National Library of Energy BETA

Sample records for draft surplus plutonium

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

    SciTech Connect (OSTI)

    N /A

    1999-05-14

    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.

  2. 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.

  3. Surplus Plutonium Disposition Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    1999-11-19

    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.

  4. CHARACTERIZATION OF SURPLUS PLUTONIUM FOR DISPOSITION OPTIONS

    SciTech Connect (OSTI)

    Allender, J; Edwin Moore, E; Scott Davies, S

    2008-07-15

    The United States (U.S.) 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. Except for materials that remain in use for programs outside of national defense, including programs for nuclear-energy development, the 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. Some items will be disposed as transuranic waste, low-level waste, or spent fuel. The remaining surplus plutonium will be managed through: (1) the Mixed Oxide (MOX) Fuel Fabrication Facility (FFF), to be constructed at the Savannah River Site (SRS), where the plutonium will be converted to fuel that will be irradiated in civilian power reactors and later disposed to a high-level waste (HLW) repository as spent fuel; (2) the SRS H-Area facilities, by dissolving and transfer to HLW systems, also for disposal to the repository; or (3) alternative immobilization techniques that would provide durable and secure disposal. From the beginning of the U.S. program for surplus plutonium disposition, DOE has sponsored research to characterize the surplus materials and to judge their suitability for planned disposition options. Because many of the items are stored without extensive analyses of their current chemical content, the characterization involves three interacting components: laboratory sample analysis, if available; non-destructive assay data; and rigorous evaluation of records for the processing history for items and inventory groups. This information is collected from subject-matter experts at inventory sites and from materials stabilization and surveillance programs, in cooperation with the design agencies for the disposition facilities. This report describes the operation and status of the characterization program.

  5. Surplus Plutonium Disposition (SPD) Environmental Data Summary

    SciTech Connect (OSTI)

    Fledderman, P.D.

    2000-08-24

    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.

  6. ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Moore, E.

    2013-07-17

    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.

  7. EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental...

    Energy Savers [EERE]

    program, including changes to the inventory of surplus plutonium and proposed new alternatives. The Final SEIS does not identify a preferred alternative. Once a preferred...

  8. Characterizing surplus US plutonium for disposition

    SciTech Connect (OSTI)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-02-26

    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. 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)

    2013-07-01

    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)

  10. TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION

    SciTech Connect (OSTI)

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

    2013-07-16

    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.

  11. SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP

    SciTech Connect (OSTI)

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

    2012-06-08

    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.

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

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-12-13

    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.

  13. 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

    1998-08-01

    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.

  14. 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

    1997-08-01

    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.

  15. Plutonium destruction in a non-fertile, ZrO{sub 2}-based fuel: A reactor option for disposition of surplus plutonium

    SciTech Connect (OSTI)

    Oversby, V.M. [Lawrence Livermore National Lab., CA (United States); McPheeters, C.C. [Argonne National Lab., IL (United States)

    1996-02-01

    The United States and Russia are assessing options for disposition of surplus weapon-grade plutonium. This paper reviews the options under consideration by the US Department of Energy and suggests an additional option that fits within the framework of the environmental analysis provided in the draft PEIS (Programmatic Environmental Impact Statement). In addition to the burning of Pu in mixed U-Pu oxide fuel, we recommend consideration of a non-fertile fuel based on zirconia with inclusion of rare earth elements for phase stabilization and control of reactivity. The zirconia based fuel could also be used to burn plutonium generated in commercial reactor fuels, which represent a larger inventory of plutonium than the weapon-grade material. The increasing inventories of civilian plutonium potentially represent a larger threat with respect to diversion weapons usable material than the stocks of weapon-grade material considered for disposition by the US and Russia. We discuss the use of zirconia-based fuel and pyrochemical processing of spent commercial reactor fuels as a means of decreasing world-wide plutonium inventories. The experience gained in burning weapon-grade plutonium in the new non-fertile fuel would shorten the time required to gain acceptance of the fuel for commercial reactor use.

  16. 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

    1998-08-01

    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.

  17. Amended Record of Decision: Storage of Surplus Plutonium Materials...

    Office of Environmental Management (EM)

    Notices 1 A container that complies with DOE-STD-3013, Stabilization, Packaging, and Storage of Plutonium- Bearing Materials. 2 The use of FFTF and the unirradiated fuel...

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

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

    period for the Draft Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (EIS). September 1, 2012 dummy image Read our archives Contacts Editor Linda...

  19. 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

    1998-08-01

    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.

  20. 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

    1998-08-01

    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.

  1. EIS-0283-S2: DOE Notice of Availability of the Draft Supplemental...

    Office of Environmental Management (EM)

    Notice of Availability of the Draft Supplemental Environmental Impact Statement Surplus Plutonium Disposition The U. S. Department of Energy (DOE) announces the availability of...

  2. EIS-0283: Notice of Public Hearing on the Supplement to the Draft...

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

    of Public Hearing on the Supplement to the Draft Environmental Impact Statement Surplus Plutonium Disposition The Department of Energy (DOE) announced a public hearing on the...

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

    SciTech Connect (OSTI)

    Wike, L.D.

    2000-08-17

    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.

  4. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1National SHEET Lead Agency: U.S.

  5. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1National SHEET Lead Agency:

  6. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1National SHEET Lead Agency:SHEET Lead

  7. A Methodology for the Analysis and Selection of Alternative for the Disposition of Surplus Plutonium

    SciTech Connect (OSTI)

    NONE

    1999-08-31

    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. 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

    1997-04-04

    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.

  9. Characterization of Representative Materials in Support of Safe, Long Term Storage of Surplus Plutonium in DOE-STD-3013 Containers

    SciTech Connect (OSTI)

    Narlesky, Joshua E.; Stroud, Mary Ann; Smith, Paul Herrick; Wayne, David M.; Mason, Richard E.; Worl, Laura A.

    2013-02-15

    The Surveillance and Monitoring Program is a joint Los Alamos National Laboratory/Savannah River Site effort funded by the Department of Energy-Environmental Management to provide the technical basis for the safe, long-term storage (up to 50 years) of over 6 metric tons of plutonium stored in over 5,000 DOE-STD-3013 containers at various facilities around the DOE complex. The majority of this material is plutonium that is surplus to the nuclear weapons program, and much of it is destined for conversion to mixed oxide fuel for use in US nuclear power plants. The form of the plutonium ranges from relatively pure metal and oxide to very impure oxide. The performance of the 3013 containers has been shown to depend on moisture content and on the levels, types and chemical forms of the impurities. The oxide materials that present the greatest challenge to the storage container are those that contain chloride salts. Other common impurities include oxides and other compounds of calcium, magnesium, iron, and nickel. Over the past 15 years the program has collected a large body of experimental data on 54 samples of plutonium, with 53 chosen to represent the broader population of materials in storage. This paper summarizes the characterization data, moisture analysis, particle size, surface area, density, wattage, actinide composition, trace element impurity analysis, and shelf life surveillance data and includes origin and process history information. Limited characterization data on fourteen nonrepresentative samples is also presented.

  10. LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition

    SciTech Connect (OSTI)

    Bronson, M.C.

    1997-10-01

    The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium.

  11. EIS-0283-S1: Supplement to the Surplus Plutonium Disposition Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    The Supplement evaluates 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...

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

    SciTech Connect (OSTI)

    Allender, J; Moore, E

    2010-07-14

    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.

  13. Supplement Analysis For Disposal of Certain Rocky Flats Plutonium...

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

    discuss the potential impacts from different proposed alternatives for the storage and disposition of surplus plutonium and waste containing surplus plutonium. These EISs...

  14. Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

    SciTech Connect (OSTI)

    Singh, B.K.; Gillette, J.; Jackson, J.

    1994-12-01

    Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ``Decommissioning of US Department of Energy Contaminated Surplus Facilities`` (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning.

  15. Immobilization as a route to surplus fissile materials disposition. Revision 1

    SciTech Connect (OSTI)

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

    1996-03-15

    The safe management of surplus weapons plutonium is a very important and urgent task with profound environmental, national and international security implications. In the aftermath of the Cold War, Presidential Police Directive 13 and various analysis by renown scientific, technical and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths forward for the long term disposition of surplus weapons usable plutonium. The central, overarching goal 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 civilian spent reactor fuel. One disposition alternative considered for surplus Pu is immobilization, in which plutonium would be emplaced in glass, ceramic or glass-bonded zeolite. This option, along with some of the progress over the last year is discussed.

  16. Surplus Plutonium Disposition Supplemental Environmental Impact Statement |

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal ofNational NuclearSite

  17. Plutonium disposition via immobilization in ceramic or glass

    SciTech Connect (OSTI)

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

    1997-03-05

    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.

  18. Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

  19. Process for immobilizing plutonium into vitreous ceramic waste forms

    DOE Patents [OSTI]

    Feng, X.; Einziger, R.E.

    1997-01-28

    Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

  20. Process for immobilizing plutonium into vitreous ceramic waste forms

    DOE Patents [OSTI]

    Feng, X.; Einziger, R.E.

    1997-08-12

    Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

  1. Process for immobilizing plutonium into vitreous ceramic waste forms

    DOE Patents [OSTI]

    Feng, Xiangdong (Richland, WA); Einziger, Robert E. (Richland, WA)

    1997-01-01

    Disclosed is a method for converting spent nuclear fuel and surplus plutonium into a vitreous ceramic final waste form wherein spent nuclear fuel is bound in a crystalline matrix which is in turn bound within glass.

  2. EIS-0283: Notice of Intent to Prepare a Supplement to the Draft...

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

    mixed oxide (MOX) fuel in six specific commercial nuclear reactors at three sites for the disposition of surplus weapons-grade plutonium. DOE identified these reactors through a...

  3. DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 -152 -

    E-Print Network [OSTI]

    DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 - 152 - 4. Inventory of Existing Activities (Private DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 - 153 - Figure 31. Areas in the Lower Middle Snake subbasin;DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 - 154 - 4.2. Existing Plans US Forest Service and Bureau

  4. 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)

    1995-07-23

    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.

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

    E-Print Network [OSTI]

    Gonzalez, Vanessa L

    1998-01-01

    A comprehensive case study was conducted on the policy problem of disposing of U.S. weapons-grade plutonium which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option...

  6. Design-Only Conceptual Design Report: Plutonium Immobilization Plant

    SciTech Connect (OSTI)

    DiSabatino, A.; Loftus, D.

