) and 10 CFR 1021.314) that would require preparation of a Supplemental EIS. Specifically, this analysis is intended to determine if: (1) the Steam Reforming Option identified in the Final EIS adequately bounds impacts from the Steam Reforming Process proposed by the new ICP Contractor using the new characterization data, (2) the new characterization data is significantly different than the data presented in the Final EIS, (3) the new calculation methods present a significant change to the impacts described in the Final EIS, and (4) would the updated characterization data cause significant changes in the environmental impacts for the action alternatives/options presented in the Final EIS. There are no other aspects of the Final EIS that require additional review because DOE has not identified any additional new significant circumstances or information that would warrant such a review.

  4. Environmental behavior of hafnium : the impact on the disposition of weapons-grade plutonium

    E-Print Network [OSTI]

    Cerefice, Gary Steven

    1999-01-01T23:59:59.000Z

    Experimental and analytical studies were performed to examine the environmental behavior of hafnium and its utility as a neutron poison for the disposition of weapons-grade plutonium in Yucca Mountain. The hydrolysis of ...

  5. Enabling completion of the material disposition area G closure at the Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Blankenhorn, James Allen [Los Alamos National Laboratory; Bishop, Milton L [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    Los Alamos National Security, LLC (LANS) and the Los Alamos Site Office (LASO) have developed and are implementing an integrated strategy to accelerate the disposition of Los Alamos National Laboratory (LANL) legacy transuranic waste inventory currently stored in Technical Area 54, Material Disposition Area (MDA) G. As that strategy has been implemented the easier waste streams have been certified and shipped leaving the harder more challenging wastes to be dispositioned. Lessons learned from around the complex and a partnership with the National Transuranic Program located in Carlsbad, New Mexico, are enabling this acceleration. The Waste Disposition Program is responsible for the removal of both the above ground and below grade, retrievably stored transuranic waste in time to support the negotiated consent order with the State of New Mexico which requires closure of MDA G by the year 2015. The solutions and strategy employed at LANL are applicable to any organization that is currently managing legacy transuranic waste.

  6. EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This Supplemental EIS (SEIS) analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives.

  7. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for January 1 to March 31, 1988: Volume 9: Appendix C

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    The appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the first quarter of calendar year 1988 (January through March). The data in this volume of Appendix C cover the following wells: 199-N-58; 199-N-59; 199-N-60; 199-N-61; 199-N-67. The data are presented in the following order: Well Completion Report/Title III Inspection List, As-Built Diagram, Logging Charts, and Drill Logs.

  8. Final environmental impact statement/report. Volume 2. Technical studies. Northeast corridor improvement project electrification: New Haven, CT to Boston, MA

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This document is the final environmental impact statement and final environmental impact report (FEIS/R) on the proposal by the National Railroad Passenger Corporation (Amtrak) to complete the electrification of the Northeast Corridor main line by extending electric traction from New Haven, CT, to Boston, MA. This document (Volume II) presents additional technical studies to supplement Volume III of the DEIS/R issued in October 1993 (PB94-111838).

  9. IceCube Project Monthly Report -April 2010 Accomplishments

    E-Print Network [OSTI]

    Saffman, Mark

    Water Drill equipment (http://www.icecube.wisc.edu/disposition/index.php) and the site was circulated to solicit interest in the equipment following the end of IceCube construction. · The training at shorter distances. #12; 2 Cost and Schedule Performance ­ The project is 94.7% complete

  10. Northeast Corridor improvement project draft environmental impact statement/report for electrification of Northwest Corridor, New Haven, CT. to Boston, MA. Volume 3. Technical appendices. Final report, September 1992-September 1993

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The impacts of extending electrification on the National Railroad Passenger Corporation's (Amtrak) Northeast Corridor (NEC) from New Haven, Connecticut to Boston, Massachusetts are of direct concern to the Federal Railroad Administration (FRA). To improve rail service and increase ridership between New York and Boston, Amtrak proposes the electrification of the NEC main line between New Haven, CT and Boston, MA using an overhead 2 x 25,000 volt - 60 hertz power system. The volume Number III contains the detailed technical studies that were performed in order to identify and evaluate the environmental impacts of the proposed project. Some of these studies have been included entirely in the Draft Environmental Impact Statements-draft (DEIS/R) (Volume 1). The technical evaluations performed were based upon regulatory requirements as well as substantive issues raised by individuals and public agencies as part of the public participation program.

  11. Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee. Volume 1: Results of Field Sampling Program

    SciTech Connect (OSTI)

    Watkins, D.R.; Ammons, J.T.; Branson, J.L. [and others

    1993-10-01T23:59:59.000Z

    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.

  12. Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective

    SciTech Connect (OSTI)

    B.J. Orchard; L.A. Harvego; T.L. Carlson; R.P. Grant

    2009-03-01T23:59:59.000Z

    The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nation’s expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answers to national infrastructure needs. As a result of the Laboratory’s NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INL’s contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INL’s TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.

  13. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 5, Appendix B

    SciTech Connect (OSTI)

    none,

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W6-2; 299-W7-1; 299-W7-2; 299-W7-3; 299-W7-4. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  14. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 7, Appendix B (contd)

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wwlls completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W10-14; 299-W15-15; 299-W15-16; 299-W15-17; 299-W15-18. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  15. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 2, Appendix A

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix A cover the following wells: 299-E27-8; 299-E27-9; 299-E27-10; 299-E28-26; 299-E28-27. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  16. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 8, Appendix B (contd)

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W18-21; 299-W18-22; 299-W18-23; 299-W18-24. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  17. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 4, Appendix A (contd)

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix A cover the following wells: 299-E33-30; 299-E34-2; 299-E34-3; 299-E34-4; 299-E34-5; 299-E34-6. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  18. Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period, January 1-March 31, 1988: Volume 6, Appendix B (contd)

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W7-5; 299-W7-6; 299-W8-1; 299-W9-1; 299-W10-13. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

  19. Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium

    SciTech Connect (OSTI)

    Gillas, D. L.; Chambers, B. K.

    2002-02-26T23:59:59.000Z

    Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

  20. Effects of Time, Heat, and Oxygen on K Basin Sludge Agglomeration, Strength, and Solids Volume

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Daniel, Richard C.; Burns, Carolyn A.

    2011-01-04T23:59:59.000Z

    Sludge disposition will be managed in two phases under the K Basin Sludge Treatment Project. The first phase is to retrieve the sludge that currently resides in engineered containers in the K West (KW) Basin pool at ~10 to 18°C. The second phase is to retrieve the sludge from interim storage in the sludge transport and storage containers (STSCs) and treat and package it in preparation for eventual shipment to the Waste Isolation Pilot Plant. The work described in this report was conducted to gain insight into how sludge may change during long-term containerized storage in the STSCs. To accelerate potential physical and chemical changes, the tests were performed at temperatures and oxygen partial pressures significantly greater than those expected in the T Plant canyon cells where the STSCs will be stored. Tests were conducted to determine the effects of 50°C oxygenated water exposure on settled quiescent uraninite (UO2) slurry and a full simulant of KW containerized sludge to determine the effects of oxygen and heat on the composition and mechanical properties of sludge. Shear-strength measurements by vane rheometry also were conducted for UO2 slurry, mixtures of UO2 and metaschoepite (UO3•2H2O), and for simulated KW containerized sludge. The results from these tests and related previous tests are compared to determine whether the settled solids in the K Basin sludge materials change in volume because of oxidation of UO2 by dissolved atmospheric oxygen to form metaschoepite. The test results also are compared to determine if heating or other factors alter sludge volumes and to determine the effects of sludge composition and settling times on sludge shear strength. It has been estimated that the sludge volume will increase with time because of a uranium metal ? uraninite ? metaschoepite oxidation sequence. This increase could increase the number of containers required for storage and increase overall costs of sludge management activities. However, the volume might decrease because of decreases in the water-volume fraction caused by sludge solid reactions, compaction, or intergrowth and recrystallization of metaschoepite. In that case, fewer STSCs may be needed, but the shear strength would increase, and this could challenge recovery by water jet erosion and require more aggressive retrieval methods. Overall, the tests described herein indicate that the settled solids volume remains the same or decreases with time. The only case for which the sludge solids volumes increase with time is for the expansion factor attendant upon the anoxic corrosion of uranium metal to produce UO2 and subsequent reaction with oxygen to form equimolar UO2.25 and UO3•2H2O.

  1. Final environmental impact statement/report. Volume 4. Comment letters and public hearing transcripts. Northeast corridor improvement project electrication: New Haven, CT to Boston, MA

    SciTech Connect (OSTI)

    NONE

    1994-10-01T23:59:59.000Z

    This document is the final environmental impact statement and final environmental impact report (FEIS/R) on the proposal by the National Railroad Passenger Corporation (Amtrak) to complete the electrification of the Northeast Corridor main line by extending electric traction from New Haven, CT, to Boston, MA. This document (Volume IV) reprints the comments received on the DEIS/R.

  2. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  3. DEVELOPMENT OF GLASS AND CRYSTALLINE CERAMIC FORMS FOR DISPOSITION OF EXCESS PLUTONIUM

    SciTech Connect (OSTI)

    Marra, James; Cozzi, A; Crawford, C.; Herman, C.; Marra, John; Peeler, D.

    2009-09-10T23:59:59.000Z

    In the aftermath of the Cold War, the United States Department of Energy (DOE) has identified up to 50 metric tons of excess plutonium that needs to be dispositioned. The bulk of the material is slated to be blended with uranium and fabricated into a Mixed Oxide (MOX) fuel for subsequent burning in commercial nuclear reactors. Excess plutonium-containing impurity materials making it unsuitable for fabrication into MOX fuel will need to be dispositioned via other means. Glass and crystalline ceramics have been developed and studied as candidate forms to immobilize these impure plutonium feeds. A titanate-based ceramic was identified as an excellent actinide material host. This composition was based on Synroc compositions previously developed for nuclear waste immobilization. These titanate ceramics were found to be able to accommodate extremely high quantities of fissile material and exhibit excellent aqueous durability. A lanthanide borosilicate (LaBS) glass was developed to accommodate high concentrations of plutonium and to be very tolerant of impurities yet still maintain good aqueous durability. Recent testing of alkali borosilicate compositions showed promise of using these compositions to disposition lower concentrations of plutonium using existing high level waste vitrification processes. The developed waste forms all appear to be suitable for Pu disposition. Depending on the actual types and concentrations of the Pu residue streams slated for disposition, each waste form offers unique advantages.

  4. Integrated development and testing plan for the plutonium immobilization project

    SciTech Connect (OSTI)

    Kan, T.

    1998-07-01T23:59:59.000Z

    This integrated plan for the DOE Office of Fissile Materials Disposition (MD) describes the technology development and major project activities necessary to support the deployment of the immobilization approach for disposition of surplus weapons-usable plutonium. The plan describes details of the development and testing (D&T) tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology (''Immobilization Fissile Material Disposition Program Final Immobilization Form Assessment and Recommendation'', UCRL-ID-128705, October 3, 1997). The plan also presents tasks for characterization and performance testing of the immobilization form to support a repository licensing application and to develop the basis for repository acceptance of the plutonium form. Essential elements of the plant project (design, construction, facility activation, etc.) are described, but not developed in detail, to indicate how the D&T results tie into the overall plant project. Given the importance of repository acceptance, specific activities to be conducted by the Office of Civilian Radioactive Waste Management (RW) to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization D&T activities provide input to the license activity. The ultimate goal of the Immobilization Project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes (MT) of U.S. surplus weapons usable plutonium materials in a manner that meets the ''spent fuel'' standard (Fissile Materials Storage and Disposition Programmatic Environmental Impact Statement Record of Decision, ''Storage and Disposition Final PEIS'', issued January 14, 1997, 62 Federal Register 3014) and is acceptable for disposal in a geologic repository. In the can-in-canister technology, this is accomplished by encapsulating the plutonium-containing ceramic forms within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2006 and be completed within 10 years.

  5. Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program

    SciTech Connect (OSTI)

    Wijesinghe, A.M.

    1996-08-23T23:59:59.000Z

    This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

  6. Independent Verification and Validation Of SAPHIRE 8 Volume 3 Users' Guide Project Number: N6423 U.S. Nuclear Regulatory Commission

    SciTech Connect (OSTI)

    Kent Norris

    2010-03-01T23:59:59.000Z

    The purpose of the Independent Verification and Validation (IV&V) role in the evaluation of the SAPHIRE 8 Volume 3 Users’ Guide is to assess the user documentation for its completeness, correctness, and consistency with respect to requirements for user interface and for any functionality that can be invoked by the user. The IV&V team began this endeavor after the software engineering and software development of SAPHIRE had already been in production.

  7. Ground-water monitoring compliance projects for Hanford Site facilities: Volume 2, Appendices A and B: Progress report, January 1, 1987 to March 31, 1987

    SciTech Connect (OSTI)

    Not Available

    1987-05-01T23:59:59.000Z

    This report convers recent progress on ground-water monitoring programs for four Hanford Site facilities: the 300 Area Process Trenches, the 183-H Solar Evaporation Basins, the 200 Area Low-Level Burial Grounds, and the Nonradioactive Dangerous Waste Landfill. The time period covered by this covered by this report is January 1 to March 31, 1987. Volume 2 contains Appendices A and B.

  8. Final environmental impact statement/report and 4(f) statement. Volume 1. Northeast corridor improvement project electrification: New Haven, CT to Boston, MA. Final report

    SciTech Connect (OSTI)

    NONE

    1994-10-31T23:59:59.000Z

    This document is the final environmental impact statement and final environmental impact report (FEIS/R) on the proposal by the National Railroad Passenger Corporation (Amtrak) to complete the electrification of the Northeast Corridor main line by extending electric traction from New Haven, CT, to Boston, MA. This document (Volume I) is the main body of the FEIS/R and includes a 4(f) Statement on the proposed location of an electrification facility in the Great Swamp Wildlife Management Area.

  9. EM Makes Significant Progress on Dispositioning Transuranic Waste...

    Office of Environmental Management (EM)

    Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed...

  10. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    Columbia University

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on Municipal Solid Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein of solid wastes and advance sustainable waste management in the U.S. to the level of several leading

  11. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

    SciTech Connect (OSTI)

    Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

    2013-07-01T23:59:59.000Z

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  12. Electric power annual 1994. Volume 2, Operational and financial data

    SciTech Connect (OSTI)

    NONE

    1995-11-28T23:59:59.000Z

    This year, the annual is published in two volumes. Volume I focused on US electric utilities and contained final 1994 data on net generation, fossil fuel consumption, stocks, receipts, and cost. This Volume II presents annual 1994 summary statistics for the electric power industry, including information on both electric utilities and nonutility power producers. Included are preliminary data for electric utility retail sales of electricity, associated revenue, and average revenue per kilowatthour of electricity sold (based on form EIA-861) and for electric utility financial statistics, environmental statistics, power transactions, and demand- side management. Final 1994 data for US nonutility power producers on installed capacity and gross generation, as well as supply and disposition information, are also provided in Volume II. Technical notes and a glossary are included.

  13. Fuel qualification issues and strategies for reactor-based surplus plutonium disposition

    SciTech Connect (OSTI)

    Cowell, B.S.; Copeland, G.L.; Moses, D.L.

    1997-08-01T23:59:59.000Z

    The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based MOX fuels for use in domestic commercial light-water reactors (LWRs).

  14. Results From The Salt Disposition Project Next Generation Solvent Demonstration Plan

    SciTech Connect (OSTI)

    Peters, T. B.; Fondeur, F. F.; Taylor-Pashow, K. M.L.

    2014-04-02T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Solvent Hold Tank (SHT) samples were taken throughout the Next Generation Solvent (NGS) Demonstration Plan. These samples were analyzed and the results are reported. SHT: The solvent behaved as expected, with no bulk changes in the composition over time, with the exception of the TOA and TiDG. The TiDG depletion is higher than expected, and consideration must be taken on the required rate of replenishment. Monthly sampling of the SHT is warranted. If possible, additional SHT samples for TiDG analysis (only) would help SRNL refine the TiDG degradation model. CWT: The CWT samples show the expected behavior in terms of bulk chemistry. The 137Cs deposited into the CWT varies somewhat, but generally appears to be lower than during operations with the BOBCalix solvent. While a few minor organic components were noted to be present in the Preliminary sample, at this time these are thought to be artifacts of the sample preparation or may be due to the preceding solvent superwash. DSSHT: The DSSHT samples show the predicted bulk chemistry, although they point towards significant dilution at the front end of the Demonstration. The 137Cs levels in the DSSHT are much lower than during the BOBCalix operations, which is the expected observation. SEHT: The SEHT samples represent the most different output of all four of the outputs from MCU. While the bulk chemistry is as expected, something is causing the pH of the SEHT to be higher than what would be predicted from a pure stream of 0.01 M boric acid. There are several possible different reasons for this, and SRNL is in the process of investigating. Other than the pH issue, the SEHT is as predicted. In summary, the NGS Demonstration Plan samples indicate that the MCU system, with the Blend Solvent, is operating as expected. The only issue of concern regards the pH of the SEHT, and SRNL is in the process of investigating this. SRNL results support the transition to routine operations.