    1999-01-01

    This design-only conceptual design report was prepared to support a funding request by the Department of Energy Office of Fissile Materials Disposition for engineering and design of the Plutonium Immobilization Plant, which will be used to immobilize up to 50 tonnes of surplus plutonium. The siting for the Plutonium Immobilization Plant will be determined pursuant to the site-specific Surplus Plutonium Disposition Environmental Impact Statement in a Plutonium Deposition Record of Decision in early 1999. This document reflects a new facility using the preferred technology (ceramic immobilization using the can-in-canister approach) and the preferred site (at Savannah River). The Plutonium Immobilization Plant accepts plutonium from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into mineral-like forms that are subsequently encapsulated within a large canister of high-level waste glass. The final immobilized product must make the plutonium as inherently unattractive and inaccessible for use in nuclear weapons as the plutonium in spent fuel from commercial reactors and must be suitable for geologic disposal. Plutonium immobilization at the Savannah River Site uses: (1) A new building, the Plutonium Immobilization Plant, which will convert non-pit surplus plutonium to an oxide form suitable for the immobilization process, immobilize plutonium in a titanate-based ceramic form, place cans of the plutonium-ceramic forms into magazines, and load the magazines into a canister; (2) The existing Defense Waste Processing Facility for the pouring of high-level waste glass into the canisters; and (3) The Actinide Packaging and Storage Facility to receive and store feed materials. The Plutonium Immobilization Plant uses existing Savannah River Site infra-structure for analytical laboratory services, waste handling, fire protection, training, and other support utilities and services. The Plutonium Immobilization Plant may share the disposition of the 50 tonnes of plutonium with the mixed oxide fuel/reactor disposition alternative. For this case, immobilization will process 18.2 tonnes of plutonium in 10 years.

  7. DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 -1 -

    E-Print Network [OSTI]

    DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 - 1 - Oregon Side of the Lower Middle Snake Subbasin Plan May 28, 2004 Prepared for the Northwest Power and Conservation Council Lead Writer M. Cathy Nowak of Conservation Districts #12;DRAFT DRAFT DRAFT DRAFT DRAFT DRAFT 5/25/2004 - 2 - Oregon Side of the Lower Middle

  8. Department of Energy Announces Decision to Consolidate Surplus Plutonium in

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electricLaboratory | versionInnovativeStorage of CO2South Carolina |

  9. Analysis of Surplus Weapons-Grade Plutonium Disposition Options | National

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4) AugustA. Geographic TermsOVERVIEWO594-ADD1VisitNuclear

  10. Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia NationalSecurityNuclear SecurityOffices |Security U.S.

  11. Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia NationalSecurityNuclear SecurityOffices |Security U.S.

  12. Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia NationalSecurityNuclear SecurityOffices |Security U.S.of

  13. EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based|Department of5 PeerRecord of DecisionImpact Statement | DepartmentImpact

  14. EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based|Department of5 PeerRecord of DecisionImpact StatementDepartment: Record

  15. Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12, 2015Executive Order14,Energy 9,UNIVERSITY OF TEXAS AT||Solar and Wind

  16. Consolidation of Surplus Plutonium at Savannah River Site | Department of

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electric vehicle (PEV)Day-June 22,FresnoSky)Nuclear8Under the|

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

    SciTech Connect (OSTI)

    Zurn, R.M.

    1997-09-01

    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.

  18. The United States Plutonium Balance, 1944 - 2009

    SciTech Connect (OSTI)

    2012-06-01

    This report updates the report -Plutonium: The first 50 years- which was released by the U.S.Department of Energy (DOE) in 1996. The topic of both reports is plutonium, sometimes referred to as Pu-239, which is capable of sustaining a nuclear chain reaction and is used in nuclear weapons and for nuclear power production. This report updates 1994 data through 2009. The four most significant changes since 1994 include: (a) the completion of cleanup activities at the Rocky Flats Plant in 2005; (b) material consolidation and disposition activities, especially shipments from Hanford to the Savannah River Site; (c) the 2007 declaration of an additional 9.0 MT of weapons grade plutonium to be surplus to defense needs in the coming decades; and (d) the opening of the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in 1999.

  19. THE PLUTONIUM STORY

    E-Print Network [OSTI]

    Seaborg, G.T.

    2010-01-01

    Soc. , The occurrence of plutonium in nature. Mastick, D. F.positive oxidation state of plutonium. G. T. Seaborg, J. J.The first isolation of plutonium J. Am. Chem. Soc. , Fermi,

  20. Plutonium immobilization plant using ceramic in existing facilities at the Savannah River site

    SciTech Connect (OSTI)

    DiSabatino, A., LLNL

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources, and through a ceramic immobilization process converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

  1. EIS-0283-S2: Notice of Extension of Public Review and Comment...

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

    Review and Comment Period and Announcement of an Additional Public Hearing Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement DOE has extended the...

  2. Seaborg's Plutonium ?

    E-Print Network [OSTI]

    Norman, Eric B; Telhami, Kristina E

    2014-01-01

    Passive x-ray and gamma-ray analysis was performed on UC Berkeley's EH&S Sample S338. The object was found to contain Pu-239 and no other radioactive isotopes. The mass of Pu-239 contained in this object was determined to be 2.0 +- 0.3 micrograms. These observations are consistent with the identification of this object being the 2.77-microgram plutonium oxide sample described by Glenn Seaborg and his collaborators as the first sample of Pu-239 that was large enough to be weighed.

  3. Seaborg's Plutonium?

    E-Print Network [OSTI]

    Eric B. Norman; Keenan J. Thomas; Kristina E. Telhami

    2015-02-17

    Passive x-ray and gamma-ray analysis was performed on UC Berkeley's EH&S Sample S338. The object was found to contain Pu-239 and no other radioactive isotopes. The mass of Pu-239 contained in this object was determined to be 2.0 +- 0.3 micrograms. These observations are consistent with the identification of this object being the 2.77-microgram plutonium oxide sample described by Glenn Seaborg and his collaborators as the first sample of Pu-239 that was large enough to be weighed.

  4. Process modeling of plutonium conversion and MOX fabrication for plutonium disposition

    SciTech Connect (OSTI)

    Schwartz, K.L. [Univ. of Texas, Austin, TX (United States). Dept. of Nuclear Engineering

    1998-10-01

    Two processes are currently under consideration for the disposition of 35 MT of surplus plutonium through its conversion into fuel for power production. These processes are the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel. This study was undertaken to determine the optimal size for both facilities, whereby the 35 MT of plutonium metal will be converted into fuel and burned for power. The bounding conditions used were a plutonium concentration of 3--7%, a burnup of 20,000--40,000 MWd/MTHM, a core fraction of 0.1 to 0.4, and the number of reactors ranging from 2--6. Using these boundary conditions, the optimal cost was found with a plutonium concentration of 7%. This resulted in an optimal throughput ranging from 2,000 to 5,000 kg Pu/year. The data showed minimal costs, resulting from throughputs in this range, at 3,840, 2,779, and 3,497 kg Pu/year, which results in a facility lifetime of 9.1, 12.6, and 10.0 years, respectively.

  5. Study 59 - Fed 70WY Surplus Deficit.xls

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

    1049 -305 -225 322 1995 Federal SurplusDeficit 260 -205 -53 142 1931 3119 1491 3318 3012 2668 519 347 1375 1996 Federal SurplusDeficit 1081 2864 3933 4477 3832 4732 4138 5391...

  6. Global plutonium management: A security option

    SciTech Connect (OSTI)

    Sylvester, K.W.B.

    1998-12-31

    The US surplus plutonium disposition program was created to reduce the proliferation risk posed by the fissile material from thousands of retired nuclear weapons. The Department of Energy has decided to process its Put into a form as secure as Pu in civilian spent fuel. While implementation issues have been considered, a major one (Russian reciprocity) remains unresolved. Russia has made disposition action conditional on extracting the fuel value of its Pu but lacks the infrastructure to do so. Assistance in the construction of the required facilities would conflict with official US policy opposing the development of a Pu fuel cycle. The resulting stagnation provides impetus for a reevaluation of US nonproliferation objectives and Pu disposition options. A strategy for satisfying Russian fuel value concerns and reducing the proliferation risk posed by surplus weapons-grade plutonium (WGPu) is proposed. The effectiveness of material alteration (e.g., isotopic, chemical, etc.{hor_ellipsis}) at reducing the desire, ability and opportunity for proliferation is assessed. Virtually all the security benefits attainable by material processing can be obtained by immobilizing Pu in large unit size/mass monoliths without a radiation barrier. Russia would be allowed to extract the Pu at a future date for use as fuel in a verifiable manner. Remote tracking capability, if proven feasible, would further improve safeguarding capability. As an alternate approach, the US could compensate Russia for its Pu, allowing it to be disposed of or processed elsewhere. A market based method for pricing Pu is proposed. Surplus Pu could represent access to nuclear fuel at a fixed price at a future date. This position can be replicated in the uranium market and priced using derivative theory. The proposed strategy attempts to meet nonproliferation objectives by recognizing technical limitations and satisfying political constraints.

  7. 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.

    1997-04-01

    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.

  8. EIS Data Call Report: Plutonium immobilization plant using ceramic in new facilities at the Savannah River Site

    SciTech Connect (OSTI)

    DiSabatino, A.

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

  9. THE PLUTONIUM STORY

    E-Print Network [OSTI]

    Seaborg, G.T.

    2010-01-01

    the bulk of the uranium, as uranyl nitrate hexahydrate, fromto separate large- amounts of uranyl nitrate from plutonium.Plutonium. A sample of uranyl nitrate weighing 1.2 kilograms

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

    SciTech Connect (OSTI)

    Greene, S.R.

    1999-07-17

    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.

  11. TECHNIQUES FOR MONITORING PLUTONIUM IN THE ENVIRONMENT

    E-Print Network [OSTI]

    Nero Jr., A.V.

    2011-01-01

    of Environmental Plutonium and its Related Nuclides," IEEEJ. Koch, and C. T. Schmidt, "Plutonium Survey with an X-RayDetermination of Plutonium," Talanta!! , 215 (1967). C. E.

  12. Plutonium radiation surrogate

    DOE Patents [OSTI]

    Frank, Michael I. (Dublin, CA)

    2010-02-02

    A self-contained source of gamma-ray and neutron radiation suitable for use as a radiation surrogate for weapons-grade plutonium is described. The source generates a radiation spectrum similar to that of weapons-grade plutonium at 5% energy resolution between 59 and 2614 keV, but contains no special nuclear material and emits little .alpha.-particle radiation. The weapons-grade plutonium radiation surrogate also emits neutrons having fluxes commensurate with the gamma-radiation intensities employed.

  13. Plutonium Vulnerability Management Plan

    SciTech Connect (OSTI)

    1995-03-01

    This Plutonium Vulnerability Management Plan describes the Department of Energy`s response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department`s Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B.

  14. Plutonium dissolution process

    DOE Patents [OSTI]

    Vest, Michael A. (Oak Park, IL); Fink, Samuel D. (Aiken, SC); Karraker, David G. (Aiken, SC); Moore, Edwin N. (Aiken, SC); Holcomb, H. Perry (North Augusta, SC)

    1996-01-01

    A two-step process for dissolving plutonium metal, which two steps can be carried out sequentially or simultaneously. Plutonium metal is exposed to a first mixture containing approximately 1.0M-1.67M sulfamic acid and 0.0025M-0.1M fluoride, the mixture having been heated to a temperature between 45.degree. C. and 70.degree. C. The mixture will dissolve a first portion of the plutonium metal but leave a portion of the plutonium in an oxide residue. Then, a mineral acid and additional fluoride are added to dissolve the residue. Alteratively, nitric acid in a concentration between approximately 0.05M and 0.067M is added to the first mixture to dissolve the residue as it is produced. Hydrogen released during the dissolution process is diluted with nitrogen.

  15. 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

    1998-10-01

    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.

  16. Department of Energy Announces Decision to Consolidate Surplus...

    Energy Savers [EERE]

    (MOX) Fuel Fabrication Facility (currently under construction); the existing H-Canyon facility; and the proposed new, small-scale plutonium vitrification capability. DOE will...

  17. Working Draft

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

    Draft SAE Plan June 29, 2015 Page 1 Crude Oil Characteristics Research Sampling, Analysis and Experiment (SAE) Plan The U.S. is experiencing a renaissance in oil and gas...

  18. Lithium metal reduction of plutonium oxide to produce plutonium metal

    DOE Patents [OSTI]

    Coops, Melvin S. (Livermore, CA)

    1992-01-01

    A method is described for the chemical reduction of plutonium oxides to plutonium metal by the use of pure lithium metal. Lithium metal is used to reduce plutonium oxide to alpha plutonium metal (alpha-Pu). The lithium oxide by-product is reclaimed by sublimation and converted to the chloride salt, and after electrolysis, is removed as lithium metal. Zinc may be used as a solvent metal to improve thermodynamics of the reduction reaction at lower temperatures. Lithium metal reduction enables plutonium oxide reduction without the production of huge quantities of CaO--CaCl.sub.2 residues normally produced in conventional direct oxide reduction processes.

  19. Plutonium 239 Equivalency Calculations

    SciTech Connect (OSTI)

    Wen, J

    2011-05-31

    This document provides the basis for converting actual weapons grade plutonium mass to a plutonium equivalency (PuE) mass of Plutonium 239. The conversion can be accomplished by performing calculations utilizing either: (1) Isotopic conversions factors (CF{sub isotope}), or (2) 30-year-old weapons grade conversion factor (CF{sub 30 yr}) Both of these methods are provided in this document. Material mass and isotopic data are needed to calculate PuE using the isotopic conversion factors, which will provide the actual PuE value at the time of calculation. PuE is the summation of the isotopic masses times their associated isotopic conversion factors for plutonium 239. Isotopic conversion factors are calculated by a normalized equation, relative to Plutonium 239, of specific activity (SA) and cumulated dose inhalation affects based on 50-yr committed effective dose equivalent (CEDE). The isotopic conversion factors for converting weapons grade plutonium to PuE are provided in Table-1. The unit for specific activity (SA) is curies per gram (Ci/g) and the isotopic SA values come from reference [1]. The cumulated dose inhalation effect values in units of rem/Ci are based on 50-yr committed effective dose equivalent (CEDE). A person irradiated by gamma radiation outside the body will receive a dose only during the period of irradiation. However, following an intake by inhalation, some radionuclides persist in the body and irradiate the various tissues for many years. There are three groups CEDE data representing lengths of time of 0.5 (D), 50 (W) and 500 (Y) days, which are in reference [2]. The CEDE values in the (W) group demonstrates the highest dose equivalent value; therefore they are used for the calculation.

  20. 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.

  1. Atomic spectrum of plutonium

    SciTech Connect (OSTI)

    Blaise, J.; Fred, M.; Gutmacher, R.G.

    1984-08-01

    This report contains plutonium wavelengths, energy level classifications, and other spectroscopic data accumulated over the past twenty years at Laboratoire Aime Cotton (LAC) Argonne National Laboratory (ANL), and Lawrence Livermore National Laboratory (LLNL). The primary purpose was term analysis: deriving the energy levels in terms of quantum numbers and electron configurations, and evaluating the Slater-Condon and other parameters from the levels.

  2. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    SciTech Connect (OSTI)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

    1995-08-01

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

  3. Manufacturing of Plutonium Tensile Specimens

    SciTech Connect (OSTI)

    Knapp, Cameron M

    2012-08-01

    Details workflow conducted to manufacture high density alpha Plutonium tensile specimens to support Los Alamos National Laboratory's science campaigns. Introduces topics including the metallurgical challenge of Plutonium and the use of high performance super-computing to drive design. Addresses the utilization of Abaqus finite element analysis, programmable computer numerical controlled (CNC) machining, as well as glove box ergonomics and safety in order to design a process that will yield high quality Plutonium tensile specimens.

  4. (Final Draft) Superconducting

    E-Print Network [OSTI]

    ANDAND (Final Draft) Achieving Advanced Electrical Wires From Superconducting Coatings Prepared and Development Roadmap to Achieve Electrical Wire Advancements from Superconducting Coatings (Final Draft) Edited

  5. Neutrons find "missing" magnetism of plutonium

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

    numbers of electrons in plutonium's outer valence shell-an observation that also explains abnormal changes in plutonium's volume in its different phases. Neutrons are uniquely...

  6. 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.; Chae, S.M.

    1998-11-01

    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.

  7. The ORNL Surplus Facilities Management Program Long Range Plan

    SciTech Connect (OSTI)

    Myrick, T.E.

    1984-09-01

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy`s (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 76 individual surplus facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. The ORNL SFMP has prepared this Long Range Plan to outline the long-term management strategy for those facilities included in the program. The primary objective of this plan are to: (1) develop a base of information for each ORNL SFMP facility, (2) conduct preliminary decommissioning analyses to identify feasible alternatives, (3) assess the current and future risk of each facility, (4) establish a priority list for the decommissioning projects, and (5) integrate the individual project costs and schedules into an overall program schedule and cost estimate for the ORNL site. The Long Range Plan also provides an overview of the ORNL SFMP management structure, specifies the decommissioning criteria to be employed, and identifies special technical problems, research and development needs, and special facilities and equipment that may be required for decommissioning operations.

  8. Photochemical preparation of plutonium pentafluoride

    DOE Patents [OSTI]

    Rabideau, Sherman W. (Los Alamos, NM); Campbell, George M. (Los Alamos, NM)

    1987-01-01

    The novel compound plutonium pentafluoride may be prepared by the photodissociation of gaseous plutonium hexafluoride. It is a white solid of low vapor pressure, which consists predominantly of a face-centered cubic structure with a.sub.o =4.2709.+-.0.0005 .ANG..

  9. Options for the Immobilisation of UK Civil Plutonium

    SciTech Connect (OSTI)

    Scales, C.R.; Maddrell, E.R.; Harrison, M.T. [Nexia Solutions Ltd., Cumbria, CA (United Kingdom)

    2007-07-01

    As a result of the reprocessing of spent nuclear fuel the UK expects to accumulate in excess of 100 tonnes of separated plutonium. There is currently no long term strategy for the management of this material. The Nuclear Decommissioning Authority (NDA) has commissioned a programme with Nexia Solutions to examine the alternatives for the disposition of this material and subsequently present the NDA with technically underpinned option(s) for plutonium disposition. The overall programme comprises two main options, re-use as fuel in reactors and immobilisation in the event of being declared surplus to requirements and is targeted specifically at the requirements of the UK. The disposition programme will take account of the UK reactor portfolio, and the quantity that may require immobilisation will depend on future UK nuclear strategy. Immobilisation options are being reviewed in the light that a proportion of the stockpile could be declared waste. The options for immobilisation are being assessed in the expectation that any immobilised product would be destined for an as yet undefined repository, preceded by a period of storage in secure facilities. Potential products are being developed to be compatible with a wide range of disposal scenarios. (authors)

  10. Certification of Plutonium Standards for KAMS Neutron Multiplicity Counter

    SciTech Connect (OSTI)

    Salaymeh, S.R.

    2002-05-31

    As part of the implementation of the PEIS record of decision in January of 1997, DOE will pursue two technologies to disposition fifty metric tons of its stockpile of plutonium. As a result of this and in order to expedite the closure of Rocky Flats Environmental Technology Site in Colorado, DOE decided to use existing facilities at the Savannah River Site (SRS) for storing all material containing plutonium at KAMS. A neutron multiplicity counter was designed and built to carry out receipt verification measurement at the facility. Since the material covers a wide range and different levels of impurities, it is essential that we obtain a set of working standards. An agreement was drafted to select the first drums to be these standards. A plan was developed for the certification of these standards using Rocky Flat's existing nondestructive assay equipment. This paper will discuss the types of materials to be shipped to SRS, number of standards to certify for each type of material, and the certification plan. It will also discuss the activities necessary to determine the nuclear content of these working standards to be used at SRS facilities in support of shipment and receipt of the Pu containing materials. Definition of instrument qualifications, measurement control processes, measurement methodologies, and calculations necessary to report the gram quantities and their uncertainties for plutonium, americium-241, uranium-235 (if present) and neptunium-237 (if present) will also be presented.

  11. Los Alamos National Laboratory Plutonium Facility (PF-4) Seismic...

    Office of Environmental Management (EM)

    Laboratory Plutonium Facility (PF-4) Seismic Safety Los Alamos National Laboratory Plutonium Facility (PF-4) Seismic Safety Los Alamos National Laboratory Plutonium Facility (PF-4)...

  12. Complexation of Plutonium (IV) with Fluoride at Variable Tempeartures

    E-Print Network [OSTI]

    Moore, Dean A.

    2011-01-01

    of Neptunium and Plutonium. Edited by OECD Nuclear EnergyComplexation of Plutonium(IV) with Fluoride at Variablehigher temperatures. Key Words: Plutonium (IV) / Fluoride /

  13. PRELIMINARY DRAFT

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuilding energy codes have a moreINCREASES5-24690-1EA-2000 DRAFT

  14. Draft EIS

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalentLaboratory |Sector FullDOEUrsulaNatural Gas fromDraft-EIS Sign

  15. Hanford surplus facilities programs facilities listings and descriptions. Revision 1

    SciTech Connect (OSTI)

    Kiser, S.K.; Witt, T.L.

    1994-01-01

    On the Hanford Site, many surplus facilities exist (including buildings, stacks, tanks, cribs, burial grounds, and septic systems) that are scheduled to be decommissioned. Many of these facilities contain large inventories of radionuclides, which present potential radiological hazards on and off the Hanford Site. Some structures with limited structural deterioration present potential radiological and industrial safety hazards to personnel. Because of the condition of these facilities, a systematic surveillance and maintenance program is performed to identify and correct potential hazards to personnel and the environment until eventual decommissioning operations are completed.

  16. EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

  17. EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Harford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

  18. Draft-O-Meter

    K-12 Energy Lesson Plans and Activities Web site (EERE)

    Students will learn an easy technique to measure the presence of drafts in their homes and classrooms.