  15. ISMS/EMS Lessons Learned Disposition Projects at SRS | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaefer To:Department ofOralGovernment Vehicle UtilizationDepartment ofISAAugust

  16. Facilities Infrastructure & Services Unneeded Materials and Chemicals Disposition Project (4579)

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8,Dist. Category UC-lFederalFY 2008 FOIAFabricatedJuanTim

  17. Summary - Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the Passing of AdmiraltheOil and Less

  18. High-solids black liquor firing in pulp and paper industry kraft recovery boilers: Phase 1 -- Final report. Volume 2: Project technical results

    SciTech Connect (OSTI)

    Southards, W.T.; Clement, J.L.; McIlroy, R.A.; Tharp, M.R.; Verrill, C.L.; Wessell, R.A.

    1995-11-01T23:59:59.000Z

    This project is a multiple-phase effort to develop technologies to improve high-solids black liquor firing in pulp mill recovery boilers. The principal means to this end is to construct and operate a pilot-scale recovery furnace simulator (RFS) in which these technologies can be tested. The Phase 1 objectives are to prepare a preliminary design for the RFS, delineate a project concept for evaluating candidate technologies, establish industrial partners, and report the results. Phase 1 addressed the objectives with seven tasks: Develop a preliminary design of the RFS; estimate the detailed design and construction costs of the RFS and the balance of the project; identify interested parties in the paper industry and key suppliers; plan the Phase 2 and Phase 3 tests to characterize the RFS; evaluate the economic justification for high-solids firing deployment in the industry; evaluate high-solids black liquor property data to support the RFS design; manage the project and reporting results, which included planning the future program direction.

  19. Spent Fuel Working Group Report. Volume 1

    SciTech Connect (OSTI)

    O`Toole, T.

    1993-11-01T23:59:59.000Z

    The Department of Energy is storing large amounts of spent nuclear fuel and other reactor irradiated nuclear materials (herein referred to as RINM). In the past, the Department reprocessed RINM to recover plutonium, tritium, and other isotopes. However, the Department has ceased or is phasing out reprocessing operations. As a consequence, Department facilities designed, constructed, and operated to store RINM for relatively short periods of time now store RINM, pending decisions on the disposition of these materials. The extended use of the facilities, combined with their known degradation and that of their stored materials, has led to uncertainties about safety. To ensure that extended storage is safe (i.e., that protection exists for workers, the public, and the environment), the conditions of these storage facilities had to be assessed. The compelling need for such an assessment led to the Secretary`s initiative on spent fuel, which is the subject of this report. This report comprises three volumes: Volume I; Summary Results of the Spent Fuel Working Group Evaluation; Volume II, Working Group Assessment Team Reports and Protocol; Volume III; Operating Contractor Site Team Reports. This volume presents the overall results of the Working Group`s Evaluation. The group assessed 66 facilities spread across 11 sites. It identified: (1) facilities that should be considered for priority attention. (2) programmatic issues to be considered in decision making about interim storage plans and (3) specific vulnerabilities for some of these facilities.

  20. EA-1239: Disposition of Mound Plant's South Property, Miamisburg, Ohio

    Broader source: Energy.gov [DOE]

    DOE prepared an EA for the proposed title transfer of 123 acres of land referred to as the “South Property” at the Miamisburg Environmental Management Project Mound Plant in Miamisburg, Ohio.

  1. Now Available: Pacific Northwest Smart Grid Demonstration Project...

    Energy Savers [EERE]

    Now Available: Pacific Northwest Smart Grid Demonstration Project - Technology Performance Report Volume 1 Now Available: Pacific Northwest Smart Grid Demonstration Project -...

  2. Ground-water monitoring compliance projects for Hanford Site facilities: Progress report for the period January 1--March 31, 1988: Volume 1, Text

    SciTech Connect (OSTI)

    Not Available

    1988-05-01T23:59:59.000Z

    This report describes the progress of eight Hanford Site ground-water monitoring projects for the period January 1 to March 31, 1988. The facilities represented by the eight projects are the 300 Area Process trenches, 183-H Solar Evaporation Basins, 200 Areas Low-Level Burial Grounds, Nonradioactive Dangerous Waste Landfill, 216-A-36B Crib, 1301-N Liquid Waste Disposal Facility, 1325-N Liquid Waste Disposal Facility, and 1324-N/NA Surface Impoundment and Percolation Ponds. The latter four projects are included in this series of quarterly reports for the first time. This report is the seventh in a series of periodic status reports; the first six cover the period from May 1, 1986, through December 31, 1987 (PNL 1986; 1987a, b, c, d; 1988a). This report satisfies the requirements of Section 17B(3) of the Consent Agreement and Compliance Order issued by the Washington State Department of Ecology (1986a) to the US Department of Energy-Richland Operations Office. 13 refs., 19 figs., 24 tabs.

  3. EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO

    Broader source: Energy.gov [DOE]

    NNSA/DOE announces its intent to prepare an EIS for the disposition of the Bannister Federal Complex, Kansas City, MO. NNSA previously decided in a separate NEPA review (EA-1592) to relocate its operations from the Bannister Federal Complex to a newly constructed industrial campus eight miles from the current location.

  4. HLW Salt Disposition Alternatives Identification Preconceptual Phase I Summary Report (Including Attachments)

    SciTech Connect (OSTI)

    Piccolo, S.F.

    1999-07-09T23:59:59.000Z

    The purpose of this report is to summarize the process used by the Team to systematically develop alternative methods or technologies for final disposition of HLW salt. Additionally, this report summarizes the process utilized to reduce the total list of identified alternatives to an ''initial list'' for further evaluation. This report constitutes completion of the team charter major milestone Phase I Deliverable.

  5. IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION

    SciTech Connect (OSTI)

    Allender, J; Moore, E

    2010-07-14T23:59:59.000Z

    This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

  6. Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)

    SciTech Connect (OSTI)

    NONE

    1994-04-30T23:59:59.000Z

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

  7. LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

  8. Final Demolition and Disposition of 209-E Critical Mass Laboratory - 12267

    SciTech Connect (OSTI)

    Woolery, Wade [US Department of Energy, Richland WA (United States); Dodd, Edwin III [CH2M Hill Plateau Remediation Company, Richland WA (United States)

    2012-07-01T23:59:59.000Z

    The 209-E Critical Mass Laboratory was constructed in 1960 to provide a heavy shielded reactor room where quantities of plutonium or uranium in solution could be brought to near-critical configurations under carefully controlled and monitored conditions. In the late 1980's, the responsible contractor, Pacific Northwest National Laboratory (PNNL), was directed by the Department of Energy (DOE) to prepare the facility for unoccupied status. The facility was demolished under a Removal Action Work Plan pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The funding for this project was provided by the American Recovery and Reinvestment Act (ARRA). The primary rooms of concern with regards to contamination in 209-E facility, which is over 9,000 square feet, are the criticality assembly room (CAR), the mix room, and the change room. The CAR contained two reactor hoods (HO-140 and HO-170), which each had a high efficiency particulate air (HEPA) filter system. The CAR contained 13 tanks ranging from 38 L (10 gal) to 401 L (106 gal). Tanks TK-109 and TK-110 are below grade, and were removed as part of this demolition and disposition remedy. Nonradiological and radiological hazardous substances were removed, decontaminated, or fixed in place, prior to demolition. Except for the removal of below grade tanks TK-109 and TK-110, the facility was demolished to slab-on-grade. PNNL performed stabilization and deactivation activities that included removal of bulk fissile material and chemicals, flushing tanks, stabilizing contamination within gloveboxes and hoods, and packaging and removing waste. The removal of the contaminated plutonium equipment and materials from the 209E facility presented a number of challenges similar in nature to those associated with the inventory reduction and cleanup activities at the Plutonium Finishing Plant. Although there were no bulk fissile materials or chemicals within the facility, there were residual radiological materials (isotopes of plutonium and americium) in the tanks and hoods. The complexity of the remedy was present because of the various configurations of the tanks and hoods, combined with the residual contaminants. Because of the weight and dimensional configuration, size reduction of the slab tanks, as well as removal and disposal of the different material used for moderation and absorption, were two examples of challenges that were resolved to complete the remedy. One of the key methods developed and implemented at the facility was the design and construction of a shroud to allow the cutting of the Pu contaminated tanks. The shroud design, development and implementation at the 209E Project was an example of enhanced work planning and task hazards analysis with worker involvement. This paper will present the lessons learned from the 209E facility inventory reduction activities including the shroud and other methodologies used. The initial Lessons Learned discussion for this project was scheduled for late January 2012. This facility is the first open-air demolition of a highly contaminated plutonium-contaminated facility accomplished by CH2M Hill under the Plateau Remediation Contract. The demolition was completed without spread of contamination to the workers and the surrounding area. As with any project of this complexity, there are significant accomplishments, as well as experience that can be applied to future demolition of plutonium-contaminated facilities on the Hanford Site. These experiences will be documented at a later date. (authors)

  9. Used fuel disposition campaign international activities implementation plan.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2011-06-29T23:59:59.000Z

    The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

  10. DOE Signs Notice to Prepare Environmental Assessment on Proposed Project with Germany

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – The Energy Department recently signed a notice of intent to prepare an environmental assessment to analyze the potential environmental impacts from a proposed project to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition.

  11. Rendering Implicit Flow Volumes Daqing Xue, Caixia Zhang, Roger Crawfis*

    E-Print Network [OSTI]

    Crawfis, Roger

    Rendering Implicit Flow Volumes Daqing Xue, Caixia Zhang, Roger Crawfis* Department of Computer and then rendered using an unstructured volume rendering technique. Unless a detailed refinement of the flow volume-dimensional texture mapping and an interval volume segmentation coupled with a tetrahedron projection-based renderer

  12. Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1

    SciTech Connect (OSTI)

    Cartmell, D.B.

    1995-09-01T23:59:59.000Z

    Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ``Draft`` Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ``Draft`` MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million.

  13. Viability Assessment Volume 5

    SciTech Connect (OSTI)

    DOE,

    1998-12-01T23:59:59.000Z

    This volume presents a management summary of the cost estimate to complete the design, and to license, construct, operate, monitor, close, and decommission a Monitored Geologic Repository at Yucca Mountain in Nevada. This volume summarizes the scope, estimating methodologies, and assumptions used in development of the Monitored Geologic Repository-VA cost estimate. It identifies the key features necessary to understand the summary costs presented herein. This cost summary derives from a larger body of documented cost analysis. Volume 5 is organized to reflect this structured approach to cost estimation and contains the following sections: Section 1, Cost Elements. This section briefly defines the components of each major repository cost element. Section 2, Project Phases. This section presents the definition, as used in the estimate, of five project phases (Licensing, Pre-emplacement Construction, Emplacement Operations, Monitoring, and Closure and Decommissioning) and the schedule dates for each phase. It also contains major milestone dates and a bar chart schedule. Section 3, Major Assumptions. This section identifies key high-level assumptions for the cost estimate basis. Additional detailed assumptions are included in the appendices. Section 4, Integrated Cost Summary. This section presents a high-level roll-up of the VA costs resulting from the estimating work. The tables and figures contained in this section were compiled from the more detailed cost estimates in the appendices. Section 5, References. This section identifies the references that support this cost volume. Appendices. For each major repository cost element, Appendices B-F [B, C, D, E, F] presents additional information on the scope of cost elements, identifies methodologies used to develop the cost estimates, lists underlying cost assumptions, and tabulates summary results. Appendix A contains a glossary to assist the reader in understanding the terminology in Volume 5. Appendix G presents costs associated with three VA design options, as described in Volume 2. These costs are provided for information and are not compiled into the integrated cost summary.

  14. [The Waste Package Project. Final report, July 1, 1995--February 27, 1996]: Volume 2, Experimental verification of structural response of a flexible three-link hydraulic steel robot

    SciTech Connect (OSTI)

    Ladkany, S.G.; Channarayapatna, S.S.

    1996-06-01T23:59:59.000Z

    This report presents experimental techniques for determining the static and dynamic response, in three dimensional space, of a flexible three-link hydraulic steel robot. The flexible robot was originally built under a grant from the Army Research Office (ARO) and has been the subject of a six year research project involving 12 graduate students and four faculty members. The research was continued under grant from the U.S. Department of Energy which is considering the use of robot in remote handling, placement and retrievability of H.L.N.W. canisters in geological formations. A series of static and dynamic experiments was conducted under two different loads at various angular positions of the robot links.

  15. Pilot-scale Limestone Emission Control (LEC) process: A development project. Volume 1, Main report and appendices A, B, C, and D: Final report

    SciTech Connect (OSTI)

    Prudich, M.E. [Ohio Univ., Athens, OH (United States); Appell, K.W.; McKenna, J.D. [ETS, Inc., Roanoke, VA (United States)

    1994-03-01T23:59:59.000Z

    ETS, Inc., a pollution consulting firm with headquarters in Roanoke, Virginia, has developed a dry, limestone-based flue gas desulfurization (FGD) system. This SO{sub 2} removal system, called Limestone Emission Control (LEC), can be designed for installation on either new or existing coal-fired boilers. In the LEC process, the SO{sub 2} in the flue gas reacts with wetted granular limestone that is contained in a moving bed. A surface layer of principally calcium sulfate (CaSO{sub 4}) is formed on the limestone. Periodic removal of this surface layer by mechanical agitation allows high utilization of the limestone granules. A nominal 5,000 acfm LEC pilot plant has been designed, fabricated and installed on the slipstream of a 70,000 pph stoker boiler providing steam to Ohio University`s Athens, Ohio campus. A total of over 90 experimental trials have been performed using the pilot-scale moving-bed LEC dry scrubber as a part of this research project with run times ranging up to a high of 125 hours. SO{sub 2} removal efficiencies as high as 99.9% were achievable for all experimental conditions studied during which sufficient humidification was added to the LEC bed. The LEC process and conventional limestone scrubbing have been compared on an equatable basis using flue gas conditions that would be expected at the outlet of the electrostatic precipitator (ESP) of a 500 MW coal-fired power plant. The LEC was found to have a definite economic advantage in both direct capital costs and operating costs. Based on the success and findings of the present project, the next step in LEC process development will be a full-scale commercial demonstration unit.

  16. Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program

    SciTech Connect (OSTI)

    Wijesinghe, A.M.

    1996-08-23T23:59:59.000Z

    This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

  17. Used fuel disposition research and development roadmap - FY10 status.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2010-10-01T23:59:59.000Z

    Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in the U.S. and other nations in understanding disposal concepts in different geologic media, but gaps in knowledge still exist. A principal aspect of concern to the UFDC as it considers the broad issues of siting a repository in different geologic media are the marked differences in the regulatory bases for assessing suitability and safety of a repository between the U.S. and other nations. Because the probability based - risked informed nature of the current U.S. regulations for high-level radioactive waste and spent nuclear fuel is sufficiently different from other regulations, information gained in previous studies, while useful, likely need to be supplemented to enable more convincing communication with the public, better defense of the numerical models, and stronger safety cases. Thus, it was recognized when the UFDC was established that there were readily identified disposal-related R&D opportunities to address knowledge gaps. An effort to document these research opportunities was a key component of Fiscal Year (FY) 2010 engineered system, natural system, and system-level modeling activities for a range of disposal environments. A principal contribution to identifying these gaps was a workshop held to gather perspectives from experts both within and external to the UFDC regarding R&D opportunities. In the planning for FY2010 it was expected that these activities would culminate with a UFDC research and development roadmap that would identify the knowledge gaps, discuss the R&D needed to fill these gaps, and prioritize the proposed R&D over both the near- and long-term. A number of knowledge gaps and needed R&D were identified and are discussed in this report. However, these preliminary R&D topics have not been evaluated in detail nor have they been prioritized to support future planning efforts. This will be completed in FY11 and the final UFDC Research and Development Roadmap will be completed. This report discusses proposed R&D topics in three areas related to repository siting, design, and performance: natural systems

  18. Evaluation of disposition scores in Bos indicus/Bos taurus cross calves at different stages of production

    E-Print Network [OSTI]

    Funkhouser, Rena Rebecca

    2008-10-10T23:59:59.000Z

    Rebecca Funkhouser, B.S., Virginia Tech Chair of Advisory Committee: Dr. Jim Sanders Aggressiveness, nervousness, flightiness, gregariousness and overall disposition were evaluated in F 2 Nellore-Angus embryo transfer calves (n = 443) from 13 full... for use in QTL analysis for major genes for disposition in Nellore-Angus cross cattle. v ACKNOWLEDGEMENTS First and foremost I would like to thank Dr. Sanders for being so much more than a committee chair. Your help and support both...

  19. An evaluation of known remaining oil resources in the United States: Project on advanced oil recovery and the states. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-10-01T23:59:59.000Z

    The Interstate Oil and Gas Compact Commission (IOGCC) has conducted a series of studies to evaluate the known, remaining oil resource in twenty-three (23) states. The primary objective of the IOGCC`s effort is to examine the potential impact of an aggressive and focused program of research, development, and demonstration (RD&D) and technology transfer on future oil recovery in the United States. As part of a larger effort by the IOGCC, this report focuses on the potential economic, social, and political benefits of improved oil recovery to the nation as a whole. Individual reports for major oil producing states have been separately published. The individual state reports include California, Illinois, Kansas, Louisiana, New Mexico, Oklahoma, Texas, and Wyoming. The analysis presented in this report is based on the databases and models available in the Tertiary Oil Recovery Information System (TORIS). TORIS is a tested and verified system maintained and operated by the Department of Energy`s Bartlesville Project Office. The TORTS system was used to evaluate over 2,300 major reservoirs in a consistent manner and on an individual basis, the results of which have been aggregated to arrive at the national total.

  20. Field grouting summary report on the WAG 4 seeps 4 and 6 removal action project, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3. Appendixes E and F

    SciTech Connect (OSTI)

    NONE

    1997-05-01T23:59:59.000Z

    During the summer of 1996, a unique multi-phase, multi-stage, low-pressure permeation grouting pilot program was performed inside portions of four unlined waste disposal trenches at Waste Area Grouping (WAG) 4 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The project was deemed a non-time-critical removal action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA); however, due to a history of heavy precipitation in the fall, the schedule was fast-tracked to meet an October 31, 1996 grouting completion date. The technical objective of the removal action was to reduce the off-site transport of j Strontium 90 ({sup 90}Sr) by grouting portions of four waste disposal trenches believed to be responsible for over 70 percent of the {sup 90}Sr leaving the site. A goal of the grouting operation was to reduce the average in situ hydraulic conductivity of the grouted waste materials to a value equal to or less than 1 x 10{sup -6} cm/sec. This target hydraulic conductivity value was established to be at least two orders of magnitude lower than that of the surrounding natural ground.

  1. Tri-State Synfuels Project Review: Volume 8. Commercial status of licensed process units. [Proposed Henderson, Kentucky coal to gasoline plant; licensed commercial processes

    SciTech Connect (OSTI)

    Not Available

    1982-06-01T23:59:59.000Z

    This document demonstrates the commercial status of the process units to be used in the Tri-State Synfuels Project at Henderson, Kentucky. The basic design philosophy as established in October, 1979, was to use the commercial SASOL II/III plants as a basis. This was changed in January 1982 to a plant configuration to produce gasoline via a methanol and methanol to gasoline process. To accomplish this change the Synthol, Oil workup and Chemical Workup Units were eliminated and replaced by Methanol Synthesis and Methanol to Gasoline Units. Certain other changes to optimize the Lurgi liquids processing eliminated the Tar Distillation and Naphtha Hydrotreater Units which were replaced by the Partial Oxidation Unit. The coals to be gasified are moderately caking which necessitates the installation of stirring mechanism in the Lurgi Dry Bottom gasifier. This work is in the demonstration phase. Process licenses either have been obtained or must be obtained for a number of processes to be used in the plant. The commercial nature of these processes is discussed in detail in the tabbed sections of this document. In many cases there is a list of commercial installations at which the licensed equipment is used.

  2. Electric power annual 1997. Volume 2

    SciTech Connect (OSTI)

    NONE

    1998-10-01T23:59:59.000Z

    The Electric Power Annual 1997, Volume 2 contains annual summary statistics at national, regional, and state levels for the electric power industry, including information on both electric utilities and nonutility power producers. Included are data for electric utility retail sales of electricity, associated revenue, and average revenue per kilowatthour of electricity sold; financial statistics; environmental statistics; power transactions; and demand-side management. Also included are data for US nonutility power producers on installed capacity; gross generation; emissions; and supply and disposition of energy. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts, and the general public with historical data that may be used in understanding US electricity markets. 15 figs., 62 tabs.

  3. U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option

    SciTech Connect (OSTI)

    Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

    1998-10-01T23:59:59.000Z

    A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

  4. Disposition of PUREX facility tanks D5 and E6 uranium and plutonium solutions. Final report

    SciTech Connect (OSTI)

    Harty, D.P.

    1993-12-01T23:59:59.000Z

    Approximately 9 kilograms of plutonium and 5 metric tons of uranium in a 1 molar nitric acid solution are being stored in two PUREX facility vessels, tanks D5 and E6. The plutonium was accumulated during cleanup activities of the plutonium product area of the PUREX facility. Personnel at PUREX recently completed a formal presentation to the Surplus Materials Peer Panel (SMPP) regarding disposition of the material currently in these tanks. The peer panel is a group of complex-wide experts who have been chartered by EM-64 (Office of Site and Facility Transfer) to provide a third party independent review of disposition decisions. The information presented to the peer panel is provided in the first section of this report. The panel was generally receptive to the information provided at that time and the recommendations which were identified.

  5. The environmental assessment of nuclear materials disposition options: A transportation perspective

    SciTech Connect (OSTI)

    Wilson, R.K.; Clauss, D.B.; Moyer, J.W.

    1994-12-31T23:59:59.000Z

    The US Department of Energy has undertaken a program to evaluate and select options for the long-term storage and disposition of fissile materials declared surplus to defense needs as a result of the end of the Cold War. The transport of surplus fissile material will be an important and highly visible aspect of the environmental impact studies and other planning documents required for implementation of the disposition options. This report defines the roles and requirements for transportation of fissile materials in the program, and discusses an existing methodology for determining the environmental impact in terms of risk. While it will be some time before specific alternatives are chosen that will permit the completion of detailed risk calculations, the analytical models for performing the probabilistic risk assessments already exist with much of the supporting data related to the transportation system. This report summarizes the various types of data required and identifies sources for that data.

  6. Fabrication of large-volume, low-cost ceramic lanthanum halide scintillators for gamma ray detection : final report for DHS/DNDO/TRDD project TA-01-SL01.

    SciTech Connect (OSTI)

    Boyle, Timothy J.; Ottley, Leigh Anna M.; Yang, Pin; Chen, Ching-Fong; Sanchez, Margaret R.; Bell, Nelson Simmons

    2008-10-01T23:59:59.000Z

    This project uses advanced ceramic processes to fabricate large, optical-quality, polycrystalline lanthanum halide scintillators to replace small single crystals produced by the conventional Bridgman growth method. The new approach not only removes the size constraint imposed by the growth method, but also offers the potential advantages of both reducing manufacturing cost and increasing production rate. The project goal is to fabricate dense lanthanum halide ceramics with a preferred crystal orientation by applying texture engineering and solid-state conversion to reduce the thermal mechanical stress in the ceramic and minimize scintillation light scattering at grain boundaries. Ultimately, this method could deliver the sought-after high sensitivity and <3% energy resolution at 662 keV of lanthanum halide scintillators and unleash their full potential for advanced gamma ray detection, enabling rapid identification of radioactive materials in a variety of practical applications. This report documents processing details from powder synthesis, seed particle growth, to final densification and texture development of cerium doped lanthanum bromide (LaBr{sub 3}:Ce{sup +3}) ceramics. This investigation demonstrated that: (1) A rapid, flexible, cost efficient synthesis method of anhydrous lanthanum halides and their solid solutions was developed. Several batches of ultrafine LaBr{sub 3}:Ce{sup +3} powder, free of oxyhalide, were produced by a rigorously controlled process. (2) Micron size ({approx} 5 {micro}m), platelet shape LaBr{sub 3} seed particles of high purity can be synthesized by a vapor phase transport process. (3) High aspect-ratio seed particles can be effectively aligned in the shear direction in the ceramic matrix, using a rotational shear-forming process. (4) Small size, highly translucent LaBr{sub 3} (0.25-inch diameter, 0.08-inch thick) samples were successfully fabricated by the equal channel angular consolidation process. (5) Large size, high density, translucent LaBr{sub 3} ceramics samples (3-inch diameter, > 1/8-inch thick) were fabricated by hot pressing, demonstrating the superior manufacturability of the ceramic approach over single crystal growth methods in terms of size capability and cost. (6) Despite all these advances, evidence has shown that LaBr{sub 3} is thermally unstable at temperatures required for the densification process. This is particularly true for material near the surface where lattice defects and color centers can be created as bromine becomes volatile at high temperatures. Consequently, after densification these samples made using chemically prepared ultrafine powders turned black. An additional thermal treatment in a flowing bromine condition proved able to reduce the darkness of the surface layer for these densified samples. These observations demonstrated that although finer ceramic powders are desirable for densification due to a stronger driving force from their large surface areas, the same desirable factor can lead to lattice defects and color centers when these powders are densified at higher temperatures where material near the surface becomes thermally unstable.

  7. Definitive design report: Design report project W-025, Radioactive Mixed Waste (RMW) Land Disposal Facility NON-DRAG-OFF. Revision 1, Volume 1 and 2

    SciTech Connect (OSTI)

    Roscha, V.

    1994-11-29T23:59:59.000Z

    The purpose of this report is to describe the definitive design of the Radioactive Mixed Waste (RMW) Non-Drag-Off disposal facility, Project W-025. This report presents a n of the major landfill design features and a discussion of how each of the criteria is addressed in the design. The appendices include laboratory test results, design drawings, and individual analyses that were conducted in support of the design. Revision 1 of this document incorporates design changes resulting from an increase in the required operating life of the W-025 landfill from 2 to 20 years. The rationale for these design changes is described in Golder Associates Inc. 1991a. These changes include (1) adding a 1.5-foot-thick layer of compacted admix directory-under the primary FML on the floor of the landfill to mitigate the effects of possible stress cracking in the primary flexible membrane liner (FML), and (2) increasing the operations layer thickness from two to three feet over the entire landfill area, to provide additional protection for the secondary admix layer against mechanical damage and the effects of freezing and desiccation. The design of the W-025 Landfill has also been modified in response to the results of the EPA Method 9090 chemical compatibility testing program (Golder Associates Inc. 1991b and 1991c), which was completed after the original design was prepared. This program consisted of testing geosynthetic materials and soil/bentonite admix with synthetic leachate having the composition expected during the life of the W-025 Landfill., The results of this program indicated that the polyester geotextile originally specified for the landfill might be susceptible to deterioration. On this basis, polypropylene geotextiles were substituted as a more chemically-resistant alternative. In addition, the percentage of bentonite in the admix was increased to provide sufficiently low permeability to the expected leachate.

  8. Wildlife Impact Assessment and Summary of Previous Mitigation Related to Hydroelectric Projects in Montana, Phase 1, Volume Two (B), Clark Fork River Projects, Cabinet Gorge and Noxon Rapids Dams, Operator, Washington Water Power Company.

    SciTech Connect (OSTI)

    Wood, Marilyn

    1984-06-01T23:59:59.000Z

    This report documents best available information concerning the wildlife species impacted and the degree of the impact. A target species list was developed to focus the impact assessment and to direct mitigation efforts. Many non-target species also incurred impacts but are not discussed in this report. All wildlife habitats inundated by the two reservoirs are represented by the target species. It was assumed the numerous non-target species also affected will be benefited by the mitigation measures adopted for the target species. Impacts addressed are limited to those directly attributable to the loss of habitat and displacement of wildlife populations due to the construction and operation of the two hydroelectric projects. Secondary impacts, such as the relocation of railroads and highways, and the increase of the human population, were not considered. In some cases, both positive and negative impacts were assessed; and the overall net effect was reported. The loss/gain estimates reported represent impacts considered to have occurred during one point in time except where otherwise noted. When possible, quantitative estimates were developed based on historical information from the area or on data from similar areas. Qualitative loss estimates of low, moderate, or high with supporting rationale were assessed for each species or species group.

  9. Nuclear Material Disposition | Y-12 National Security Complex

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOE Project TapsDOE

  10. Draft Environmental Assessment on the Remote-handled Waste Disposition

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField Campaign:INEA : Papers69Christopher FeckoDraft ResourceAdvice:Project

  11. US weapons-useable plutonium disposition policy: implementation of the MOX fuel option 

    E-Print Network [OSTI]

    Gonzalez, Vanessa L

    1998-01-01T23:59:59.000Z

    be construed as conflicting with the current proposed policy to use mixed-oxide fuel. Additionally, the plutonium disposition policy is completely contingent upon the United States' ability to secure a bilateml agreement with Russia for reciprocal plutonium..., Russia and India- may attempt to establish a global plutonium economy in which the U. S. , under its current policy, could not be a participant (Davis and Donnelly 1994). In fact, despite the United States' efforts to curtail proliferation risks...

  12. Decommissioning of Active Ventilation Systems in a Nuclear R and D Facility to Prepare for Building Demolition (Whiteshell Laboratories Decommissioning Project, Canada) - 13073

    SciTech Connect (OSTI)

    Wilcox, Brian; May, Doug; Howlett, Don; Bilinsky, Dennis [Atomic Energy of Canada Limited, Ara Mooradian Way, Pinawa, Manitoba (Canada)] [Atomic Energy of Canada Limited, Ara Mooradian Way, Pinawa, Manitoba (Canada)

    2013-07-01T23:59:59.000Z

    Whiteshell Laboratories (WL) is a nuclear research establishment owned by the Canadian government and operated by Atomic Energy of Canada Limited (AECL) since the early 1960's. WL is currently under a decommissioning license and the mandate is to remediate the nuclear legacy liabilities in a safe and cost effective manner. The WL Project is the first major nuclear decommissioning project in Canada. A major initiative underway is to decommission and demolish the main R and D Laboratory complex. The Building 300 R and D complex was constructed to accommodate laboratories and offices which were mainly used for research and development associated with organic-cooled reactors, nuclear fuel waste management, reactor safety, advanced fuel cycles and other applications of nuclear energy. Building 300 is a three storey structure of approximately 16,000 m{sup 2}. In order to proceed with building demolition, the contaminated systems inside the building have to be characterized, removed, and the waste managed. There is a significant focus on volume reduction of radioactive waste for the WL project. The active ventilation system is one of the significant contaminated systems in Building 300 that requires decommissioning and removal. The active ventilation system was designed to manage hazardous fumes and radioactivity from ventilation devices (e.g., fume hoods, snorkels and glove boxes) and to prevent the escape of airborne hazardous material outside of the laboratory boundary in the event of an upset condition. The system includes over 200 ventilation devices and 32 active exhaust fan units and high efficiency particulate air (HEPA) filters. The strategy to remove the ventilation system was to work from the laboratory end back to the fan/filter system. Each ventilation duct was radiologically characterized. Fogging was used to minimize loose contamination. Sections of the duct were removed by various cutting methods and bagged for temporary storage prior to disposition. Maintenance of building heating, ventilation and air conditioning (HVAC) balancing was critical to ensure proper airflow and worker safety. Approximately 103 m{sup 3} of equipment and materials were recovered or generated by the project. Low level waste accounted for approximately 37.4 m{sup 3}. Where possible, ducting was free released for metal recycling. Contaminated ducts were compacted into B-1000 containers and stored in a Shielded Modular Above-Ground Storage Facility (SMAGS) on the WL site awaiting final disposition. The project is divided into three significant phases, with Phases 1 and 2 completed. Lessons learned during the execution of Phases 1 and 2 have been incorporated into the current ventilation removal. (authors)

  13. Study of plutonium disposition using existing GE advanced Boiling Water Reactors

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

  14. Safeguards and security requirements for weapons plutonium disposition in light water reactors

    SciTech Connect (OSTI)

    Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

    1994-10-01T23:59:59.000Z

    This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

  15. PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Koenig, R.; Davies, S.

    2009-06-01T23:59:59.000Z

    Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

  16. Advanced Materials and Processing of Composites for High Volume...

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

    Focal Project 4: Structural Automotive Components from Composite Materials Advanced Materials and Processing of Composites for High Volume Applications Libby Berger (General...