  19. Standard practice for removal of uranium or plutonium, or both, for impurity assay in uranium or plutonium materials

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01

    Standard practice for removal of uranium or plutonium, or both, for impurity assay in uranium or plutonium materials

  20. ISAB 2001-3 Hatchery Surplus Letter -Page 1 Independent Scientific Advisory Board

    E-Print Network [OSTI]

    ISAB 2001-3 Hatchery Surplus Letter - Page 1 Independent Scientific Advisory Board Portland, Oregon 97204 ISAB@nwppc.org April 16, 2001 Dr. Usha Varanasi Science Director Northwest Fisheries Surplus Review Dear Dr. Varanasi: This letter is the ISAB's response to your January 29, 2001 request

  1. JMU SURPLUS BICYCLE PROGRAM WEB SITE JMU offers University departments and individual employees ("Customer") the

    E-Print Network [OSTI]

    Arnold, Elizabeth A.

    JMU SURPLUS BICYCLE PROGRAM WEB SITE JMU offers University departments and individual employees ("Customer") the opportunity to select and borrow a Surplus Property bicycle for up to one year the bicycle to others. The following procedures must be followed to qualify for this program. Since the costs

  2. The producer surplus associated with gasoline fuel use in the United States1

    E-Print Network [OSTI]

    Lin, C.-Y. Cynthia

    : Q41, Q43 Keywords: oil, marginal costs, producer surplus, gasoline, wealth transfer, drilling costs the average long-run cost ­ is an important part of social cost-benefit analyses of changes in petroleum use, and then applies the estimates of producer surplus to two kinds of social cost-benefit analyses related

  3. Plutonium focus area

    SciTech Connect (OSTI)

    NONE

    1996-08-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this new approach, EM developed a management structure and principles that led to the creation of specific Focus Areas. These organizations were designed to focus the scientific and technical talent throughout DOE and the national scientific community on the major environmental restoration and waste management problems facing DOE. The Focus Area approach provides the framework for intersite cooperation and leveraging of resources on common problems. After the original establishment of five major Focus Areas within the Office of Technology Development (EM-50, now called the Office of Science and Technology), the Nuclear Materials Stabilization Task Group (EM-66) followed the structure already in place in EM-50 and chartered the Plutonium Focus Area (PFA). The following information outlines the scope and mission of the EM, EM-60, and EM-66 organizations as related to the PFA organizational structure.

  4. Screening study for evaluation of the potential for system 80+ to consume excess plutonium - Volume 1. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-04-30

    As part of the U.S. effort to evaluate technologies offering solutions for the safe disposal or utilization of surplus nuclear materials, the fiscal year 1993 Energy and Water Appropriations legislation provided the Department of Energy (DOE) the necessary funds to conduct multi-phased studies to determine the technical feasibility of using reactor technologies for the triple mission of burning weapons grade plutonium, producing tritium for the existing smaller weapons stockpile, and generating commercial electricity. DOE limited the studies to five advanced reactor designs. Among the technologies selected is the ABB-Combustion Engineering (ABB-CE) System 80+. The DOE study, currently in Phase ID, is proceeding with a more detailed evaluation of the design`s capability for plutonium disposition.

  5. Screening study for evaluation of the potential for system 80+ to consume excess plutonium - Volume 2. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-04-30

    As part of the U.S. effort to evaluate technologies offering solutions for the safe disposal or utilization of surplus nuclear materials, the fiscal year 1993 Energy and Water Appropriations legislation provided the Department of Energy (DOE) the necessary funds to conduct multi-phased studies to determine the technical feasibility of using reactor technologies for the triple mission of burning weapons grade plutonium, producing tritium for the existing smaller weapons stockpile, and generating commercial electricity. DOE limited the studies to five advanced reactor designs. Among the technologies selected is the ABB-Combustion Engineering (ABB-CE) System 80+. The DOE study, currently in Phase ID, is proceeding with a more detailed evaluation of the design`s capability for plutonium disposition.

  6. Selecting a plutonium vitrification process

    SciTech Connect (OSTI)

    Jouan, A. [Centre d`Etudes de la Vallee du Rhone, Bagnols sur Ceze (France)

    1996-05-01

    Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO{sub 2} or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO{sub 2} mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

  7. APPENDIX G Partition Coefficients For Plutonium

    E-Print Network [OSTI]

    and not adsorption reactions. C Adsorption data show that the presence of ligands influence plutonium adsorption onto soils. Increasing concentrations of ligands decrease plutonium adsorption. C If no complexing ligandsAPPENDIX G Partition Coefficients For Plutonium #12;Appendix G Partition Coefficients

  8. Plutonium Oxide Process Capability Work Plan

    SciTech Connect (OSTI)

    Meier, David E.; Tingey, Joel M.

    2014-02-28

    Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.

  9. Plutonium-the element of surprise

    E-Print Network [OSTI]

    Short, Daniel

    Plutonium-the element of surprise G.R.ChoppinandB.E.Stout This year marked the soth annivrsary ol the original isolation o{ plutonium, making ita relativenewcomerto the PeriodicTable.Ovrthe past 50 years plutonium has become more familiar to tho generslpublic than manyothor,olderelem6nts

  10. The occurrence of plutonium in nature

    E-Print Network [OSTI]

    Levine, Charles A.; Seaborg, Glenn T.

    1950-01-01

    Nuclear Energy S e r i e s , Plutonium P r o j e c t Record,Nuclear Energy S e r i e s , Plutonium P r o j e c t Record,Laboratory THE OCCURRENCE OF PLUTONIUM IN NATUIRE Charles A.

  11. Method of separating thorium from plutonium

    DOE Patents [OSTI]

    Clifton, David G. (Los Alamos, NM); Blum, Thomas W. (Los Alamos, NM)

    1984-01-01

    A method of chemically separating plutonium from thorium. Plutonium and thorium to be separated are dissolved in an aqueous feed solution, preferably as the nitrate salts. The feed solution is acidified and sodium nitrite is added to the solution to adjust the valence of the plutonium to the +4 state. A chloride salt, preferably sodium chloride, is then added to the solution to induce formation of an anionic plutonium chloride complex. The anionic plutonium chloride complex and the thorium in solution are then separated by ion exchange on a strong base anion exchange column.

  12. Method of separating thorium from plutonium

    DOE Patents [OSTI]

    Clifton, D.G.; Blum, T.W.

    1984-07-10

    A method is described for chemically separating plutonium from thorium. Plutonium and thorium to be separated are dissolved in an aqueous feed solution, preferably as the nitrate salts. The feed solution is acidified and sodium nitrite is added to the solution to adjust the valence of the plutonium to the +4 state. A chloride salt, preferably sodium chloride, is then added to the solution to induce formation of an anionic plutonium chloride complex. The anionic plutonium chloride complex and the thorium in solution are then separated by ion exchange on a strong base anion exchange column.

  13. Union Station, Tacoma, Washington : a design study for a surplus rail site

    E-Print Network [OSTI]

    Rhoads, Jeffrey David

    1982-01-01

    Recent technological changes in railroads, mergers, major shifts in urban land use patterns, and declining rail passenger travel has resulted in a surplus of urban rail lands. These lands represent a significant resource ...

  14. Self-irradiation damage to the local structure of plutonium and plutonium intermetallics

    E-Print Network [OSTI]

    Booth, C. H.

    2014-01-01

    Self-irradiation damage to the local structure of plutoniumand plutonium intermetallics C. H. Booth, 1 Yu Jiang, 1 S.espe- cially in elemental plutonium. For instance, although

  15. Progress in the Assessment of Waste-forms for the Immobilisation of UK Civil Plutonium

    SciTech Connect (OSTI)

    Harrison, M.T.; Scales, C.R.; Maddrell, E.R. [Nexia Solutions Ltd., British Technology Centre, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)

    2008-07-01

    The alternatives for the disposition of the UK's civil plutonium stocks are currently being investigated by Nexia Solutions Ltd. on behalf of the Nuclear Decommissioning Authority (NDA). A number of scenarios are currently being considered depending on the strategic requirements of the UK. The two main disposition options are: re-use as MOX (Mixed Oxide) fuel in reactors, or immobilisation in the event of any material being declared surplus to requirements. The amount of Pu which will require immobilisation will depend on future UK nuclear strategy, along with the extent of any stocks deemed unsuitable for re-use. However, it is likely that some portion will have to be immobilised and therefore three credible waste-forms are under consideration; ceramic, glass and 'immobilisation' MOX. These are currently being developed and assessed in a systematic programme that involves periodic evaluation against a range of criteria. In this way, by down-selecting on the basis of robust and technical review, the most appropriate option for immobilising surplus civil plutonium in the UK can be recommended. The latest results from the immobilisation experimental programme are presented following the de-selection of the least favourable glass and ceramic candidates. The main criteria for this decision were waste loading, durability, processability, criticality and proliferation resistance. In addition, the durability of unirradiated MOX fuel is being examined to determine its potential as a wasteform for Pu, and recent leach test data is discussed. The current evaluation comprises not only a comparison of the relevant physical properties of the various waste-forms, but also key processing parameters, e.g. glass viscosity and melter technology, ceramic fabrication routes, and criticality issues. Other important aspects of the long-term behaviour of the waste-forms under consideration in a potential repository environment, such as radiation damage, criticality control and the properties of any neutron poisons present, are also included. (authors)

  16. Air transport of plutonium metal: content expansion initiative for the plutonium air transportable (PAT01) packaging

    SciTech Connect (OSTI)

    Caviness, Michael L; Mann, Paul T

    2010-01-01

    The National Nuclear Security Administration (NNSA) has submitted an application to the Nuclear Regulatory Commission (NRC) for the air shipment of plutonium metal within the Plutonium Air Transportable (PAT-1) packaging. The PAT-1 packaging is currently authorized for the air transport of plutonium oxide in solid form only. The INMM presentation will provide a limited overview of the scope of the plutonium metal initiative and provide a status of the NNSA application to the NRC.

  17. Multi-generational stewardship of plutonium

    SciTech Connect (OSTI)

    Pillay, K.K.S. [Los Alamos National Lab., NM (United States). Nuclear Materials Technology Div.

    1997-10-01

    The post-cold war era has greatly enhanced the interest in the long-term stewardship of plutonium. The management of excess plutonium from proposed nuclear weapons dismantlement has been the subject of numerous intellectual discussions during the past several years. In this context, issues relevant to long-term management of all plutonium as a valuable energy resource are also being examined. While there are differing views about the future role of plutonium in the economy, there is a recognition of the environmental and health related problems and proliferation potentials of weapons-grade plutonium. The long-term management of plutonium as an energy resource will require a new strategy to maintain stewardship for many generations to come.

  18. Determination of Plutonium Content in Spent Fuel with Nondestructive Assay

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01

    LBNL- Determination of Plutonium Content in Spent Fuel withSwinhoe. “Determination of Plutonium Content in Spent FuelS. Tobin, “Measurement of Plutonium in Spent Nuclear Fuel by

  19. US Releases Updated Plutonium Inventory Report | National Nuclear...

    National Nuclear Security Administration (NNSA)

    details the current plutonium inventory of the U.S. Titled The United States Plutonium Balance, 1944-2009, the document serves as an update to Plutonium: the First 50 Years, which...

  20. PLUTONIUM METAL: OXIDATION CONSIDERATIONS AND APPROACH

    SciTech Connect (OSTI)

    Estochen, E.

    2013-03-20

    Plutonium is arguably the most unique of all metals when considered in the combined context of metallurgical, chemical, and nuclear behavior. Much of the research in understanding behavior and characteristics of plutonium materials has its genesis in work associated with nuclear weapons systems. However, with the advent of applications in fuel materials, the focus in plutonium science has been more towards nuclear fuel applications, as well as long term storage and disposition. The focus of discussion included herein is related to preparing plutonium materials to meet goals consistent with non-proliferation. More specifically, the emphasis is on the treatment of legacy plutonium, in primarily metallic form, and safe handling, packaging, and transport to meet non-proliferation goals of safe/secure storage. Elevated temperature oxidation of plutonium metal is the treatment of choice, due to extensive experiential data related to the method, as the oxide form of plutonium is one of only a few compounds that is relatively simple to produce, and stable over a large temperature range. Despite the simplicity of the steps required to oxidize plutonium metal, it is important to understand the behavior of plutonium to ensure that oxidation is conducted in a safe and effective manner. It is important to understand the effect of changes in environmental variables on the oxidation characteristics of plutonium. The primary purpose of this report is to present a brief summary of information related to plutonium metal attributes, behavior, methods for conversion to oxide, and the ancillary considerations related to processing and facility safety. The information provided is based on data available in the public domain and from experience in oxidation of such materials at various facilities in the United States. The report is provided as a general reference for implementation of a simple and safe plutonium metal oxidation technique.

  1. Plutonium nitrate bottle counter manual

    SciTech Connect (OSTI)

    Menlove, H.O.; Adams, E.L.; Holbrooks, O.R.

    1984-03-01

    A neutron coincidence counter has been designed for plutonium nitrate assay in large storage bottles. This assay system can be used in the reprocessing plant or in the nitrate-to-oxide conversion facility. The system is based on the family of neutron detectors similar to the high-level neutron coincidence counter. This manual describes the system and gives performance and calibration parameters for typical applications. 4 references, 11 figures, 9 tables.

  2. TA-55: LANL Plutonium-Processing Facilities

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

    perform plutonium metal preparation and recovery operations. Foundry, machining, welding, and assembly operations also are required for pit manufacturing, as well as a...

  3. Calculating Plutonium and Praseodymium Structural Transformations...

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

    transition of praseodymium. As plutonium is heated it undergoes six complex crystalline phase transitions-the most of any element at ambient pressure. Explaining these six...

  4. EA-0841: Import of Russian Plutonium-238

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of a proposal to purchase plutonium-238 from the Russian Federation (Russia) for use in the Nation's space program.

  5. Plutonium Disposition Program | National Nuclear Security Administrati...

    National Nuclear Security Administration (NNSA)

    irradiating it in fast reactors operating under certain nonproliferation conditions. Irradiation in fast reactors is a technically credible approach for Russian plutonium...

  6. TECHNIQUES FOR MONITORING PLUTONIUM IN THE ENVIRONMENT

    E-Print Network [OSTI]

    Nero Jr., A.V.

    2011-01-01

    NTIS). "Proceedings of the Rocky Flats Symposium on SafetyTotal Inventories from Rocky Flats," Health Physics 30, 209-Fraction of Plutonium at Rocky Flats," Health Physics ~,

  7. Independent Activity Report, Hanford Plutonium Finishing Plant...

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

    May 2012 Criticality Safety Information Meeting for the Hanford Plutonium Finishing Plant HIAR-RL-2012-05-14 This Independent Activity Report documents an oversight activity...

  8. Comparative repository performance of plutonium forms - initial...

    Office of Scientific and Technical Information (OSTI)

    IL (United States) Country of Publication: United States Language: English Subject: 05 NUCLEAR FUELS; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE DISPOSAL; PLUTONIUM; WASTE...

  9. Type A Accident Investigation of the March 16, 2000, Plutonium...

    Energy Savers [EERE]

    Multiple Intake Event at the Plutonium Facility, Los Alamos National Laboratory, New Mexico Type A Accident Investigation of the March 16, 2000, Plutonium-238 Multiple Intake...

  10. Investigation of the November 8, 2011, Plutonium Contamination...

    Office of Environmental Management (EM)

    November 8, 2011, Plutonium Contamination in the Zero Power Physics Reactor Facility, at the Idaho National Laboratory Investigation of the November 8, 2011, Plutonium...

  11. Hanford Site Workers Meet Challenging Performance Goal at Plutonium...

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

    at the Hanford site's Plutonium Finishing Plant are surpassing goals for removing hazardous tanks once used in the plutonium production process. EM's Richland Operations Office...

  12. Plutonium Finishing Plant 242-Z Americium Recovery Facility

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

    of the overall mission to safely and compliantly decommission and demolish Hanford's Plutonium Finishing Plant. The Plutonium Finishing Plant once produced two-thirds of the...

  13. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOE Patents [OSTI]

    Mullins, L.J.; Christensen, D.C.

    1982-09-20

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium for electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  14. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOE Patents [OSTI]

    Mullins, Lawrence J. (Los Alamos, NM); Christensen, Dana C. (Los Alamos, NM)

    1984-01-01

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium from electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  15. Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel

    SciTech Connect (OSTI)

    Delashmitt, Jeffrey {Jeff} S [ORNL; Keever, Tamara {Tammy} Jo [ORNL; Smith, Rob R [ORNL] [ORNL; Hexel, Cole R [ORNL] [ORNL; Ilgner, Ralph H [ORNL] [ORNL

    2010-01-01

    The United States Department of Energy (DOE) Fissile Materials Disposition Program (FMDP) is pursuing disposal of surplus weapons-usable plutonium by reactor irradiation as the fissile constituent of MOX fuel. Lead test assemblies (LTAs) have been irradiated for approximately 36 months in Duke Energy's Catawba-1 nuclear power plant (NPP). Per the mixed oxide (MOX) fuel topical report, approved by the U.S. Nuclear Regulatory Commission (NRC), destructive post-irradiation examinations (PIEs) are to be performed on second cycle rods (irradiated to an average burnup of approximately 45 GWd/MTHM). The Radiochemical Analysis Group (RAG) at Oak Ridge National Laboratory (ORNL) is currently performing the detailed destructive post-irradiation examinations (PIE) on four of the mixed uranium and plutonium oxide fuel rods. The analytical process involves dissolution of designated fuel segments in a shielded hot cell for high precision quantification of select fission products and actinide isotopes employing isotope dilution mass spectrometry (IDMS) among other analyses. The hot cell dissolution protocol to include the collection and subsequent alkaline fusion digestion of the fuel's acid resistant metallic particulates will be presented. Although the IDMS measurements of the fission products and actinide isotopes will not be completed by the time of the 51st INMM meeting, the setup and testing of the HPLC chromatographic separations in preparation for these measurements will be discussed.

  16. REMOVAL OF LEGACY PLUTONIUM MATERIALS FROM SWEDEN

    SciTech Connect (OSTI)

    Dunn, Kerry A.; Bellamy, J. Steve; Chandler, Greg T.; Iyer, Natraj C.; Koenig, Rich E.; Leduc, D.; Hackney, B.; Leduc, Dan R.

    2013-08-18

    U.S. Department of Energy’s National Nuclear Security Administration (NNSA) Office of Global Threat Reduction (GTRI) recently removed legacy plutonium materials from Sweden in collaboration with AB SVAFO, Sweden. This paper details the activities undertaken through the U.S. receiving site (Savannah River Site (SRS)) to support the characterization, stabilization, packaging and removal of legacy plutonium materials from Sweden in 2012. This effort was undertaken as part of GTRI’s Gap Materials Program and culminated with the successful removal of plutonium from Sweden as announced at the 2012 Nuclear Security Summit. The removal and shipment of plutonium materials to the United States was the first of its kind under NNSA’s Global Threat Reduction Initiative. The Environmental Assessment for the U.S. receipt of gap plutonium material was approved in May 2010. Since then, the multi-year process yielded many first time accomplishments associated with plutonium packaging and transport activities including the application of the of DOE-STD-3013 stabilization requirements to treat plutonium materials outside the U.S., the development of an acceptance criteria for receipt of plutonium from a foreign country, the development and application of a versatile process flow sheet for the packaging of legacy plutonium materials, the identification of a plutonium container configuration, the first international certificate validation of the 9975 shipping package and the first intercontinental shipment using the 9975 shipping package. This paper will detail the technical considerations in developing the packaging process flow sheet, defining the key elements of the flow sheet and its implementation, determining the criteria used in the selection of the transport package, developing the technical basis for the package certificate amendment and the reviews with multiple licensing authorities and most importantly integrating the technical activities with the Swedish partners.

  17. April 20, 2012 Fourth Draft POSITION VACANCY ANNOUNCEMENT / POSITION 00010069 DRAFT

    E-Print Network [OSTI]

    Meyers, Steven D.

    April 20, 2012 ­Fourth Draft POSITION VACANCY ANNOUNCEMENT / POSITION 00010069 ­ DRAFT Assistant of Concern Action Team (SOCAT). #12;April 20, 2012 ­Fourth Draft SALARY: Negotiable, competitive

  18. NIST Interage (Second Draft

    E-Print Network [OSTI]

    technical leadership for the nation's measurement and standards infrastructure. ITL develops tests, test of technical, physical, administrative, and management standards and guidelines for the cost-effective security (Second Draft) CAESARS Framework Extension: An Enterprise Continuous Monitoring Technical Reference Model

  19. Laboratory-scale evaluations of alternative plutonium precipitation methods

    SciTech Connect (OSTI)

    Martella, L.L.; Saba, M.T.; Campbell, G.K.

    1984-02-08

    Plutonium(III), (IV), and (VI) carbonate; plutonium(III) fluoride; plutonium(III) and (IV) oxalate; and plutonium(IV) and (VI) hydroxide precipitation methods were evaluated for conversion of plutonium nitrate anion-exchange eluate to a solid, and compared with the current plutonium peroxide precipitation method used at Rocky Flats. Plutonium(III) and (IV) oxalate, plutonium(III) fluoride, and plutonium(IV) hydroxide precipitations were the most effective of the alternative conversion methods tested because of the larger particle-size formation, faster filtration rates, and the low plutonium loss to the filtrate. These were found to be as efficient as, and in some cases more efficient than, the peroxide method. 18 references, 14 figures, 3 tables.