  17. Water volume okay; early runoff leads to dry year declaration

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

    Water-volume-okay-early-runoff-leads-to-dry-year-declaration Sign In About | Careers | Contact | Investors | bpa.gov Search News & Us Expand News & Us Projects & Initiatives...

  18. Computing the Maximum Volume Inscribed Ellipsoid of a Polytopic ...

    E-Print Network [OSTI]

    Jianzhe Zhen

    2015-01-23T23:59:59.000Z

    Jan 23, 2015 ... Abstract: This paper introduces a method for computing the maximum volume inscribed ellipsoid and k-ball of a projected polytope. It is known ...

  19. Variable volume architecture : expanding the boundary

    E-Print Network [OSTI]

    Saheba, Asheshh (Asheshh Mohit), 1972-

    2001-01-01T23:59:59.000Z

    Research into the creation of a Variable Volume Architecture is explored through a series of proposals and projects. An argument is established to develop the means and methods of achieving an architecture of transformation. ...

  20. SLUDGE TREATMENT PROJECT KOP CONCEPTUAL DESIGN CONTROL DECISION REPORT

    SciTech Connect (OSTI)

    CARRO CA

    2010-03-09T23:59:59.000Z

    This control decision addresses the Knock-Out Pot (KOP) Disposition KOP Processing System (KPS) conceptual design. The KPS functions to (1) retrieve KOP material from canisters, (2) remove particles less than 600 {micro}m in size and low density materials from the KOP material, (3) load the KOP material into Multi-Canister Overpack (MCO) baskets, and (4) stage the MCO baskets for subsequent loading into MCOs. Hazard and accident analyses of the KPS conceptual design have been performed to incorporate safety into the design process. The hazard analysis is documented in PRC-STP-00098, Knock-Out Pot Disposition Project Conceptual Design Hazard Analysis. The accident analysis is documented in PRC-STP-CN-N-00167, Knock-Out Pot Disposition Sub-Project Canister Over Lift Accident Analysis. Based on the results of these analyses, and analyses performed in support of MCO transportation and MCO processing and storage activities at the Cold Vacuum Drying Facility (CVDF) and Canister Storage Building (CSB), control decision meetings were held to determine the controls required to protect onsite and offsite receptors and facility workers. At the conceptual design stage, these controls are primarily defined by their safety functions. Safety significant structures, systems, and components (SSCs) that could provide the identified safety functions have been selected for the conceptual design. It is anticipated that some safety SSCs identified herein will be reclassified based on hazard and accident analyses performed in support of preliminary and detailed design.

  1. No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

    SciTech Connect (OSTI)

    NONE

    1995-05-31T23:59:59.000Z

    The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site.

  2. FY 2012 USED FUEL DISPOSITION CAMPAIGN TRANSPORTATION TASK REPORT ON INL EFFORTS SUPPORTING THE MODERATOR EXCLUSION CONCEPT AND STANDARDIZED TRANSPORTATION

    SciTech Connect (OSTI)

    D. K. Morton

    2012-08-01T23:59:59.000Z

    Following the defunding of the Yucca Mountain Project, it is reasonable to assume that commercial used fuel will remain in storage for a longer time period than initially assumed. Previous transportation task work in FY 2011, under the Department of Energy’s Office of Nuclear Energy, Used Fuel Disposition Campaign, proposed an alternative for safely transporting used fuel regardless of the structural integrity of the used fuel, baskets, poisons, or storage canisters after an extended period of storage. This alternative assures criticality safety during transportation by implementing a concept that achieves moderator exclusion (no in-leakage of moderator into the used fuel cavity). By relying upon a component inside of the transportation cask that provides a watertight function, a strong argument can be made that moderator intrusion is not credible and should not be a required assumption for criticality evaluations during normal or hypothetical accident conditions of transportation. This Transportation Task report addresses the assigned FY 2012 work that supports the proposed moderator exclusion concept as well as a standardized transportation system. The two tasks assigned were to (1) promote the proposed moderator exclusion concept to both regulatory and nuclear industry audiences and (2) advance specific technical issues in order to improve American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, Division 3 rules for storage and transportation containments. The common point behind both of the assigned tasks is to provide more options that can be used to resolve current issues being debated regarding the future transportation of used fuel after extended storage.

  3. ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1997-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

  4. Programmatic methods for addressing contaminated volume uncertainties.

    SciTech Connect (OSTI)

    DURHAM, L.A.; JOHNSON, R.L.; RIEMAN, C.R.; SPECTOR, H.L.; Environmental Science Division; U.S. ARMY CORPS OF ENGINEERS BUFFALO DISTRICT

    2007-01-01T23:59:59.000Z

    Accurate estimates of the volumes of contaminated soils or sediments are critical to effective program planning and to successfully designing and implementing remedial actions. Unfortunately, data available to support the preremedial design are often sparse and insufficient for accurately estimating contaminated soil volumes, resulting in significant uncertainty associated with these volume estimates. The uncertainty in the soil volume estimates significantly contributes to the uncertainty in the overall project cost estimates, especially since excavation and off-site disposal are the primary cost items in soil remedial action projects. The Army Corps of Engineers Buffalo District's experience has been that historical contaminated soil volume estimates developed under the Formerly Utilized Sites Remedial Action Program (FUSRAP) often underestimated the actual volume of subsurface contaminated soils requiring excavation during the course of a remedial activity. In response, the Buffalo District has adopted a variety of programmatic methods for addressing contaminated volume uncertainties. These include developing final status survey protocols prior to remedial design, explicitly estimating the uncertainty associated with volume estimates, investing in predesign data collection to reduce volume uncertainties, and incorporating dynamic work strategies and real-time analytics in predesign characterization and remediation activities. This paper describes some of these experiences in greater detail, drawing from the knowledge gained at Ashland1, Ashland2, Linde, and Rattlesnake Creek. In the case of Rattlesnake Creek, these approaches provided the Buffalo District with an accurate predesign contaminated volume estimate and resulted in one of the first successful FUSRAP fixed-price remediation contracts for the Buffalo District.

  5. Constrained Inverse Volume Rendering for Planetary Nebulae Marcus Magnor

    E-Print Network [OSTI]

    Utah, University of

    Inverse Volume Rendering I.4.m [Image Processing and Computer Vision]: Miscellaneous--Volumetric Modeling that we are observing 2D projections of 3D volumes of glowing gas, the actual spatial struc- ture of PNeConstrained Inverse Volume Rendering for Planetary Nebulae Marcus Magnor MPI Informatik, Germany

  6. DATA QUALITY OBJECTIVES SUMMARY REPORT FOR WASTE DISPOSITION OF FY2004 ISRM INJECTION & MONITORING WELLS

    SciTech Connect (OSTI)

    THOMAS, G.

    2004-03-03T23:59:59.000Z

    The purpose of this data quality objective (DQO) summary report is to develop a sampling plan for waste disposition of soil cuttings and other drilling-related wastes that will result from the drilling of 21 injection wells and one groundwater monitoring well west of the 184-D Powerhouse Ash Pit in the 100-D Area of the Hanford Site. The 21 In Situ Redox Manipulation (ISRM) wells will inject treatment solutions to assist in intercepting and preventing the discharge of a hexavalent chromium plume to the Columbia River. The monitoring well will help establish groundwater chemistry downgradient of the ISRM zone. The proposed well locations are shown.

  7. SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03T23:59:59.000Z

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These “123 agreements” are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  8. A preliminary analysis of the reactor-based plutonium disposition alternative deployment schedules

    SciTech Connect (OSTI)

    Zurn, R.M.

    1997-09-01T23:59:59.000Z

    This paper discusses the preliminary analysis of the implementation schedules of the reactor-based plutonium disposition alternatives. These schedule analyses are a part of a larger process to examine the nine decision criteria used to determine the most appropriate method of disposing of U.S. surplus weapons plutonium. The preliminary analysis indicates that the mission durations for the reactor-based alternatives range from eleven years to eighteen years and the initial mission fuel assemblies containing surplus weapons-usable plutonium could be loaded into the reactors between nine and fourteen years after the Record of Decision.

  9. CONTAMINATED SOIL VOLUME ESTIMATE TRACKING METHODOLOGY

    SciTech Connect (OSTI)

    Durham, L.A.; Johnson, R.L.; Rieman, C.; Kenna, T.; Pilon, R.

    2003-02-27T23:59:59.000Z

    The U.S. Army Corps of Engineers (USACE) is conducting a cleanup of radiologically contaminated properties under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The largest cost element for most of the FUSRAP sites is the transportation and disposal of contaminated soil. Project managers and engineers need an estimate of the volume of contaminated soil to determine project costs and schedule. Once excavation activities begin and additional remedial action data are collected, the actual quantity of contaminated soil often deviates from the original estimate, resulting in cost and schedule impacts to the project. The project costs and schedule need to be frequently updated by tracking the actual quantities of excavated soil and contaminated soil remaining during the life of a remedial action project. A soil volume estimate tracking methodology was developed to provide a mechanism for project managers and engineers to create better project controls of costs and schedule. For the FUSRAP Linde site, an estimate of the initial volume of in situ soil above the specified cleanup guidelines was calculated on the basis of discrete soil sample data and other relevant data using indicator geostatistical techniques combined with Bayesian analysis. During the remedial action, updated volume estimates of remaining in situ soils requiring excavation were calculated on a periodic basis. In addition to taking into account the volume of soil that had been excavated, the updated volume estimates incorporated both new gamma walkover surveys and discrete sample data collected as part of the remedial action. A civil survey company provided periodic estimates of actual in situ excavated soil volumes. By using the results from the civil survey of actual in situ volumes excavated and the updated estimate of the remaining volume of contaminated soil requiring excavation, the USACE Buffalo District was able to forecast and update project costs and schedule. The soil volume tracking methodology helped the USACE Buffalo District track soil quantity changes from projected excavation work over time and across space, providing the basis for an explanation of some of the project cost and schedule variances.

  10. Project Year Project Title

    E-Print Network [OSTI]

    Gray, Jeffrey J.

    Project Year 2011-2012 Project Title Using M-Health and GIS Technology in the Field to Improve-specialized, but practically useless skill. Solution One goal of this summer's Applied Geographic Information Systems in Public lessons about observational epidemiology. Technologies Used Geographic Info System (GIS), Blackboard

  11. National Bioenergy Center Sugar Platform Integration Project: Quarterly Update #10, January-March 2006

    SciTech Connect (OSTI)

    Not Available

    2006-04-01T23:59:59.000Z

    Volume 10 of a quarterly newsletter that describes the activities of the National Bioenergy Center's Sugar Platform Integration Project.

  12. National Bioenergy Center Sugar Platform Integration Project: Quarterly Update #9, October-December 2005

    SciTech Connect (OSTI)

    Schell, D. J.

    2006-01-01T23:59:59.000Z

    Volume 9 of a quarterly newsletter that describes the activities of the National Bioenergy Center's Sugar Platform Integration Project.

  13. National Bioenergy Center Sugar Platform Integration Project: Quarterly Update #12, July-September 2006

    SciTech Connect (OSTI)

    Schell, D.

    2006-10-01T23:59:59.000Z

    Volume 12 of a quarterly newsletter that describes the activities of the National Bioenergy Center's Sugar Platform Integration Project.

  14. The Nuclear Material Focus Area Roadmapping Process Utilizing Environmental Management Complex-Wide Nuclear Material Disposition Pathways

    SciTech Connect (OSTI)

    Sala, D. R.; Furhman, P.; Smith, J. D.

    2002-02-26T23:59:59.000Z

    This paper describes the process that the Nuclear Materials Focus Area (NMFA) has developed and utilizes in working with individual Department of Energy (DOE) sites to identify, address, and prioritize research and development efforts in the stabilization, disposition, and storage of nuclear materials. By associating site technology needs with nuclear disposition pathways and integrating those with site schedules, the NMFA is developing a complex wide roadmap for nuclear material technology development. This approach will leverage technology needs and opportunities at multiple sites and assist the NMFA in building a defensible research and development program to address the nuclear material technology needs across the complex.

  15. MODELING OF PLUTONIUM RECOVERY AND DISCARD PROCESSES FOR THE PURPOSE OF SELECTING OPTIMUM (MINIMUM WASTE, COST AND DOSE) RESIDUE DISPOSITIONS

    SciTech Connect (OSTI)

    M. A. ROBINSON; M. B. KINKER; ET AL

    2001-04-01T23:59:59.000Z

    Researchers have developed a quantitative basis for disposition of actinide-bearing process residues. Research included the development of a technical rationale for determining when residues could be considered unattractive for proliferation purposes, and establishing plutonium-concentration-based discard ceilings of unimmobilized residues and richer discard ceilings for immobilized monolithic waste forms. Further quantitative analysis (process modeling) identifies the plutonium (Pu) concentration at which residues should be discarded to immobilization in order to minimize the quantifiable negative consequences of residue processing (cost, waste, dose). Results indicate that optimum disposition paths can be identified by process modeling, and that across-the-board discard decisions maximize negative consequences.

  16. Special Projects Branch

    E-Print Network [OSTI]

    Dear Mr. Krich; Joseph G. Giitter; S Troy Harris/lovington; James Ferl; Cty John Parker/nmed

    2006-01-01T23:59:59.000Z

    On June 6, 2005, you submitted a U.S. Department of Energy (DOE) report providing the basis for DOE’s cost estimate for dispositioning depleted uranium generated at your proposed uranium enrichment facility in

  17. Project Fact Sheet Project Update

    E-Print Network [OSTI]

    & Figures: Budget: £51,074,000 Funding Source: Capital Plan Construction Project Programme: Start on SiteProject Fact Sheet Project Update: Project Brief: The concept of the new scheme is to redevelop Gardens project http://www.imperial.ac.uk/princesgardens/ Construction Project Team: Project Facts

  18. University Loaned Normal Uranium Slug Disposition Study: University survey responses. Predecisional draft

    SciTech Connect (OSTI)

    Becker, G.W. Jr.

    1992-09-01T23:59:59.000Z

    During the 1950`s and 1960`s, the Atomic Energy Commission loaned rejected natural uranium slugs from the Savannah River Site to United States universities for use in subcritical assemblies. Currently, there are sixty-two universities holding 91,798 slugs, containing about 167 metric tons of natural uranium. It was originally planned that the universities would return the material to Fernald when they no longer required it. Fernald has not received slugs since it was shut down in 1988. The Department of Energy`s Office of Weapons and Materials Planning requested that the Planning Support Group develop information to assist them in facilitating the return of the unwanted slugs to one or more of their facilities and develop alternatives for the ultimate disposition of this material. This supplemental report to the University Loaned Normal Uranium Slug Disposition Study documents responses to and summarizes the results of a survey of fifty-eight universities. University contacts and survey responses covering loaned slug descriptions, historical information, radiological data, current status, and plans and schedules are documented.

  19. Implementation of safeguards and security for fissile materials disposition reactor alternative facilities

    SciTech Connect (OSTI)

    Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

    1995-10-01T23:59:59.000Z

    A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular attention will be given to the reactor alternatives which include existing, partially completed, advanced or evolutionary LWRs and CANDU reactors. The various reactor alternatives are all very similar and include processing which converts Pu to a usable form for fuel fabrication, a MOX fuel fab facility located in either the US or in Europe, US LWRs or the CANDU reactors and ultimate disposal of spent fuel in a geologic repository. This paper focuses on how the objectives of reducing security risks and strengthening arms reduction and nonproliferation will be accomplished and the possible impacts of meeting these objectives on facility operations and design. Some of the areas in this paper include: (1) domestic and international safeguards requirements, (2) non-proliferation criteria and measures, (3) the threat, and (4) potential proliferation risks, the impacts on the facilities, and safeguards and security issues unique to the presence of Category 1 or strategic special nuclear material.

  20. A comparative assessment of the economics of plutonium disposition including comparison with other nuclear fuel cycles

    SciTech Connect (OSTI)

    Williams, K.A.; Miller, J.W.; Reid, R.L.

    1997-05-01T23:59:59.000Z

    DOE has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. Other objectives of the paper are to discuss major technical and economic issues that impact plutonium disposition cost and schedule. Also to compare the economics of a once-through weapons-derived MOX nuclear fuel cycle to other fuel cycles, such as those utilizing spent fuel reprocessing. To evaluate the economics of these technologies on an equitable basis, a set of cost estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs.