  20. Structural Characterization of and Plutonium Sorption on Mesoporous and Nanoparticulate Ferrihydrite

    E-Print Network [OSTI]

    Brogan, Luna Kestrel Schwaiger

    2012-01-01

    2.2.1 Plutonium Redox Chemistry . . . . . . . . .2.5 Plutonium Measurement with Liquid Scintillation CountingChemistry . . . . . . . . . . . . . 5.9.4 Plutonium Uptake

  1. Quantifying structural damage from self-irradiation in a plutonium superconductor

    E-Print Network [OSTI]

    2006-01-01

    was presented as part of Plutonium Futures - The Science: Atopical Confer- ence on Plutonium and Actinide, Asilomar,in loading one of the plutonium samples. This work was

  2. Interstitial incorporation of plutonium into a low-dimensional potassium borate

    E-Print Network [OSTI]

    Wang, Shuao

    2014-01-01

    the disposal of weapons plutonium. J. Mat. Res. 1995, 10,C. ; Scheinost, A. Plutonium incorporation in phosphate andfor the immobilization of plutonium and “minor” actinides.

  3. From Yellow to Black: Dramatic Changes between Cerium(IV) and Plutonium(IV) Molybdates

    E-Print Network [OSTI]

    Cross, Justin N.

    2014-01-01

    molybdate • cerium • plutonium • optical energy spectrum •is particularly common with plutonium where Ce(IV) has beenand the formation of plutonium molybdates has been suggested

  4. Reaction of Plutonium(VI) with the Manganese-Substituted Iron Oxide Mineral Goethite

    E-Print Network [OSTI]

    Hu, Yung-Jin Hu

    2011-01-01

    Plutonium(VI) Sorption on Manganese-SubstitutedX-ray Beam-Induced Chemistry on Plutonium Sorbed on Variousof Plutonium . . . . . . . . . . . . . . . . .159 v E Anion

  5. Molecular Interactions of Plutonium(VI) with Synthetic Manganese-Substituted Goethite

    E-Print Network [OSTI]

    Hu, Yung-Jin

    2011-01-01

    E. , Thesis, Reactions of Plutonium(VI) with the Iron Oxideof Uranium, Neptunium, Plutonium, Americium and Technetium;Molecular Interactions of Plutonium(VI) with Synthetic

  6. Excess Plutonium: Weapons Legacy or National Asset?

    SciTech Connect (OSTI)

    Klipa, G.; Boeke, S.; Hottel, R.

    2002-02-27

    The Nuclear Materials Stewardship Initiative was established in January, 2000, to accelerate the work of achieving integration and cutting long-term costs associated with the management of nuclear materials. As part of that initiative, the Department of Energy (DOE), Office of Environmental Management (EM), has established Nuclear Material Management Groups for the management of excess nuclear materials. As one of these groups, the Plutonium Material Management Group (PMMG) has been chartered to serve as DOE's complex wide resource and point of contact for technical coordination and program planning support in the safe and efficient disposition of the nations excess Plutonium 239. This paper will explain the mission, goals, and objectives of the PMMG. In addition, the paper will provide a broad overview of the status of the plutonium inventories throughout the DOE complex. The DOE currently manages approximately 99.5 MT of plutonium isotopes. Details of the various categories of plutonium, from material designated for national security needs through material that has been declared excess, will be explained. For the plutonium that has been declared excess, the various pathways to disposition (including reuse, recycling, sale, transfer, treatment, consumption, and disposal) will be discussed. At this time 52.5 MT of plutonium has been declared excess and the method of disposition for that material is the subject of study and evaluation within DOE. The role of the PMMG in those evaluations will be outlined.

  7. Commercial nuclear fuel from U.S. and Russian surplus defense inventories: Materials, policies, and market effects

    SciTech Connect (OSTI)

    NONE

    1998-05-01

    Nuclear materials declared by the US and Russian governments as surplus to defense programs are being converted into fuel for commercial nuclear reactors. This report presents the results of an analysis estimating the market effects that would likely result from current plans to commercialize surplus defense inventories. The analysis focuses on two key issues: (1) the extent by which traditional sources of supply, such as production from uranium mines and enrichment plants, would be displaced by the commercialization of surplus defense inventories or, conversely, would be required in the event of disruptions to planned commercialization, and (2) the future price of uranium considering the potential availability of surplus defense inventories. Finally, the report provides an estimate of the savings in uranium procurement costs that could be realized by US nuclear power generating companies with access to competitively priced uranium supplied from surplus defense inventories.

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

    SciTech Connect (OSTI)

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

    1993-06-01

    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.

  9. Alternative fuels: Feasibility of expanding the fuel ethanol industry using surplus grain

    SciTech Connect (OSTI)

    Not Available

    1987-01-01

    This report examines two financing concepts in using surplus federally owned grain to further the development of the ethanol industry. They are (1) producers/developers would use surplus grain as collateral to obtain financing from lending institutions to construct new ethanol plants or expanding existing facilities and (2) producers/developers would use surplus grain as a free feedstock to produce ethanol, which could induce lending institutions to finance the construction or expansion of ethanol plants or facilities. Surplus grain inventories are large enough to support these concepts. However, producers/developers and lenders are skeptical about the concepts' usefulness for expanding the industry, given the current slump in the ethanol market. Most of producers/developers said the concepts were feasible; most lenders had little interest in the grain-as-collateral concept but were more interested in the feedstock-as-inducement concept. Department of Agriculture officials said that it is unlikely they would initiate the financing concepts unless directed by the Congress.

  10. Plutonium

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia4)9 Federal Register / Vol. 76,EXAMPLE 4 ***

  11. PLUTONIUM METALLOGRAPHY AT LOS ALAMOS

    SciTech Connect (OSTI)

    PEREYRA, RAMIRO A.; LOVATO, DARRYL

    2007-01-08

    From early days of the Manhattan program to today, scientists and engineers have continued to investigate the metallurgical properties of plutonium (Pu). Although issues like aging was not a concern to the early pioneers, today the reliability of our aging stockpile is of major focus. And as the country moves toward a new generation of weapons similar problems that the early pioneers faced such as compatibility, homogeneity and malleability have come to the forefront. And metallography will continue to be a principle tool for the resolution of old and new issues. Standard metallographic techniques are used for the preparation of plutonium samples. The samples are first cut with a slow speed idamond saw. After mounting in Epon 815 epoxy resin, the samples are ground through 600 grit silicon carbide paper. PF 5070 (a Freon substitute) is used as a coolant, lubricant, and solvent for most operations. Rough mechanical polished is done with 9-{mu} diamond using a nap less cloth, for example nylon or cotton. Final polish is done with 1-{mu} diamond on a nappy cloth such as sylvet. Ethyl alcohol is then used ultrasonically to clean the samples before electro polishing. The sample is then electro-polished and etched in an electrolyte containing 10% nitric acid, and 90% dimethyleneformalmide. Ethyl alcohol is used as a final cleaning agent. Although standard metallographic preparation techniques are used, there are several reasons why metallography of Pu is difficult and challenging. Firstly, because of the health hazards associated with its radioactive properties, sample preparation is conducted in glove boxes. Figure 1 shows the metallography line, in an R and D facility. Since they are designed to be negative in pressure to the laboratory, cross-contamination of abrasives is a major problem. In addition, because of safety concerns and waste issues, there is a limit to the amount of solvent that can be used. Secondly, Pu will readily hydride or oxidize when in contact with metallographic polishing lubricants, solvents, or chemicals. And water being one of the most reactive solutions, is not used in the preparation. Figure 2 shows an example of a plutonium sample in which an oxide film has formed on the surface due to overexposure to solutions. it has been noted that nucleation of the hydride/oxide begins around inclusions and samples with a higher concentration of impurities seem to be more susceptible to this reaction. Figure 3 shows examples of small oxide rings, forming around inclusions. Lastly, during the cutting, grinding, or polishing process there is enough stress induced in the sample that the surface can transform from the soft face-centered-cubic delta phase (30 HV) to the strain-induced monoclinic alpha{prime} phase (300 HV). Figure 4 and 5 shows cross-sectional views of samples in which one was cut using a diamond saw and the other was processed through 600 grit. The white layers on the edges is the strain induced alpha{prime} phase. The 'V' shape indentation in Figure 5 was caused by a coarser abrasive which resulted in transformations to a depth of approximately 20 {micro}m. Another example of the transformation sensitivity of plutonium can be seen in Figure 6, in which the delta phase has partly transformed to alpha{prime} during micro hardness indentation.

  12. TECHNIQUES FOR MONITORING PLUTONIUM IN THE ENVIRONMENT

    E-Print Network [OSTI]

    Nero Jr., A.V.

    2011-01-01

    150 day decay time, except for LMFBR, which assumes 30 days.> N") Plutonium from an LMFBR C'J II I I N") CD C".J c:'-l

  13. LANL Plutonium-Processing Facilities National Security

    E-Print Network [OSTI]

    range of national security programs that involve stockpile stewardship, plutonium processing, nuclear materials stabilization, materials disposition, nuclear forensics, nuclear counter-terrorism, and nuclear of technical capabilities. These capabilities form a center of excellence for actinide science and technology

  14. EIS-0219: F-Canyon Plutonium Solutions

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environmental impacts of processing the plutonium solutions to metal form using the F-Canyon and FB-Line facilities at the Savannah River Site.

  15. Guidelines for international plutonium management: Overview and implications

    SciTech Connect (OSTI)

    Bryson, M.C. [Los Alamos National Lab., NM (United States); Fitzgerald, C.P.; Kincaid, C. [Dept. of Energy, Washington, DC (United States)

    1998-12-31

    In September, 1997, nine of the world`s plutonium-using countries agreed to a set of guidelines for international plutonium management, with acceptances to be submitted to the International Atomic Energy Agency on December 1. Following three years of discussion, the guidelines provide a unified package of accepted rules for the storage, handling, and transportation of civil plutonium as well as military plutonium that has been declared as no longer required for defense purposes. New requirements include a formal declaration of national plutonium strategies, which will recognize the environmental, economic, and proliferation concerns and the consequent importance of balancing plutonium supply and demand. Nations will also make annual declaration of their non-military stockpiles of unirradiated plutonium, together with estimates of the plutonium content in spent reactor fuel. These guidelines represent the first formally accepted recognition of the need for plutonium management of this scope and could thus provide a partial basis for future monitoring and policy regimes.

  16. Development of plutonium aerosol fractionation system 

    E-Print Network [OSTI]

    Mekala, Malla R.

    1993-01-01

    DEVELOPMENT OF A PLUTONIUM AEROSOL FRACTIONATION SYSTEM A Thesis by MALLA R. MEKALA Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August... 1993 Major Subject: Mechanical Engineering DEVELOPMENT OP A PLUTONIUM AEROSOL FRACTIONATION SYSTEM A Thesis by MALLA R. MEKALA Approved as to style and content by: A. R. McFarland (Chair of Committee) N. K. Anand (Mer toer) (', & C. B...

  17. Plutonium: The first 50 years. United States plutonium production, acquisition, and utilization from 1944 through 1994

    SciTech Connect (OSTI)

    None

    1996-02-01

    The report contains important newly declassified information regarding the US production, acquisition, and removals of plutonium. This new information, when combined with previously declassified data, has allowed the DOE to issue, for the first time, a truly comprehensive report on the total DOE plutonium inventory. At the December 7, 1993, Openness Press Conference, the DOE declassified the plutonium inventories at eight locations totaling 33.5 metric tons (MT). This report declassifies the remainder of the DOE plutonium inventory. Newly declassified in this report is the quantity of plutonium at the Pantex Site, near Amarillo, Texas, and in the US nuclear weapons stockpile of 66.1 MT, which, when added to the previously released inventory of 33.5 MT, yields a total plutonium inventory of 99.5 MT. This report will document the sources which built up the plutonium inventory as well as the transactions which have removed plutonium from that inventory. This report identifies four sources that add plutonium to the DOE/DoD inventory, and seven types of transactions which remove plutonium from the DOE/DoD inventory. This report also discusses the nuclear material control and accountability system which records all nuclear material transactions, compares records with inventory and calculates material balances, and analyzes differences to verify that nuclear materials are in quantities as reported. The DOE believes that this report will aid in discussions in plutonium storage, safety, and security with stakeholders as well as encourage other nations to declassify and release similar data. These data will also be available for formulating policies with respect to disposition of excess nuclear materials. The information in this report is based on the evaluation of available records. The information contained in this report may be updated or revised in the future should additional or more detailed data become available.

  18. Multiconfigurational nature of 5f orbitals in uranium and plutonium intermetallics

    E-Print Network [OSTI]

    Booth, C. H.

    2014-01-01

    Orbitals in Uranium and Plutonium Intermetallics C. H. BoothAbstract: Uranium and plutonium’s 5f electrons are tenuouslyanomalous properties of ?-plutonium. Nature 446(7135):513.

  19. Plutonium Finishing Plant safety evaluation report

    SciTech Connect (OSTI)

    Not Available

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

  20. CEC3002012003LCD LEAD COMMISSIONER DRAFT

    E-Print Network [OSTI]

    APRIL 2012 CEC3002012003LCD LEAD COMMISSIONER DRAFT GUIDEBOOK RENEWABLE ENERGY PROGRAM OVERALL PROGRAM GUIDEBOOK Fourth Edition Lead Commissioner Draft Guidebook CALIFORNIA ENERGY COMMISSION, California 95814 M Staff Proposed Errata to the Lead Commissioner Draft Renewables Portfolio Standard

  1. The design and evaluation of an international plutonium storage system

    E-Print Network [OSTI]

    Bae, Eugene

    2001-01-01

    To address the proliferation risk of separated plutonium, a technical and institutional design of an international plutonium storage system (IPSS) is presented. The IPSS is evaluated from two perspectives: its ability to ...

  2. Elastic and Mechanical Properties of Plutonium and Plutonium Alloys Tarik A. Saleh, Adam M. Farrow, Franz J. Friebert, Albert Migliori, Jeremy N. Mitchell, Michael E. Bange

    E-Print Network [OSTI]

    Elastic and Mechanical Properties of Plutonium and Plutonium Alloys Tarik A. Saleh, Adam M. Farrow and reactivity of plutonium on mechanical properties is of paramount importance to plutonium research of plutonium and its alloys, focusing on changing properties as a function of homogenization and age

  3. U.S. and Russia Sign Plutonium Disposition Agreement | National...

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

    Plutonium Disposition Agreement | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  4. Standard test method for plutonium assay by plutonium (III) diode array spectrophotometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This test method describes the determination of total plutonium as plutonium(III) in nitrate and chloride solutions. The technique is applicable to solutions of plutonium dioxide powders and pellets (Test Methods C 697), nuclear grade mixed oxides (Test Methods C 698), plutonium metal (Test Methods C 758), and plutonium nitrate solutions (Test Methods C 759). Solid samples are dissolved using the appropriate dissolution techniques described in Practice C 1168. The use of this technique for other plutonium-bearing materials has been reported (1-5), but final determination of applicability must be made by the user. The applicable concentration range for plutonium sample solutions is 10–200 g Pu/L. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropria...

  5. Calculated Phonon Spectra of Plutonium at High Temperatures

    E-Print Network [OSTI]

    Savrasov, Sergej Y.

    Calculated Phonon Spectra of Plutonium at High Temperatures X. Dai,1 S. Y. Savrasov,2 * G. Kotliar dynamical proper- ties of plutonium using an electronic structure method, which incorporates correlation anharmonic and can be stabilized at high temperatures by its phonon entropy. Plutonium (Pu) is a material

  6. Atomic Scale Mechanism of Plutonium Corrosion Steven D. Conradson,1

    E-Print Network [OSTI]

    Atomic Scale Mechanism of Plutonium Corrosion Steven D. Conradson,1 Alison L. Costello,1 Francisco Estudios Superiores, Merida, Yucatan, Mexico conradson@lanl.gov INTRODUCTION The reaction of plutonium (Pu chemistry, nuclear forensics, and other areas of plutonium science and technology. The current model

  7. Removal of Uranium from Plutonium Solutions by Anion Exchange

    SciTech Connect (OSTI)

    Rudisill, T.S.

    2002-03-22

    The anion exchange capacity in the HB-Line Phase II Facility will be used to purify plutonium solutions potentially containing significant quantities of depleted uranium. Following purification, the plutonium will be precipitated as an oxalate and calcined to plutonium oxide (PuO2) for storage until final disposition.

  8. Excess plutonium disposition using ALWR technology

    SciTech Connect (OSTI)

    Phillips, A.; Buckner, M.R.; Radder, J.A.; Angelos, J.G.; Inhaber, H.

    1993-02-01

    The Office of Nuclear Energy of the Department of Energy chartered the Plutonium Disposition Task Force in August 1992. The Task Force was created to assess the range of practicable means of disposition of excess weapons-grade plutonium. Within the Task Force, working groups were formed to consider: (1) storage, (2) disposal,and(3) fission options for this disposition,and a separate group to evaluate nonproliferation concerns of each of the alternatives. As a member of the Fission Working Group, the Savannah River Technology Center acted as a sponsor for light water reactor (LWR) technology. The information contained in this report details the submittal that was made to the Fission Working Group of the technical assessment of LWR technology for plutonium disposition. The following aspects were considered: (1) proliferation issues, (2) technical feasibility, (3) technical availability, (4) economics, (5) regulatory issues, and (6) political acceptance.

  9. Method for dissolving delta-phase plutonium

    DOE Patents [OSTI]

    Karraker, David G. (1600 Sherwood Pl., SE., Aiken, SC 29801)

    1992-01-01

    A process for dissolving plutonium, and in particular, delta-phase plutonium. The process includes heating a mixture of nitric acid, hydroxylammonium nitrate (HAN) and potassium fluoride to a temperature between 40.degree. and 70.degree. C., then immersing the metal in the mixture. Preferably, the nitric acid has a concentration of not more than 2M, the HAN approximately 0.66M, and the potassium fluoride 0.1M. Additionally, a small amount of sulfamic acid, such as 0.1M can be added to assure stability of the HAN in the presence of nitric acid. The oxide layer that forms on plutonium metal may be removed with a non-oxidizing acid as a pre-treatment step.

  10. Alternating layers of plutonium and lead or indium as surrogate for plutonium

    SciTech Connect (OSTI)

    Rudin, Sven Peter

    2009-01-01

    Elemental plutonium (Pu) assumes more crystal structures than other elements, plausibly due to bonding f electrons becoming non-bonding. Complex geometries hamper understanding of the transition in Pu, but calculations predict this transition in a system with simpler geometry: alternating layers either of plutonium and lead or of plutonium and indium. Here the transition occurs via a pairing-up of atoms within Pu layers. Calculations stepping through this pairing-up reveal valuable details of the transition, for example that the transition from bonding to non-bonding proceeds smoothly.

  11. For the draft Australian Curriculum

    E-Print Network [OSTI]

    Boynton, Walter R.

    year 7Geography For the draft Australian Curriculum Explaining our catchment #12;Prepared by: Water...........................................................................................................2 Australian Curriculum links for this unit ...........................................................................3 Australian Curriculum: Geography

  12. REVIEW OF PLUTONIUM OXIDATION LITERATURE

    SciTech Connect (OSTI)

    Korinko, P.

    2009-11-12

    A brief review of plutonium oxidation literature was conducted. The purpose of the review was to ascertain the effect of oxidation conditions on oxide morphology to support the design and operation of the PDCF direct metal oxidation (DMO) furnace. The interest in the review was due to a new furnace design that resulted in oxide characteristics that are different than those of the original furnace. Very little of the published literature is directly relevant to the DMO furnace operation, which makes assimilation of the literature data with operating conditions and data a convoluted task. The oxidation behavior can be distilled into three regimes, a low temperature regime (RT to 350 C) with a relatively slow oxidation rate that is influenced by moisture, a moderate temperature regime (350-450 C) that is temperature dependent and relies on more or less conventional oxidation growth of a partially protective oxide scale, and high temperature oxidation (> 500 C) where the metal autocatalytically combusts and oxidizes. The particle sizes obtained from these three regimes vary with the finest being from the lowest temperature. It is surmised that the slow growth rate permits significant stress levels to be achieved that help break up the oxides. The intermediate temperatures result in a fairly compact scale that is partially protective and that grows to critical thickness prior to fracturing. The growth rate in this regime may be parabolic or paralinear, depending on the oxidation time and consequently the oxide thickness. The high temperature oxidation is invariant in quiescent or nearly quiescent conditions due to gas blanketing while it accelerates with temperature under flowing conditions. The oxide morphology will generally consist of fine particles (<15 {micro}m), moderately sized particles (15 < x < 250 {micro}m) and large particles (> 250 {micro}m). The particle size ratio is expected to be < 5%, 25%, and 70% for fine, medium and large particles, respectively, for metal temperatures in the 500-600 C range.

  13. Dehydration of plutonium or neptunium trichloride hydrate

    DOE Patents [OSTI]

    Foropoulos, J. Jr.; Avens, L.R.; Trujillo, E.A.

    1992-03-24

    A process is described for preparing anhydrous actinide metal trichlorides of plutonium or neptunium by reacting an aqueous solution of an actinide metal trichloride selected from the group consisting of plutonium trichloride or neptunium trichloride with a reducing agent capable of converting the actinide metal from an oxidation state of +4 to +3 in a resultant solution, evaporating essentially all the solvent from the resultant solution to yield an actinide trichloride hydrate material, dehydrating the actinide trichloride hydrate material by heating the material in admixture with excess thionyl chloride, and recovering anhydrous actinide trichloride.