  1. Evaluation of alternatives for the disposition of surplus weapons-usable plutonium

    SciTech Connect (OSTI)

    Dyer, J.S.; Butler, J.C. [Univ. of Texas, Austin, TX (United States); Edmunds, T. [Lawrence Livermore National Lab., CA (United States)] [and others

    1997-04-04T23:59:59.000Z

    The Department of Energy Record of Decision (ROD) selected alternatives for disposition of surplus, weapons grade plutonium. A major objective of this decision was to prevent the proliferation of nuclear weapons. Other concerns addressed included economic, technical, institutional, schedule, environmental, and health and safety issues. The analysis reported here was conducted in parallel with technical, environmental, and nonproliferation analyses; it uses multiattribute utility theory to combine these considerations in order to facilitate an integrated evaluation of alternatives. This analysis is intended to provide additional insight regarding alternative evaluation and to assist in understanding the rationale for the choice of alternatives recommended in the ROD. Value functions were developed for objectives of disposition, and used to rank alternatives. Sensitivity analyses indicated that the ranking of alternatives for the base case was relatively insensitive to changes in assumptions over reasonable ranges. The analyses support the recommendation of the ROD to pursue parallel development of the vitrification immobilization alternative and the use of existing light water reactors alternative. 27 refs., 109 figs., 20 tabs.

  2. Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel and nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.

  3. Estimating Residual Solids Volume In Underground Storage Tanks

    SciTech Connect (OSTI)

    Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.; Tihey, John R.

    2014-01-08T23:59:59.000Z

    The Savannah River Site liquid waste system consists of multiple facilities to safely receive and store legacy radioactive waste, treat, and permanently dispose waste. The large underground storage tanks and associated equipment, known as the 'tank farms', include a complex interconnected transfer system which includes underground transfer pipelines and ancillary equipment to direct the flow of waste. The waste in the tanks is present in three forms: supernatant, sludge, and salt. The supernatant is a multi-component aqueous mixture, while sludge is a gel-like substance which consists of insoluble solids and entrapped supernatant. The waste from these tanks is retrieved and treated as sludge or salt. The high level (radioactive) fraction of the waste is vitrified into a glass waste form, while the low-level waste is immobilized in a cementitious grout waste form called saltstone. Once the waste is retrieved and processed, the tanks are closed via removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations and severing/sealing external penetrations. The comprehensive liquid waste disposition system, currently managed by Savannah River Remediation, consists of 1) safe storage and retrieval of the waste as it is prepared for permanent disposition; (2) definition of the waste processing techniques utilized to separate the high-level waste fraction/low-level waste fraction; (3) disposition of LLW in saltstone; (4) disposition of the HLW in glass; and (5) closure state of the facilities, including tanks. This paper focuses on determining the effectiveness of waste removal campaigns through monitoring the volume of residual solids in the waste tanks. Volume estimates of the residual solids are performed by creating a map of the residual solids on the waste tank bottom using video and still digital images. The map is then used to calculate the volume of solids remaining in the waste tank. The ability to accurately determine a volume is a function of the quantity and quality of the waste tank images. Currently, mapping is performed remotely with closed circuit video cameras and still photograph cameras due to the hazardous environment. There are two methods that can be used to create a solids volume map. These methods are: liquid transfer mapping / post transfer mapping and final residual solids mapping. The task is performed during a transfer because the liquid level (which is a known value determined by a level measurement device) is used as a landmark to indicate solids accumulation heights. The post transfer method is primarily utilized after the majority of waste has been removed. This method relies on video and still digital images of the waste tank after the liquid transfer is complete to obtain the relative height of solids across a waste tank in relation to known and usable landmarks within the waste tank (cooling coils, column base plates, etc.). In order to accurately monitor solids over time across various cleaning campaigns, and provide a technical basis to support final waste tank closure, a consistent methodology for volume determination has been developed and implemented at SRS.

  4. Project Funding

    Broader source: Energy.gov [DOE]

    Federal energy projects require funding to generate results. Carefully matching available funding options with specific project needs can make the difference between a stalled, unfunded project and a successful project generating energy and cost savings.

  5. NCBI Handout Series | BioProject | Last Update August 19, 2013 Contact: info@ncbi.nlm.nih.gov Biological studies in the post-genome era often produce large volumes of complex and high-throughput

    E-Print Network [OSTI]

    Levin, Judith G.

    Project. Registering a project requires credentials from an MyNCBI, NIH or eRA login. Searching with "Chinchilla [orgn of Health · Department of Health and Human Services B A C E D Chinchilla [organism] #12;The Bio

  6. Volume Comparison

    Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial and InstitutionalArea:Mnt(N)3.1.Liquids ReserveVolume

  7. Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky

    E-Print Network [OSTI]

    US Army Corps of Engineers

    until 1981 when it was closed due to declining boat traffic. Since the failure of Green River Dam 4 by the dams and the impacts if the pool were to be lost, either by demolition or failure of the lock andGreen River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16

  8. Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-02-26T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

  9. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW of solid wastes and advance sustainable waste management in the U.S. to the level of several leading-2010, the Earth Engineering Center (EEC) of Columbia University conducted a bi- annual survey on Municipal Solid

  10. A little here, a little there, a fairly big problem everywhere: Small quantity site transuranic waste disposition alternatives

    SciTech Connect (OSTI)

    D. Luke; D. Parker; J. Moss; T. Monk (INEEL); L. Fritz (DOE-ID); B. Daugherty (SRS); K. Hladek (WM Federal Services Hanford); S. Kosiewicx (LANL)

    2000-02-27T23:59:59.000Z

    Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound Laboratory. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

  11. A Little Here, A Little There, A Fairly Big Problem Everywhere: Small Quantity Site Transuranic Waste Disposition Alternatives

    SciTech Connect (OSTI)

    Luke, Dale Elden; Parker, Douglas Wayne; Moss, J.; Monk, Thomas Hugh; Fritz, Lori Lee; Daugherty, B.; Hladek, K.; Kosiewicx, S.

    2000-03-01T23:59:59.000Z

    Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

  12. A Roadmap and Discussion of Issues for Physics Analyses Required to Support Plutonium Disposition in VVER-1000 Reactors

    SciTech Connect (OSTI)

    Primm, R.T.; Drischler, J.D.; Pavlovichev, A.M. Styrine, Y.A.

    2000-06-01T23:59:59.000Z

    The purpose of this report is to document the physics analyses that must be performed to successfully disposition weapons-usable plutonium in VVER-1000 reactors in the Russian Federation. The report is a document to support programmatic and financial planning. It does not include documentation of the technical procedures by which physics analyses are performed, nor are the results of any analyses included.

  13. Dispositional reflections 

    E-Print Network [OSTI]

    Brummans, Boris H. J. M.

    2005-02-17T23:59:59.000Z

    In this dissertation, I explicate how scholars implicate themselves in the subfield of organizational communication studies by engaging in antinomic language-games which make the conduct of research (and textwork in particular) possible. My...

  14. Dispositional reflections

    E-Print Network [OSTI]

    Brummans, Boris H. J. M.

    2005-02-17T23:59:59.000Z

    analysis suggests that the studied scholars enact these games to understand a more or less common object of knowledge, but also to constitute a more or less identifiable position in this given social space. Reflection on the ontological complicity between...

  15. End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

    2010-09-01T23:59:59.000Z

    This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

  16. Piloting A Monitoring Program For CCC LWD Projects

    E-Print Network [OSTI]

    Atherton, Shanna; Zhu, Bingyao

    2013-01-01T23:59:59.000Z

    R. Micheli. "Evaluating Stream Restoration Projects."In Salmonid Stream Habitat Restoration Manual, Volume 1, byCalifornia." In Salmon Stream Habitat Restoration Manual, by

  17. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 2 of 3

    SciTech Connect (OSTI)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  18. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 3 of 3

    SciTech Connect (OSTI)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  19. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 1 of 3

    SciTech Connect (OSTI)

    Beck Colleen M,Edwards Susan R.,King Maureen L.

    2011-09-01T23:59:59.000Z

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  20. Savannah River Site Approved Site Treatment Plan, 2001 Annual Update (Volumes I and II)

    SciTech Connect (OSTI)

    Lawrence, B.

    2001-04-30T23:59:59.000Z

    The Compliance Plan Volume (Volume I) identifies project activity scheduled milestones for achieving compliance with Land Disposal Restrictions. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.

  1. Waste management project fiscal year 1998 multi-year work plan WBS 1.2

    SciTech Connect (OSTI)

    Slaybaugh, R.R.

    1997-08-29T23:59:59.000Z

    The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

  2. Waste minimization handbook, Volume 1

    SciTech Connect (OSTI)

    Boing, L.E.; Coffey, M.J.

    1995-12-01T23:59:59.000Z

    This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

  3. Development of a fresh MOX fuel transport package for disposition of weapons plutonium

    SciTech Connect (OSTI)

    Ludwig, S.B.; Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D. [Oak Ridge National Lab., TN (United States); Chae, S.M. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

    1998-11-01T23:59:59.000Z

    The US Department of Energy announced its Record of Decision on January 14, 1997, to embark on a dual-track approach for disposition of surplus weapons-usable plutonium using immobilization in glass or ceramics and burning plutonium as mixed-oxide (MOX) fuel in reactors. In support of the MOX fuel alternative, Oak Ridge National Laboratory initiated development of conceptual designs for a new package for transporting fresh (unirradiated) MOX fuel assemblies between the MOX fabrication facility and existing commercial light-water reactors in the US. This paper summarizes progress made in development of new MOX transport package conceptual designs. The development effort has included documentation of programmatic and technical requirements for the new package and development and analysis of conceptual designs that satisfy these requirements.

  4. North Area Right-of-Way Maintenance Project

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

    Sacramento Valley Right-of-Way Maintenance Project Sacramento Valley Right-of-Way Maintenance Project Final EA Report Cover Vol I August 2005(PDF - 492 MG) Final EA Main Volume...

  5. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    SciTech Connect (OSTI)

    Not Available

    1984-01-01T23:59:59.000Z

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

  6. Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

  7. A Methodology for the Analysis and Selection of Alternative for the Disposition of Surplus Plutonium

    SciTech Connect (OSTI)

    NONE

    1999-08-31T23:59:59.000Z

    The Department of Energy (DOE) - Office of Fissile Materials Disposition (OFMD) has announced a Record of Decision (ROD) selecting alternatives for disposition of surplus plutonium. A major objective of this decision was to further U.S. efforts to prevent the proliferation of nuclear weapons. Other concerns that were addressed include economic, technical, institutional, schedule, environmental, and health and safety issues. The technical, environmental, and nonproliferation analyses supporting the ROD are documented in three DOE reports [DOE-TSR 96, DOE-PEIS 96, and DOE-NN 97, respectively]. At the request of OFMD, a team of analysts from the Amarillo National Resource Center for Plutonium (ANRCP) provided an independent evaluation of the alternatives for plutonium that were considered during the evaluation effort. This report outlines the methodology used by the ANRCP team. This methodology, referred to as multiattribute utility theory (MAU), provides a structure for assembling results of detailed technical, economic, schedule, environment, and nonproliferation analyses for OFMD, DOE policy makers, other stakeholders, and the general public in a systematic way. The MAU methodology has been supported for use in similar situations by the National Research Council, an agency of the National Academy of Sciences.1 It is important to emphasize that the MAU process does not lead to a computerized model that actually determines the decision for a complex problem. MAU is a management tool that is one component, albeit a key component, of a decision process. We subscribe to the philosophy that the result of using models should be insights, not numbers. The MAU approach consists of four steps: (1) identification of alternatives, objectives, and performance measures, (2) estimation of the performance of the alternatives with respect to the objectives, (3) development of value functions and weights for the objectives, and (4) evaluation of the alternatives and sensitivity analysis. These steps are described below.

  8. LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

  9. Idaho High-Level Waste & Facilities Disposition, Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2002-10-11T23:59:59.000Z

    This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. After considering comments on the Draft EIS (DOE/EIS-0287D), as well as information on available treatment technologies, DOE and the State of Idaho have identified separate preferred alternatives for waste treatment. DOE's preferred alternative for waste treatment is performance based with the focus on placing the wastes in forms suitable for disposal. Technologies available to meet the performance objectives may be chosen from the action alternatives analyzed in this EIS. The State of Idaho's Preferred Alternative for treating mixed transuranic waste/SBW and calcine is vitrification, with or without calcine separations. Under both the DOE and State of Idaho preferred alternatives, newly generated liquid waste would be segregated after 2005, stored or treated directly and disposed of as low-level, mixed low-level, or transuranic waste depending on its characteristics. The objective of each preferred alternative is to enable compliance with the legal requirement to have INEEL HLW road ready by a target date of 2035. Both DOE and the State of Idaho have identified the same preferred alternative for facilities disposition, which is to use performance-based closure methods for existing facilities and to design new facilities consistent with clean closure methods.

  10. Project Title:

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

    Repair flowline 61-66-SX-3 DOE Code: Project Lead: Wes Riesland NEPA COMPLIANCE SURVEY 291 Project Information Date: 31 12010 Contractor Code: Project Overview In order to...

  11. DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.

  12. Review of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project, September 2011

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, anEnergy nepdg_5251_5500.pdfAnalysis of Downwash from

  13. Rigollier C., Wald L., 1999. The HelioClim Project: from satellite images to solar radiation maps. In Proceedings of the ISES Solar World Congress 1999, Jerusalem, Israel, July 4-9, 1999, volume I, pp 427-431.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Rigollier C., Wald L., 1999. The HelioClim Project: from satellite images to solar radiation maps-431. THE HELIOCLIM PROJECT: FROM SATELLITE IMAGES TO SOLAR RADIATION MAPS C. Rigollier, L. Wald Ecole des Mines de such a climatological database of solar radiation, images of the visible channel of the series of Meteosat

  14. Sandia Software Guidelines, Volume 2. Documentation

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    This volume is one in a series of Sandia Software Guidelines intended for use in producing quality software within Sandia National Laboratories. In consonance with the IEEE Standards for software documentation, this volume provides guidance in the selection of an adequate document set for a software project and example formats for many types of software documentation. A tutorial on life cycle documentation is also provided. Extended document thematic outlines and working examples of software documents are available on electronic media as an extension of this volume.

  15. The Relationship of Student Dispositions and Teacher Characteristics with the Mathematics Achievement of Students in Lebanon and Six Arab Countries in TIMSS 2007.

    E-Print Network [OSTI]

    Younes, Rayya

    2013-03-22T23:59:59.000Z

    The present study is divided into two parts. The first part examines the performance of Lebanese students in public and private schools in Lebanon in 8th grade using the TIMSS 2007 data. The effects of students’ dispositions and teacher...

  16. Programmatic methods for addressing contaminated volume uncertainties

    SciTech Connect (OSTI)

    Rieman, C.R.; Spector, H.L. [U.S. Army Corps of Engineers Buffalo District, Buffalo, NY (United States); Durham, L.A.; Johnson, R.L. [Argonne National Laboratory, Environmental Science Div., IL (United States)

    2007-07-01T23:59:59.000Z

    Accurate estimates of the volumes of contaminated soils or sediments are critical to effective program planning and to successfully designing and implementing remedial actions. Unfortunately, data available to support the pre-remedial design are often sparse and insufficient for accurately estimating contaminated soil volumes, resulting in significant uncertainty associated with these volume estimates. The uncertainty in the soil volume estimates significantly contributes to the uncertainty in the overall project cost estimates, especially since excavation and off-site disposal are the primary cost items in soil remedial action projects. The U.S. Army Corps of Engineers Buffalo District's experience has been that historical contaminated soil volume estimates developed under the Formerly Utilized Sites Remedial Action Program (FUSRAP) often underestimated the actual volume of subsurface contaminated soils requiring excavation during the course of a remedial activity. In response, the Buffalo District has adopted a variety of programmatic methods for addressing contaminated volume uncertainties. These include developing final status survey protocols prior to remedial design, explicitly estimating the uncertainty associated with volume estimates, investing in pre-design data collection to reduce volume uncertainties, and incorporating dynamic work strategies and real-time analytics in pre-design characterization and remediation activities. This paper describes some of these experiences in greater detail, drawing from the knowledge gained at Ashland 1, Ashland 2, Linde, and Rattlesnake Creek. In the case of Rattlesnake Creek, these approaches provided the Buffalo District with an accurate pre-design contaminated volume estimate and resulted in one of the first successful FUSRAP fixed-price remediation contracts for the Buffalo District. (authors)

  17. Oak Ridge K-25 Site Technology Logic Diagram. Volume 1, Technology evaluation

    SciTech Connect (OSTI)

    Fellows, R.L. [ed.

    1993-02-26T23:59:59.000Z

    The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration and waste management problems at the Oak Ridge K-25 Site to potential technologies that can remediate these problems. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remedial action, and decontamination and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. This Volume, Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This volume is divided into ten chapters. The first chapter is a brief introduction, and the second chapter details the technical approach of the TLD. These categories are the work activities necessary for successful decontamination and decommissioning, waste management, and remedial action of the K-25 Site. The categories are characterization, decontamination, dismantlement, robotics and automation, remedial action, and waste management. Materials disposition is addressed in Chap. 9. The final chapter contains regulatory compliance information concerning waste management, remedial action, and decontamination and decommissioning.

  18. Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials

    SciTech Connect (OSTI)

    NONE

    1995-03-29T23:59:59.000Z

    Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

  19. Project Controls

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-03-28T23:59:59.000Z

    Project controls are systems used to plan, schedule, budget, and measure the performance of a project/program. The cost estimation package is one of the documents that is used to establish the baseline for project controls. This chapter gives a brief description of project controls and the role the cost estimation package plays.

  20. Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

  1. Advances in Lung Volume

    E-Print Network [OSTI]

    Jones, Michelle

    Advances in Lung Volume Reduction Surgery The Ohio University Medical Center Lung Volume Reduction LungVolumeReductionSurgery Spring 2010 © 2010 The Ohio State University Medical Center ­ 04 Consult Ohio State's #12;The Ohio State University Medical Center Lung Volume Reduction Surgery Patient

  2. Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program

    SciTech Connect (OSTI)

    Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

    1997-12-01T23:59:59.000Z

    This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

  3. X-ray fluorescence spectroscopy for the elemental analysis of plutonium-bearing materials for the materials disposition program

    SciTech Connect (OSTI)

    Voit, S.L.; Boerigter, S.T.; Rising, T.L.

    1997-11-01T23:59:59.000Z

    The US Fissile Materials Disposition (MD) program will disposition about 50 MT of plutonium in the next century. Both of the alternative technologies for disposition, MOX Fuel and Immobilization require knowledge of the incoming composition to 1--5 wt%. Wavelength Dispersive X-Ray Fluorescence (WDXRF) systems, a common elemental analysis technology with a variety of industrial applications and commercial vendors, can readily achieve this level of characterization. Since much of the excess plutonium will be packaged in a long-term storage container as part of the DOE Environmental Management (DOE-EM) program to stabilize plutonium-bearing materials, the characterization system must be implemented during the packaging process. The authors describe a preliminary design for the integration of the WDXRF system into the packaging system to be used at the Rocky Flats site. The Plutonium Stabilization and Packaging System (PuSPS), coupled with the WDXRF characterization system will provide MD with stabilized plutonium-bearing excess material that can be more readily fed to an immobilization facility. The overall added expense to the MD program of obtaining analytical information after materials have been packaged in long-term storage containers could far exceed the expense of implementing XRF analysis during the packaging process.

  4. NEAMS VLTS project : level 2 milestone summary.

    SciTech Connect (OSTI)

    Hansen, Glen A.; Ostien, Jakob T.; Chen, Qiushi

    2012-08-01T23:59:59.000Z

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Very Long Term Storage (VLTS) Project is to develop a simple, benchmark model that describes the performance of Zry4 d-hydrides in cladding, under conditions of long-term storage of used fuel. This model will be used to further explore the requirements of hydride modeling for used fuel storage and transport. It is expected that this model will be further developed as its weaknesses are understood, and as a basis of comparison as the Used Fuel Disposition (UFD) Campaign explores more comprehensive, multiscale approaches. Cladding hydride processes, a thermal model, a hydride model API, and the initial implementation of the J2Fiber hydride model is documented in this report.

  5. SRS MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01T23:59:59.000Z

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 2 or 3 facility with storage of bulk PuO{sub 2} and assembly, storage, and shipping of fuel bundles in an S and S Category 1 facility. The total Category 1 approach, which is the recommended option, would be done in the 221-H Canyon Building. A facility that was never in service will be removed from one area, and a hardened wall will be constructed in another area to accommodate execution of the LA fuel fabrication. The non-Category 1 approach would require removal of process equipment in the FB-Line metal production and packaging glove boxes, which requires work in a contamination area. The Immobilization Hot Demonstration Program equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

  6. Project Fact Sheet Project Update

    E-Print Network [OSTI]

    Project Fact Sheet Project Update: Project Brief: The works cover the refurbishment of floors 4, 5, with `wet' labs for molecular biology, materials characterisation, cell culture and flow studies, and `dry operating theatre. The Bionanotechnology Centre is one of the projects funded from the UK Government's £20

  7. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    .union.ic.ac.uk/marketing/building Construction Project Team: Project Facts & Figures: Budget: £1,400,000 Funding Source: Capital PlanProject Fact Sheet Project Brief: In the first phase of the Union Building re that it adapts to meet the needs of a changing student body. The re-development plans are grounded in a full

  8. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    Facts & Figures: Budget: £3,500,000 Funding Source: SRIF III Construction Project Programme: StartProject Fact Sheet Project Brief: This project refurbished half of the 5th and 7th floors of work includes: · Building fabric replacement and revised space planning · New mechanical and electrical

  9. Final environmental impact statement/report. Volume 3. Response to comments on draft environmental impact statement/report. Northeast corridor improvement project electrification: New Haven CT to Boston, MA

    SciTech Connect (OSTI)

    NONE

    1994-10-31T23:59:59.000Z

    This document is the final environmental impact statement and final environmental impact report (FEIS/R) on the proposal by the National Railroad Passenger Corporation (Amtrak) to complete the electrification of the Northeast Corridor main line by extending electric traction from New Haven, CT, to Boston, MA. This document (Volume III) of the FEIS/R presents summaries of comments received on the DEIS/R and responses to these comments.

  10. Full-scale incineration-system demonstration at the Naval Battalion Construction Center, Gulfport, Mississippi. volume 8. delisting. Final report, Sep 86-Feb 89

    SciTech Connect (OSTI)

    Haley, D.J.

    1991-07-01T23:59:59.000Z

    Volume VIII documents the regulatory and technical lessons learned concerning disposition of soil after treatment. The report also documents the data collected in support of soil disposition. It explains EPA's use of the Vertical Horizontal Spread/Organic Leachate Model (VHS/OLM) to show the health risk of a hazardous waste site. Field operations and subsequent analyses were undertaken to support delisting of the soil, including the verification test burn, a RCRA trial burn, and data collected during routine operations. Conclusions are presented that can be drawn from the delisting process. It examines problems with EPA's Practical Quantitation Limits and VHS/OLM, the cost and level of effort, the technical complexity, the required concentrations needed for delisting, and the Air Force response to EPA's implied delisting denial. Six recommendations are offered to anyone considering submission of a delisting petition for a hazardous waste.

  11. Site Selection for the Salt Disposition Facility at the Savannah River Site

    SciTech Connect (OSTI)

    Gladden, J.B.; Rueter, K.J.; Morin, J.P.

    2000-11-15T23:59:59.000Z

    A site selection study was conducted to identify a suitable location for the construction and operation of a new Salt Disposition Facility (SDF) at the Savannah River Site (SRS). The facility to be sited is a single processing facility and support buildings that could house either of three technology alternatives being developed by the High Level Waste Systems Engineering Team: Small Tank Tetraphenylborate Precipitation, Crystalline Silicotitanate Non-Elutable Ion Exchange or Caustic Side Solvent Extraction. A fourth alternative, Direct Disposal in grout, is not part of the site selection study because a location has been identified that is unique to this technology (i.e., Z-Area). Facility site selection at SRS is a formal, documented process that seeks to optimize siting of new facilities with respect to facility-specific engineering requirements, sensitive environmental resources, and applicable regulatory requirements. In this manner, the prime objectives of cost minimization, environmental protection, and regulatory compliance are achieved. The results from this geotechnical characterization indicated that continued consideration be given to Site B for the proposed SDF. Suitable topography, the lack of surface hydrology and floodplain issues, no significant groundwater contamination, the presence of minor soft zones along the northeast portion of footprint, and no apparent geological structure in the Gordon Aquitard support this recommendation.

  12. Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze; Dr. Koji Shirai

    2012-07-01T23:59:59.000Z

    Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

  13. Investor Confidence Project

    E-Print Network [OSTI]

    Golden, M.

    2013-01-01T23:59:59.000Z

    Actionable Data ESL-KT-13-12-38 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 Near-Term: Not Enough Deal-Flow • High Transaction Costs • Lack of Viable Origination Channels • Highly Variable Performance • Complex... Custom Projects ESL-KT-13-12-38 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 Long-Term: High Cost of Capital • More equity than debt • Not enough volume to securitize • Insufficient actuarial data...

  14. STATE OF CALIFORNIA CONSTANT VOLUME SINGLE ZONE UNITARY AIR CONDITIONER AND HEAT PUMP SYSTEMS

    E-Print Network [OSTI]

    STATE OF CALIFORNIA CONSTANT VOLUME SINGLE ZONE UNITARY AIR CONDITIONER AND HEAT PUMP SYSTEMS CEC Volume Single Zone Unitary Air Conditioner and Heat Pump Systems (Page 1 of 4) Project Name CONSTANT VOLUME SINGLE ZONE UNITARY AIR CONDITIONER AND HEAT PUMP SYSTEMS CEC-MECH-3A (Revised 08

  15. Computer News, Volume 3

    E-Print Network [OSTI]

    [mandelbrot set] MATH DEPT Computer News, Volume 3. How to take advantage of the newer, faster machines on our network ...

  16. Computer News, Volume 2

    E-Print Network [OSTI]

    [mandelbrot set] MATH DEPT Computer News, Volume 2. How to handle .pdf files on the web: acroread, distill, and Netscape ...

  17. Assessing alternative strategies for the disposition of weapons-grade uranium and plutonium

    SciTech Connect (OSTI)

    Chow, B.G.

    1995-12-31T23:59:59.000Z

    Highly-enriched uranium (HEU) from dismantled nuclear weapons and military inventory can be blended down into proliferation-resistant low-enriched uranium and used economically as fuel in current nuclear reactors. However, the US can no longer expect the agreement to purchase and resell the uranium blended down from 500 metric tons of Russia`s HEU to be budget neutral. The authors recommend that other countries participate in the repurchase of blended-down uranium from the US and that a multilateral offer to Russia, which acts on behalf of all four former Soviet nuclear republics, be made for the purchase of the blended-down uranium from Russia`s remaining HEU. Since spent fuel in temporary storage worldwide contains enough plutonium to fuel breeders on any realistic buildup schedule in the event that breeders are needed, there is no need to save the weapons-grade plutonium for the future. This paper compares the costs of burning it in existing light water reactors, storing it indefinitely, and burying it after 20 years of storage. They found that the present-valued cost is about $1 to 2 billion in US dollars for all three alternatives. The deciding factor for selection should be an alternative`s proliferation resistance. Prolonged plutonium storage in Russia runs the risk of theft and, if the Russian political scene turns for the worse, the risk of re-use in its nuclear arsenal. The most urgent issue, however, is to determine not the disposition alternative but whether Russia will let its weapons-grade plutonium leave the former Soviet Republics (FSRs). The US should offer to buy and remove such plutonium from the FSRs. If Russia refuses even after the best US efforts, the US should then persuade Russia to burn or bury the plutonium, but not store it indefinitely for future breeder use.

  18. A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 1

    SciTech Connect (OSTI)

    NONE

    1995-05-01T23:59:59.000Z

    This report presents a comprehensive inventory of the radiological and nonradiological contaminants in waste buried or projected to be buried from 1984 through 2003 in the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The project to compile the inventory is referred to as the recent and projected data task. The inventory was compiled primarily for use in a baseline risk assessment under the Comprehensive Environmental Response, Compensation, and Liability Act. The compiled information may also be useful for environmental remediation activities that might be necessary at the RWMC. The information that was compiled has been entered into a database termed CIDRA-the Contaminant Inventory Database for Risk Assessment. The inventory information was organized according to waste generator and divided into waste streams for each generator. The inventory is based on waste information that was available in facility operating records, technical and programmatic reports, shipping records, and waste generator forecasts. Additional information was obtained by reviewing the plant operations that originally generated the waste, by interviewing personnel formerly employed as operators, and by performing nuclear physics and engineering calculations. In addition to contaminant inventories, information was compiled on the physical and chemical characteristics and the packaging of the 99 waste streams. The inventory information for waste projected to be buried at the SDA in the future was obtained from waste generator forecasts. The completeness of the contaminant inventories was confirmed by comparing them against inventories in previous reports and in other databases, and against the list of contaminants detected in environmental monitoring performed at the RWMC.

  19. UMTRA Project Office Records Management Plan

    SciTech Connect (OSTI)

    Not Available

    1993-06-01T23:59:59.000Z

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Office maintains two distinct records handling areas. One of the areas is maintained by a Technical Assistance Contractor (TAC), and is referred to as the UMTRA Project Document Control Center (UPDCC). The UPDCC manages all UMTRA records except those dealing with contracts, personnel, budgeting, finance, and any other documents which are of a purely administrative nature. The second area, the UMTRA Project Administrative Files Collection (UPAFC), contains all those records listed above that are not managed by the UPDCC. This Records Management Plan (RMP) for the UPAFC will be the framework for identifying the elements and activities that relate to the management and operational aspects involved in the handling of UPAFC. Guidelines for the program will be obtained from US Department of Energy (DOE) Orders. DOE Orders implement the guidelines issued by the National Archives and Records Administration (NARA), the final authority for records management. The RMP will address the life cycle of records, including their creation, maintenance, use, and disposition.

  20. Microsoft Word - DOE News Release - 'Deactivation Project Begins...

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

    include deactivation and stabilization, environmental cleanup, waste disposition, depleted uranium conversion, and eventual decontamination and demolition of the plant. The...

  1. Mission Need Statement: Idaho Spent Fuel Facility Project

    SciTech Connect (OSTI)

    Barbara Beller

    2007-09-01T23:59:59.000Z

    Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

  2. Magnesium Projects

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

    cyberinfrastructure projects and will be augmented by original research in Computer Science and Software Engineering towards the creation of large, distributed, autonomic and...

  3. Project Construction

    Broader source: Energy.gov [DOE]

    Integrating renewable energy into Federal new construction or major renovations requires effective structuring of the construction team and project schedule. This overview discusses key construction team considerations for renewable energy as well as timing and expectations for the construction phase. The project construction phase begins after a project is completely designed and the construction documents (100%) have been issued. Construction team skills and experience with renewable energy technologies are crucial during construction, as is how the integration of renewable energy affects the project construction schedule.

  4. Evaluation/disposition of observations no. 6-17, 6-18, and 6-22 from site electrical assessment report, 300 area powerhouse and emergency sys.

    SciTech Connect (OSTI)

    Ahola, E.L.

    1996-09-30T23:59:59.000Z

    Disposition of Observations 6-17, 6-18, 6-22 of Site Electrical Assessment Report. Application of generator differential protection, and synchro-check relay rewiring for generators of building 3621-D. In 1990, the WHC Site Electrical Task Group issued a Site Electrical Assessment Report, ``300 Area Powerhouse and Emergency System.`` This report included numerous findings and observations relating to observed deficiencies or opportunities for improvement in maintenance of the inspected electrical systems. The purpose of this letter report is to provide an evaluation and proposed disposition of Observations No. 6-1 7, 6-1 8, and 6-22 of the Site Electrical Assessment Report.

  5. Hanna, Wyoming underground coal gasification data base. Volume 1. General information and executive summary

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation. This report covers: (1) history of underground coal gasification leading to the Hanna tests; (2) area characteristics (basic meteorological and socioeconomic data); (3) site selection history; (4) site characteristics; (5) permitting; and (6) executive summary. 5 figs., 15 tabs.

  6. Design and Analysis of Salmonid Tagging Studies in the Columbia Basin : Evaluating Wetland Restoration Projects in the Columbia River Estuary using Hydroacoustic Telemetry Arrays to Estimate Movement, Survival, and Residence Times of Juvenile Salmonids, Volume XXII (22).

    SciTech Connect (OSTI)

    Perry, Russell W.; Skalski, John R.

    2008-08-01T23:59:59.000Z

    Wetlands in the Columbia River estuary are actively being restored by reconnecting these habitats to the estuary, making more wetland habitats available to rearing and migrating juvenile salmon. Concurrently, thousands of acoustically tagged juvenile salmonids are released into the Columbia River to estimate their survival as they migrate through the estuary. Here, we develop a release-recapture model that makes use of these tagged fish to measure the success of wetland restoration projects in terms of their contribution to populations of juvenile salmon. Specifically, our model estimates the fraction of the population that enter the wetland, survival within the wetland, and the mean residence time of fish within the wetland. Furthermore, survival in mainstem Columbia River downstream of the wetland can be compared between fish that remained the mainstem and entered the wetland. These conditional survival estimates provide a means of testing whether the wetland improves the subsequent survival of juvenile salmon by fostering growth or improving their condition. Implementing such a study requires little additional cost because it takes advantage of fish already released to estimate survival through the estuary. Thus, such a study extracts the maximum information at minimum cost from research projects that typically cost millions of dollars annually.

  7. Closeout of the Melton Valley Completion Project at the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Bonilla, R.; Johnson, Ch. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Skinner, R. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States); Adams, V. [U.S. DOE, Office of Groundwater and Soil Remediation, Washington, DC (United States)

    2008-07-01T23:59:59.000Z

    The U.S. Department of Energy DOE Order 413.3A (Program and Project Management for the Acquisition of Capital Assets) identifies major milestones in a project life cycle that require approval upon achievement, including Critical Decision-4 (CD-4), the project completion milestone. A CD-4 document is required for all DOE projects in accordance with DOE Order 413.3A, Program and Project Management for Acquisition of Capital Assets. A conditional CD-4 report was prepared for the Melton Valley Completion Project (MVCP) in order to document the completion of the remedial action in the Melton Valley watershed. Approval of the MVCP CD-4 was 'conditional' pending final resolution of a small quantity of unexpected pyrophoric material, with no current disposition pathway, remaining in one of the waste trenches that were to be remediated as part of the completion project. This paper will provide an overview of the MVCP remediation work and the process successfully used to demonstrate closeout of a major CERCLA project in accordance with DOE requirements. In summary: The MV ROD was planned to be completed in 12 years; however, under the ACP the remedial activities were completed 6 years ahead of schedule (September 2006). Highlights of the remedial actions include: - Completion of remedial action activities at 219 release sites identified in the MV ROD. - Construction of 58 hectares of multilayer caps for SWSA 4, SWSA 5, SWSA 6, Pits 2, 3 and 4 and Trenches 5, 6, and 7; - Complete excavation, retrieval and over-pack of 204 casks, 8 boxes, and 530 m{sup 3} of loose waste from the TRU waste retrieval project; - Complete demolition and disposition of approx. 557 m{sup 2} of various buildings such as HRE ancillary facilities, NHF, Liquid LLW pumping stations, 7841 Scrap Yard, misc. storage buildings, and well P and A; - Removal of LLW sludges and stabilization of T-1, T-2, and HFIR tanks; - In situ grouting/stabilization of approx. 12 km of inactive waste pipelines; - Excavation and disposition of approx. 38,000 m{sup 3} of soil from HFIR impoundments, HRE cryogenic pond, IHP and contaminated soil from miscellaneous leak sites; - Completion of in-situ grouting of LLLW matrix at Trenches 5 and 7. The CD-4 document to demonstrate attainment of the project completion milestone was prepared to document close-out activities. Approval of the MVCP CD-4 was obtained but deemed 'conditional' pending final resolution of a small quantity of unexpected pyrophoric material, with no current disposition pathway, remaining in Trench 13 of the 22 Trench Area in SWSA 5N. DOE is currently evaluating options for the final disposition of this material and has committed to resolution of the issue by the end of Fiscal Year 2008. At that time, all aspects of the Melton Valley Completion Project will be complete. (authors)

  8. Northeast corridor improvement project draft environmental impact statement/report for electrification of Northwest Corridor, New Haven, CT. To Boston, MA. Volume 1. Final report, September 1992-September 1993

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The impacts of extending electrification on the National Railroad Passenger Corporation's (Amtrak) Northeast Corridor (NEC) from New Haven, Connecticut to Boston, Massachusetts are of direct concern to the Federal Railroad Administration (FRA). To improve rail service and increase ridership between New York and Boston, Amtrak proposes the electrification of the NEC main line between New Haven, CT and Boston, MA using an overhead 2 X 25,000 volt - 60 hertz power system. This volume considers impacts on the Human and Natural Environment utilizing guidance as outlined in CFR Part 1500, Council on Environmental Quality, Regulations for Implementing the Procedural Requirements of NEPA as amended and the Massachusetts Environmental Policy Act (MEPA) regulations (301 CMR 11:00). Impacts analyzed include changes in the natural environment (air quality, noise and vibration, energy, electromagnetic fields, natural resources, hazardous materials and visual/aesthetics), changes in the social environment (land use and recreation, transportation and traffic), impacts on historic and archaeological sites, changes in transit service and patronage, associated changes in highway and airport congestion, capital costs, operating and maintenance costs, and financial implications. Impacts are identified both for the proposed construction period and for the long-term operation of the alternatives.

  9. Disposition of smoked cannabis with high {Delta}{sup 9}-tetrahydrocannabinol content: A kinetic model

    SciTech Connect (OSTI)

    Hunault, Claudine C., E-mail: claudine.hunault@rivm.n [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Eijkeren, Jan C.H. van [Expertise Center for Methodology and Information Services, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Mensinga, Tjeert T. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Clinic for treatment of drug addiction in Northern, Vondellaan 71-73, 9721 LB, Groningen (Netherlands); Vries, Irma de [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Leenders, Marianne E.C. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division of Perioperative and Emergency Care, University Medical Center Utrecht, 3584 CX (Netherlands); Meulenbelt, Jan [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division Intensive Care Center, University Medical Center Utrecht, 3584 CX, Utrecht (Netherlands); Institute for Risk Assessment Sciences, Utrecht University, Utrecht (Netherlands)

    2010-08-01T23:59:59.000Z

    Introduction: No model exists to describe the disposition and kinetics of inhaled cannabis containing a high THC dose. We aimed to develop a kinetic model providing estimates of the THC serum concentrations after smoking cannabis cigarettes containing high THC doses (up to 69 mg THC). Methods: Twenty-four male non-daily cannabis users smoked cannabis cigarettes containing 29.3 mg, 49.1 mg, and 69.4 mg THC. Blood samples were collected over a period of 0-8 h and serum THC concentrations were measured. A two-compartment open model was fitted on the individual observed data. Results: Large inter-individual variability was observed in the pharmacokinetic parameters. The median pharmacokinetic parameters generated by the model were C{sub max} = 175 ng/mL, T{sub max} = 14 min, and AUC{sub 0-8h} = 8150 ng x min/mL for the 69.4 mg THC dose. Median model results show an almost linear dose response relation for C{sub max}/Dose = 2.8 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 136 x 10{sup -6} min/mL. However, for increasing dose level, there was a clear decreasing trend: C{sub max}/Dose = 3.4, 2.6 and 2.5 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 157, 133 and 117 x 10{sup -6} min/mL for the 29.3, 49.1 and 69.4 mg dose, respectively. Within the restriction of 8 h of observation, the apparent terminal half life of THC was 150 min. Conclusion: The model offers insight into the pharmacokinetics of THC in recreational cannabis users smoking cannabis containing high doses of THC mixed with tobacco. The model is an objective method for providing serum THC concentrations up to 8 h after smoking cannabis with a high THC content (up to 23%).

  10. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    SciTech Connect (OSTI)

    Shropshire, D.E.; Herring, J.S.

    2004-10-03T23:59:59.000Z

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim storage, packaging, transportation, waste forms, waste treatment, decontamination and decommissioning issues; and low-level waste (LLW) and high-level waste (HLW) disposal.

  11. The U.S.-Russian joint studies on using power reactors to disposition surplus weapon plutonium as spent fuel

    SciTech Connect (OSTI)

    Chebeskov, A.; Kalashnikov, A. [State Scientific Center, Obninsk (Russian Federation). Inst. of Physics and Power Engineering; Bevard, B.; Moses, D. [Oak Ridge National Lab., TN (United States); Pavlovichev, A. [State Scientific Center, Moscow (Russian Federation). Kurchatov Inst.

    1997-09-01T23:59:59.000Z

    In 1996, the US and the Russian Federation completed an initial joint study of the candidate options for the disposition of surplus weapons plutonium in both countries. The options included long term storage, immobilization of the plutonium in glass or ceramic for geologic disposal, and the conversion of weapons plutonium to spent fuel in power reactors. For the latter option, the US is only considering the use of existing light water reactors (LWRs) with no new reactor construction for plutonium disposition, or the use of Canadian deuterium uranium (CANDU) heavy water reactors. While Russia advocates building new reactors, the cost is high, and the continuing joint study of the Russian options is considering only the use of existing VVER-1000 LWRs in Russia and possibly Ukraine, the existing BN-60O fast neutron reactor at the Beloyarsk Nuclear Power Plant in Russia, or the use of the Canadian CANDU reactors. Six of the seven existing VVER-1000 reactors in Russia and the eleven VVER-1000 reactors in Ukraine are all of recent vintage and can be converted to use partial MOX cores. These existing VVER-1000 reactors are capable of converting almost 300 kg of surplus weapons plutonium to spent fuel each year with minimum nuclear power plant modifications. Higher core loads may be achievable in future years.

  12. Spent Nuclear Fuel Project FY 1996 Multi-Year Program Plan WBS No. 1.4.1, Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-09-01T23:59:59.000Z

    This document describes the Spent Nuclear Fuel (SNF) Project portion of the Hanford Strategic Plan for the Hanford Reservation in Richland, Washington. The SNF Project was established to evaluate and integrate the urgent risks associated with N-reactor fuel currently stored at the Hanford site in the K Basins, and to manage the transfer and disposition of other spent nuclear fuels currently stored on the Hanford site. An evaluation of alternatives for the expedited removal of spent fuels from the K Basin area was performed. Based on this study, a Recommended Path Forward for the K Basins was developed and proposed to the U.S. DOE.

  13. Computer News, Volume 21

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 21. I came, I saw, ical. There's a great new calendar and appointment book program on our system called ical at.

  14. Computer News, Volume 1

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 1. You and your .cshrc file. Click on RELOAD now. This page is frequently updated and you might be looking at an old ...

  15. Computer News, Volume 36

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 36. Click on RELOAD now. This page is frequently updated and you might be looking at an old version saved by your ...

  16. Computer News, Volume 19

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 19. Those damned attachments! I explain here how to extract and decode e-mail attachments of various kinds. Click on ...

  17. Computer News, Volume 8

    E-Print Network [OSTI]

    [mandelbrot set] MATH DEPT Computer News, Volume 8. A convenient way to do e-mail from home. by guest columnist, Donu Arapura ...

  18. Computer News, Volume 20

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 20. You and your .forward file. Let's say your name is Steven Bellisandagorapahockey and your login id on math is sbellis ...

  19. Computer News, Volume 37

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 37. Click on RELOAD now. This page is frequently updated and you might be looking at an old version saved by your ...

  20. Computer News, Volume 13

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 13. How to dork your official classlist. Click on RELOAD now. This page is frequently updated and you might be looking at ...

  1. Computer News, Volume 15

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 15. How to gain access to Mathematica on a math dept SUN. Click on RELOAD now. This page is frequently updated and ...

  2. Computer News, Volume 34

    E-Print Network [OSTI]

    [mandelbrot set] MATH DEPT Computer News, Volume 34. Click on RELOAD now. This page is frequently updated and you might be looking at an old version

  3. Computer News, Volume 33

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 33. How I teach big calculus lectures with a tablet PC. Click on RELOAD now. This page is frequently updated and you ...

  4. Computer News, Volume 12

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 12. Quick and dirty math on the internet. Click on RELOAD now. This page is frequently updated and you might be ...

  5. Computer News, Volume 38

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 38. Click on RELOAD now. This page is frequently updated and you might be looking at an old version saved by your ...

  6. Computer News, Volume 27

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 27. How to approve Plans of Study on the web. First, make sure you know your Purdue Career Account Login and ...

  7. Computer News, Volume 4

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 4. Xess, the spreadsheet. Click on RELOAD now. This page is frequently updated and you might be looking at an old ...

  8. Computer News, Volume 2

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 2. How to add acroread and distill to your path. Click on RELOAD now. This page is frequently updated and you might be ...

  9. Computer News, Volume 35

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 34. Click on RELOAD now. This page is frequently updated and you might be looking at an old version saved by your ...

  10. Computer News, Volume 32

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 32. The new TeX and how to create the new PU Math letterhead stationery. with help from Brad Lucier, Rodrigo Bañuelos

  11. Computer News, Volume 39

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 39. Click on RELOAD now. This page is frequently updated and you might be looking at an old version saved by your ...

  12. Computer News, Volume 23

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 23. How to view e-mail formatted in HTML originating from the web. Click on RELOAD now. This page is frequently ...

  13. Prime Supplier Sales Volumes

    Gasoline and Diesel Fuel Update (EIA)

    Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State 356 Energy Information Administration Petroleum Marketing Annual 1996 Table 48. Prime...

  14. Prime Supplier Sales Volumes

    Gasoline and Diesel Fuel Update (EIA)

    Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State 356 Energy Information Administration Petroleum Marketing Annual 1997 Table 48. Prime...

  15. LANL Volume 2_Final

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

    42 LANL * Consider developing programmatic evaluation criteria based on the October 1999 draft of Volume VI, Emergency Management Evaluations, of the DOE emergency...

  16. Finite Volume Element Method

    E-Print Network [OSTI]

    2003-12-06T23:59:59.000Z

    FVE is closely related to the control volume finite element method ... simple stencils, to apply to a fairly wide range of fluid flow equations, to effectively treat.

  17. Project Manager

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as a project manager in the Fuel Cell Technologies Office in the DOE-EERE Office of Transportation responsible for a wide variety of highly...

  18. RENOTER Project

    Broader source: Energy.gov [DOE]

    Overview of French project on thermoelectric waste heat recovery for cars and trucks with focus on cheap, available, efficient, and sustainable TE materials, as well as efficient material integration and production process.

  19. INCIDENT # CHARGE SECTION OF NYS PENAL LAW DISPOSITION TYPE REPORTED TO PLACE OF OCCURRENCE DATE & TIME OF OCCURRENCE DATE & TIME REPORTED 1304224 None

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

    INCIDENT # CHARGE SECTION OF NYS PENAL LAW DISPOSITION TYPE REPORTED TO PLACE OF OCCURRENCE DATE Public Safety Department Music Building 6442 Kissena Blvd., Flushing, NY 11367 April 29, 2013 2:15PM Building 6660 Kissena Blvd., Flushing, NY 11367 May 1, 2013 12:15PM May 1, 2013 2:50PM 1305279 None Petit

  20. Math 13900 Pyramid Project After Lesson 32 Name: Class time ...

    E-Print Network [OSTI]

    User

    2014-08-19T23:59:59.000Z

    Pyramid Project. After Lesson 32. 2014 ... Use the information you have and what you have learned in Math 13900 to find the volume. Do not use a formula from ...

  1. Far-Field Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Form

    SciTech Connect (OSTI)

    J.P. Nicot

    2000-09-29T23:59:59.000Z

    The objective of this calculation is to estimate the quantity of fissile material that could accumulate in fractures in the rock beneath plutonium-ceramic (Pu-ceramic) and Mixed-Oxide (MOX) waste packages (WPs) as they degrade in the potential monitored geologic repository at Yucca Mountain. This calculation is to feed another calculation (Ref. 31) computing the probability of criticality in the systems described in Section 6 and then ultimately to a more general report on the impact of plutonium on the performance of the proposed repository (Ref. 32), both developed concurrently to this work. This calculation is done in accordance with the development plan TDP-DDC-MD-000001 (Ref. 9), item 5. The original document described in item 5 has been split into two documents: this calculation and Ref. 4. The scope of the calculation is limited to only very low flow rates because they lead to the most conservative cases for Pu accumulation and more generally are consistent with the way the effluent from the WP (called source term in this calculation) was calculated (Ref. 4). Ref. 4 (''In-Drift Accumulation of Fissile Material from WPs Containing Plutonium Disposition Waste Forms'') details the evolution through time (breach time is initial time) of the chemical composition of the solution inside the WP as degradation of the fuel and other materials proceed. It is the chemical solution used as a source term in this calculation. Ref. 4 takes that same source term and reacts it with the invert; this calculation reacts it with the rock. In addition to reactions with the rock minerals (that release Si and Ca), the basic mechanisms for actinide precipitation are dilution and mixing with resident water as explained in Section 2.1.4. No other potential mechanism such as flow through a reducing zone is investigated in this calculation. No attempt was made to use the effluent water from the bottom of the invert instead of using directly the effluent water from the WP. This calculation supports disposal criticality analysis and has been prepared in accordance with AP-3.12Q, Calculations (Ref. 49). This calculation uses results from Ref. 4 on actinide accumulation in the invert and more generally does reference heavily the cited calculation. In addition to the information provided in this calculation, the reader is referred to the cited calculation for a more thorough treatment of items applying to both the invert and fracture system such as the choice of the thermodynamic database, the composition of J-13 well water, tuff composition, dissolution rate laws, Pu(OH){sub 4} solubility and also for details on the source term composition. The flow conditions (seepage rate, water velocity in fractures) in the drift and the fracture system beneath initially referred to the TSPA-VA because this work was prepared before the release of the work feeding the TSPA-SR. Some new information feeding the TSPA-SR has since been included. Similarly, the soon-to-be-qualified thermodynamic database data0.ymp has not been released yet.

  2. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.

    2013-09-19T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  3. Final Environmental Assessment and Finding of No Significant Impact: Waste Disposition Activities at the Paducah Site Paducah, Kentucky

    SciTech Connect (OSTI)

    N /A

    2002-11-05T23:59:59.000Z

    The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment with in the context of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement is not necessary, and DOE is issuing this Finding of No Significant Impact (FONSI).

  4. Cloudnet Project

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

    Hogan, Robin

    Cloudnet is a research project supported by the European Commission. This project aims to use data obtained quasi-continuously for the development and implementation of cloud remote sensing synergy algorithms. The use of active instruments (lidar and radar) results in detailed vertical profiles of important cloud parameters which cannot be derived from current satellite sensing techniques. A network of three already existing cloud remote sensing stations (CRS-stations) will be operated for a two year period, activities will be co-ordinated, data formats harmonised and analysis of the data performed to evaluate the representation of clouds in four major european weather forecast models.

  5. System analysis of shallow land burial. Volume 2: technical background. Technical report, 26 November 1979-23 January 1981

    SciTech Connect (OSTI)

    Lester, D.; Buckley, D.; Donelson, S.; Dura, V.; Hecht, M.

    1981-03-01T23:59:59.000Z

    This is volume two of a three volume set detailing the activities and results of the System Analysis of Shallow Land Burial Project. Activities under four project tasks are described: Task 1 - Identify Potential Radionuclide Release Pathways, Task 2 - Systems Model for Shallow Land Burial of Low-Level Waste, Task 3 - Sensitivity and Optimization Study and Task 4 - Reference Facility Dose Assessment.

  6. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    SciTech Connect (OSTI)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15T23:59:59.000Z

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

  7. Spent Nuclear Fuel project, project management plan

    SciTech Connect (OSTI)

    Fuquay, B.J.

    1995-10-25T23:59:59.000Z

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  8. Volume dependence of light hadron masses in full lattice QCD

    E-Print Network [OSTI]

    B. Orth; T. Lippert; K. Schilling

    2003-09-15T23:59:59.000Z

    The aim of the GRAL project is to simulate full QCD with standard Wilson fermions at light quark masses on small to medium-sized lattices and to obtain infinite-volume results by extrapolation. In order to establish the functional form of the volume dependence we study systematically the finite-size effects in the light hadron spectrum. We give an update on the status of the GRAL project and show that our simulation data for the light hadron masses depend exponentially on the lattice size.

  9. ERIS Project 

    E-Print Network [OSTI]

    Hunter, Philip

    repositories. If these (generally) smaller institutions wished to continue to have access to these hosted repository spaces after the end of the project, it was proposed that these repository-lite services would be administered by the SDLC (the Scottish Digital...

  10. BLENDING STUDY FOR SRR SALT DISPOSITION INTEGRATION: TANK 50H SCALE-MODELING AND COMPUTER-MODELING FOR BLENDING PUMP DESIGN, PHASE 2

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Fowley, M.

    2011-05-26T23:59:59.000Z

    The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where 300,000-800,000 gallons of salt solution will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. Blending requires the miscible salt solutions from potentially multiple source tanks per batch to be well mixed without disturbing settled sludge solids that may be present in a Blend Tank. Disturbing solids may be problematic both from a feed quality perspective as well as from a process safety perspective where hydrogen release from the sludge is a potential flammability concern. To develop the necessary technical basis for the design and operation of blending equipment, Savannah River National Laboratory (SRNL) completed scaled blending and transfer pump tests and computational fluid dynamics (CFD) modeling. A 94 inch diameter pilot-scale blending tank, including tank internals such as the blending pump, transfer pump, removable cooling coils, and center column, were used in this research. The test tank represents a 1/10.85 scaled version of an 85 foot diameter, Type IIIA, nuclear waste tank that may be typical of Blend Tanks used in SDI. Specifically, Tank 50 was selected as the tank to be modeled per the SRR, Project Engineering Manager. SRNL blending tests investigated various fixed position, non-rotating, dual nozzle pump designs, including a blending pump model provided by the blend pump vendor, Curtiss Wright (CW). Primary research goals were to assess blending times and to evaluate incipient sludge disturbance for waste tanks. Incipient sludge disturbance was defined by SRR and SRNL as minor blending of settled sludge from the tank bottom into suspension due to blending pump operation, where the sludge level was shown to remain constant. To experimentally model the sludge layer, a very thin, pourable, sludge simulant was conservatively used for all testing. To experimentally model the liquid, supernate layer above the sludge in waste tanks, two salt solution simulants were used, which provided a bounding range of supernate properties. One solution was water (H{sub 2}O + NaOH), and the other was an inhibited, more viscous salt solution. The research performed and data obtained significantly advances the understanding of fluid mechanics, mixing theory and CFD modeling for nuclear waste tanks by benchmarking CFD results to actual experimental data. This research significantly bridges the gap between previous CFD models and actual field experiences in real waste tanks. A finding of the 2009, DOE, Slurry Retrieval, Pipeline Transport and Plugging, and Mixing Workshop was that CFD models were inadequate to assess blending processes in nuclear waste tanks. One recommendation from that Workshop was that a validation, or bench marking program be performed for CFD modeling versus experiment. This research provided experimental data to validate and correct CFD models as they apply to mixing and blending in nuclear waste tanks. Extensive SDI research was a significant step toward bench marking and applying CFD modeling. This research showed that CFD models not only agreed with experiment, but demonstrated that the large variance in actual experimental data accounts for misunderstood discrepancies between CFD models and experiments. Having documented this finding, SRNL was able to provide correction factors to be used with CFD models to statistically bound full scale CFD results. Through the use of pilot scale tests performed for both types of pumps and available engineering literature, SRNL demonstrated how to effectively apply CFD results to salt batch mixing in full scale waste tanks. In other words, CFD models were in error prior to development of experimental correction factors determined during this research, which provided a technique to use CFD models fo

  11. WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,

    E-Print Network [OSTI]

    Minimization/ Volume Reduction 0 Solid Radioactive Waste $2,168 $0 $2,168 Vial Crusher for glass vialsWASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED, REUSED, RECYCLED OR CONSERVED IN 2004 WASTE TYPE DESCRIPTION DETAILS * Automotive Waste Substitution 510 Hazardous Waste $1,020 $1,000 $1,000 Aqueous Solvent

  12. WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,

    E-Print Network [OSTI]

    labeled chemicals Waste Minimization/ Volume Reduction 0 Solid Radioactive Waste $2,168 $3,795 $2,168 VialWASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED, REUSED, RECYCLED OR CONSERVED IN 2003 WASTE TYPE DESCRIPTION DETAILS * Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste

  13. NAVFAC Ocean Thermal Energy Conversion (OTEC) Project

    E-Print Network [OSTI]

    NAVFAC Ocean Thermal Energy Conversion (OTEC) Project Contract Number N62583-09-C-0083 CDRL A014 OTEC Mini-Spar Pilot Plant 9 December 2011 OTEC-2011-001-4 Prepared for: Naval Facilities; distribution is unlimited. #12; Configuration Report and Development Plan Volume 4 Site Specific OTEC

  14. Computer News, Volume 29

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 29. How to update your login shell from csh to tcsh. If you, like me, have had an account on the Math network of SUNs ...

  15. Computer News, Volume 30

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 30. How to create an ASCII version of the Purdue Logo and other matters of e-mail etiquette. The Purdue logo... ... ah, yes ...

  16. Computer News, Volume 26

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 26. How to trim an e-mail alias. The faculty e-mail alias has a lot more people on it than you might imagine. (To find out ...

  17. Computer News, Volume 7

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 7. How to put figures in TeX. (I assume that you are using X windows on or from a math dept SUN.) To make a figure, I use ...

  18. Computer News, Volume 31

    E-Print Network [OSTI]

    MATH DEPT Computer News, Volume 31. How to create .pdf files from TeX. by Donu Arapura. Click on RELOAD now. This page is frequently updated and you ...

  19. Imaging using volume holograms

    E-Print Network [OSTI]

    Sinha, Arnab, 1978-

    2004-01-01T23:59:59.000Z

    Volume holograms can be thought of as self-aligned 3D stacks of diffractive elements that operate coherently on incident fields as they propagate through the structure. In this thesis, we propose, design and implement ...

  20. Modeling the Syn Disposition of Nitrogen Donors in Non-Heme Diiron Enzymes. Synthesis, Characterization, and Hydrogen Peroxide Reactivity of Diiron(III) Complexes with the Syn N-Donor Ligand H[subscript 2]BPG[subscript 2]DEV

    E-Print Network [OSTI]

    Friedle, Simone

    In order to model the syn disposition of histidine residues in carboxylate-bridged non-heme diiron enzymes, we prepared a new dinucleating ligand, H[subscript 2]BPG[subscript 2]DEV, that provides this geometric feature. ...

  1. Chemical Safety Vulnerability Working Group report. Volume 3

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports.

  2. Project Fact Sheet Project Brief

    E-Print Network [OSTI]

    Name: Centre for Assisted Robotic Surgery Number: BESS1002b Project Champion: Professor Guang-Zong Yang of the refurbishment is to renew and expand the laboratory space for Robotic Assisted Surgery at the South Kensington Campus as par to the Hamlyn Centre for Robotic Surgery. The overall programme incorpo- rates both core

  3. Natural Propagation and Habitat Improvement, Volume I, Oregon, 1984 Final and Annual Reports.

    SciTech Connect (OSTI)

    Miller, Rod

    1986-02-01T23:59:59.000Z

    This volume contains reports on habitat improvement and fisheries enhancement projects conducted in the following subbasins: (1) Clackamas River; (2) Hood River; :(3) Deschutes River; (4) John Day River; (5) Umatilla River; and (6) Grande Ronde River. (ACR)

  4. Direct Forcing Immersed Boundary Methods: Finite Element Versus Finite Volume Approach

    E-Print Network [OSTI]

    Frisani, Angelo 1980-

    2012-12-07T23:59:59.000Z

    Two immersed boundary methods (IBM) for the simulation of conjugate heat transfer problems with complex geometries are introduced: a finite element (IFEM) and a finite volume (IFVM) immersed boundary methods are discussed. In the IFEM a projection...

  5. Liquefied natural gas as a transportation fuel for heavy-duty trucks: Volume I

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    This document contains Volume 1 of a three-volume manual designed for use with a 2- to 3-day liquefied natural gas (LNG) training course. Transportation and off-road agricultural, mining, construction, and industrial applications are discussed. This volume provides a brief introduction to the physics and chemistry of LNG; an overview of several ongoing LNG projects, economic considerations, LNG fuel station technology, LNG vehicles, and a summary of federal government programs that encourage conversion to LNG.

  6. Portsmouth Proposed Plan for the Site-wide Waste Disposition Evaluation

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreakingMay 2015 < prev next > Sun Mon Tue Wed Thu Fri Sat 26 27 28Project |

  7. EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany

    Broader source: Energy.gov [DOE]

    This environmental assessment (EA) will evaluate the potential environmental impacts of a DOE proposal to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition. This used nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear reactors used for research and development purposes.

  8. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    SciTech Connect (OSTI)

    Bunch, Kyle J. [United States Department of State, Bureau of Arms Control, Verification and Compliance, Office of Verification and Transparency Technologies, Washington, DC (United States); Jones, Anthony M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Benz, Jacob M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Denlinger, Laura Schmidt [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

    2014-05-04T23:59:59.000Z

    The ratification and ongoing implementation of the New START Treaty have been widely regarded as noteworthy global security achievements for both the Obama Administration and the Putin (formerly Medvedev) regime. But deeper cuts that move beyond the United States and Russia to engage the P-5 and other nuclear weapons possessor states are envisioned under future arms control regimes, and are indeed required for the P-5 in accordance with their Article VI disarmament obligations in the Nuclear Non-Proliferation Treaty. Future verification needs will include monitoring the cessation of production of new fissile material for weapons, monitoring storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondary stages, and other materials. A fundamental challenge to implementing a nuclear disarmament regime is the ability to thwart unauthorized material diversion throughout the dismantlement and disposition process through strong chain of custody implementation. Verifying the declared presence, or absence, of nuclear materials and weapons components throughout the dismantlement and disposition lifecycle is a critical aspect of the disarmament process. From both the diplomatic and technical perspectives, verification under these future arms control regimes will require new solutions. Since any acceptable verification technology must protect sensitive design information and attributes to prevent the release of classified or other proliferation-sensitive information, non-nuclear non-sensitive modalities may provide significant new verification tools which do not require the use of additional information barriers. Alternative verification technologies based upon electromagnetic and acoustics could potentially play an important role in fulfilling the challenging requirements of future verification regimes. For example, researchers at the Pacific Northwest National Laboratory (PNNL) have demonstrated that low frequency electromagnetic signatures of sealed metallic containers can be used to rapidly confirm the presence of specific components on a yes/no basis without revealing classified information. PNNL researchers have also used ultrasonic measurements to obtain images of material microstructures which may be used as templates or unique identifiers of treaty-limited items. Such alternative technologies are suitable for application in various stages of weapons dismantlement and often include the advantage of an inherent information barrier due to the inability to extract classified weapon design information from the collected data. As a result, these types of technologies complement radiation-based verification methods for arms control. This article presents an overview of several alternative verification technologies that are suitable for supporting a future, broader and more intrusive arms control regime that spans the nuclear weapons disarmament lifecycle. The general capabilities and limitations of each verification modality are discussed and example technologies are presented. Potential applications are defined in the context of the nuclear material and weapons lifecycle. Example applications range from authentication (e.g., tracking and signatures within the chain of custody from downloading through weapons storage, unclassified templates and unique identification) to verification of absence and final material disposition.

  9. Solid waste operations complex W-113: Preliminary design report. Volume I

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    This document is Volume I of a Preliminary Design Report (Title I) for the Solid Waste Retrieval Facilities-Phase I (Project W-113) at Hanford. It was prepared by Raytheon and BNFL Inc. and submitted to Westinghouse Hanford Company in January 1995. This volume provides a project overview and a discussion of the waste handling systems, the data acquisition and control systems, the building systems, and the site/building structure.

  10. PROJECT SUMMARY

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferAprilOverviewEfficiencyofHSSPIAProperty Management PlanPROJECT SUMMARY 1

  11. Hallmark Project

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaefer To: CongestionDevelopmentHEADQUARTERSOutreachApril 23, 2013Project

  12. Project Management

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENA creates

  13. Project Overview

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENAManagement

  14. Projects | ORNL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeedingTechnical News,Program DirectionProject ATHENAManagementIn ThisPages

  15. Project Gnome

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg MercuryProject Final Report: HPC-Colony IIProject Gnome

  16. Project Title

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg MercuryProject FinalFluids |Storage Research and

  17. NEPA COMPLIANCE SURVEY Project Information Project Title:

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

    Boxes Date: Nov. 11 , 2010 DOE Code: 6740.010.00000 Contractor Code: 8067-451 Project Lead: Anthony Bowler Project Overview 1. Brief project description include anything that...

  18. Giannini Reporter, Volume 21

    E-Print Network [OSTI]

    2009-01-01T23:59:59.000Z

    of Climate Change on China’s Agriculture. ” AgriculturalFuture Climate Change Impacts on Water for Agriculture andAgriculture Using Probabilistic Projections of Climate Change,

  19. 1988 DOE model conference proceedings: Volume 4

    SciTech Connect (OSTI)

    Not Available

    1988-01-01T23:59:59.000Z

    These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics discussed in Volume 4 include site characterization and remediation projects, environmental monitoring and modeling; disposal site selection and facility design, risk assessment, safety and health issues, and site remediation technology.

  20. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    Hundreds of aging nuclear materials processing facilities within the Department of Energy`s (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D&D) program for DOE`s nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE`s technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D&D services.