  14. Dehydration of plutonium or neptunium trichloride hydrate

    DOE Patents [OSTI]

    Foropoulos, Jr., Jerry (Los Alamos, NM); Avens, Larry R. (Los Alamos, NM); Trujillo, Eddie A. (Espanola, NM)

    1992-01-01

    A process of preparing anhydrous actinide metal trichlorides of plutonium or neptunium by reacting an aqueous solution of an actinide metal trichloride selected from the group consisting of plutonium trichloride or neptunium trichloride with a reducing agent capable of converting the actinide metal from an oxidation state of +4 to +3 in a resultant solution, evaporating essentially all the solvent from the resultant solution to yield an actinide trichloride hydrate material, dehydrating the actinide trichloride hydrate material by heating the material in admixture with excess thionyl chloride, and recovering anhydrous actinide trichloride is provided.

  15. Draft Advanced Nuclear Energy Solicitation Fact Sheet | Department...

    Energy Savers [EERE]

    Draft Advanced Nuclear Energy Solicitation Fact Sheet Draft Advanced Nuclear Energy Solicitation Fact Sheet Draft Advanced Nuclear Energy Projects Solicitation Fact Sheet...

  16. EA-1551: Draft Environmental Assessment | Department of Energy

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

    1: Draft Environmental Assessment EA-1551: Draft Environmental Assessment DOE issued, jointly with the Montana Department of Environmental Quality (MDEQ), a Draft EA that would...

  17. DRAFT DRAFT Electricity and Natural Gas Sector Description

    E-Print Network [OSTI]

    DRAFT DRAFT Electricity and Natural Gas Sector Description For Public Distribution AB 32 Scoping of electricity and natural gas; including electricity generation, combined heat and power, and electricity and natural gas end uses for residential and commercial purposes. Use of electricity and/or gas for industrial

  18. Using magnetization measurements to detect small amounts of plutonium hydride formation in plutonium metal

    SciTech Connect (OSTI)

    Kim, Jae Wook [Rutgers Univ., New Brunswick, NJ (United States); Mielke, Charles H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Zapf, Vivien [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baiardo, Joseph P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mitchell, Jeremy N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Richmond, Scott [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Schwartz, Daniel S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mun, Eun D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Smith, Alice Iulia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-10-20

    We report the formation of plutonium hydride in 2 at % Ga-stabilized ?-Pu, with 1 atomic % H charging. We show that magnetization measurements are a sensitive, quantitative measure of ferromagnetic plutonium hydride against the nonmagnetic background of plutonium. It was previously shown that at low hydrogen concentrations, hydrogen forms super-abundant vacancy complexes with plutonium, resulting in a bulk lattice contraction. Here we use magnetization, X-ray and neutron diffraction measurements to show that in addition to forming vacancy complexes, at least 30% of the H atoms bond with Pu to precipitate PuHx, largely on the surface of the sample with x ~ 1.9. We observe magnetic hysteresis loops below 40 K with magnetic remanence, consistent with precipitates of ferromagnetic PuH1.9.

  19. Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities

    SciTech Connect (OSTI)

    Jardine, L J; Borisov, G B

    2004-07-21

    A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

  20. Biomass 2014 Draft Agenda

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based Fuels Researchof Energy|Make FuelsBioindustryWBSBiomass 2014 Draft

  1. 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

    1993-06-01

    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.

  2. EIS-0288: Draft Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE)

    Draft Environmental Impact Statement (EIS) for the Production of Tritium in a Commercial Light Water Reactor

  3. EIS-0287: Draft Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    Draft Environmental Impact Statement for the Idaho High-Level Waste & Facilities Disposition (December 1999)

  4. Low-level detection and quantification of Plutonium(III, IV, V, and VI) using a liquid core waveguide

    E-Print Network [OSTI]

    Wilson, Richard E.; Hu, Yung-Jin; Nitsche, Heino

    2003-01-01

    R. , Determination of Plutonium Oxidation States at TraceThe Absorption Spectra of Plutonium Ions in Perchloric Acidor company? Yes/No Plutonium Futures – The Science

  5. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques -- Preliminary Modeling Results Emphasizing Integration among Techniques

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01

    LBNL- Determining Plutonium Mass in Spent Fuel withSwinhoe. “Determination of Plutonium Content in Spent FuelS. Tobin, “Measurement of Plutonium in Spent Nuclear Fuel by

  6. Plutonium Immobilization Can Loading Preliminary Specifications

    SciTech Connect (OSTI)

    Kriikku, E.

    1998-11-25

    This report discusses the Plutonium Immobilization can loading preliminary equipment specifications and includes a process block diagram, process description, equipment list, preliminary equipment specifications, plan and elevation sketches, and some commercial catalogs. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas.

  7. NNSS Soils Monitoring: Plutonium Valley (CAU366)

    SciTech Connect (OSTI)

    Miller, Julianne J.; Mizell, Steve A.; Nikolich, George; Campbell, Scott

    2012-02-01

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites Contamination Area (CA) during precipitation runoff events.

  8. A Note on the Reaction of Hydrogen and Plutonium

    SciTech Connect (OSTI)

    Noone, Bailey C

    2012-08-15

    Plutonium hydride has many practical and experimental purposes. The reaction of plutonium and hydrogen has interesting characteristics, which will be explored in the following analysis. Plutonium is a radioactive actinide metal that emits alpha particles. When plutonium metal is exposed to air, the plutonium oxides and hydrides, and the volume increases. PuH{sub 2} and Pu{sub 2}O{sub 3} are the products. Hydrogen is a catalyst for plutonium's corrosion in air. The reaction can take place at room temperature because it is fairly insensitive to temperature. Plutonium hydride, or PuH{sub 2}, is black and metallic. After PuH{sub 2} is formed, it quickly flakes off and burns. The reaction of hydrogen and plutonium is described as pyrophoric because the product will spontaneously ignite when oxygen is present. This tendency must be considered in the storage of metal plutonium. The reaction is characterized as reversible and nonstoichiometric. The reaction goes as such: Pu + H{sub 2} {yields} PuH{sub 2}. When PuH{sub 2} is formed, the hydrogen/plutonium ratio is between 2 and 2.75 (approximately). As more hydrogen is added to the system, the ratio increases. When the ratio exceeds 2.75, PuH{sub 3} begins to form along with PuH{sub 2}. Once the ratio surpasses 2.9, only PuH{sub 3} remains. The volume of the plutonium sample increases because of the added hydrogen and the change in crystal structure which the sample undergoes. As more hydrogen is added to a system of metal plutonium, the crystal structure evolves. Plutonium has a crystal structure classified as monoclinic. A monoclinic crystal structure appears to be a rectangular prism. When plutonium reacts with hydrogen, the product PuH{sub 2}, becomes a fluorite structure. It can also be described as a face centered cubic structure. PuH{sub 3} forms a hexagonal crystal structure. As plutonium evolves from metal plutonium to plutonium hydride to plutonium trihydride, the crystal structure evolves from monoclinic to fluorite to hexagonal. This change in crystal structure as a result of adding hydrogen is a shared characteristic with other actinide elements. Americium is isostructural with plutonium because they both form cubic dihyrides and hexagonal trihydrides. Reacting hydrogen with plutonium has the practical application of separating plutonium from other materials that don't react as well with hydrogen. When plutonium is placed in a chamber where there is very little oxygen, it can react with hydrogen without igniting. The hydrogen plutonium reaction can then be reversed, thus regaining the separated plutonium. Another application of this reaction is that it can be used to predict how plutonium reacts with other substances. Deuterium and tritium are two isotopes of hydrogen that are of interest. They are known to react likewise to hydrogen because they have similar properties. The reaction of plutonium and isotopes of hydrogen can prove to be very informative.

  9. Interim Storage of Plutonium in Existing Facilities

    SciTech Connect (OSTI)

    Woodsmall, T.D.

    1999-05-10

    'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the reactor building. The storage life is projected to be ten years to allow the preparation of APSF. DOE has stipulated that there be no credible release during storage, since there are no design features in place to mitigate a release of plutonium (i.e. HEPA filters, facility containment boundaries, etc.). This mandate has presented most of the significant challenges to the safety analysis team. The shipping packages are designed to withstand certain accidents and conditions, but in order to take credit for these the storage environment must be strictly controlled. Damages to the packages from exposure to fire, dropping, crushing and other impact accidents have been analyzed, and appropriate preventative design features have been incorporated. Other efforts include the extension of the shipping life (roughly two years) to a suitable storage life of ten years. These issues include the effects of internal pressure increases, seal degradation and the presence of impurities. A process known as the Container Qualification Program has been conducted to address these issues. The KAMS project will be ready to receive the first shipment from Rocky Flats in January 2000. No credible design basis scenarios resulting in the release of plutonium exist. This work has been useful in the effort to provide a safer disposition of plutonium, but also the lessons learned and techniques established by the team will help with the analysis of future facility modifications.'

  10. Discussion Draft, DOE Framework

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalentLaboratory | National NuclearDiscoveringDiscrete FractureDraft, DOE

  11. Chemical Disposition of Plutonium in Hanford Site Tank Wastes

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Jones, Susan A.

    2015-05-07

    This report examines the chemical disposition of plutonium (Pu) in Hanford Site tank wastes, by itself and in its observed and potential interactions with the neutron absorbers aluminum (Al), cadmium (Cd), chromium (Cr), iron (Fe), manganese (Mn), nickel (Ni), and sodium (Na). Consideration also is given to the interactions of plutonium with uranium (U). No consideration of the disposition of uranium itself as an element with fissile isotopes is considered except tangentially with respect to its interaction as an absorber for plutonium. The report begins with a brief review of Hanford Site plutonium processes, examining the various means used to recover plutonium from irradiated fuel and from scrap, and also examines the intermediate processing of plutonium to prepare useful chemical forms. The paper provides an overview of Hanford tank defined-waste–type compositions and some calculations of the ratios of plutonium to absorber elements in these waste types and in individual waste analyses. These assessments are based on Hanford tank waste inventory data derived from separately published, expert assessments of tank disposal records, process flowsheets, and chemical/radiochemical analyses. This work also investigates the distribution and expected speciation of plutonium in tank waste solution and solid phases. For the solid phases, both pure plutonium compounds and plutonium interactions with absorber elements are considered. These assessments of plutonium chemistry are based largely on analyses of idealized or simulated tank waste or strongly alkaline systems. The very limited information available on plutonium behavior, disposition, and speciation in genuine tank waste also is discussed. The assessments show that plutonium coprecipitates strongly with chromium, iron, manganese and uranium absorbers. Plutonium’s chemical interactions with aluminum, nickel, and sodium are minimal to non-existent. Credit for neutronic interaction of plutonium with these absorbers occurs only if they are physically proximal in solution or the plutonium present in the solid phase is intimately mixed with compounds or solutions of these absorbers. No information on the potential chemical interaction of plutonium with cadmium was found in the technical literature. Definitive evidence of sorption or adsorption of plutonium onto various solid phases from strongly alkaline media is less clear-cut, perhaps owing to fewer studies and to some well-attributed tests run under conditions exceeding the very low solubility of plutonium. The several studies that are well-founded show that only about half of the plutonium is adsorbed from waste solutions onto sludge solid phases. The organic complexants found in many Hanford tank waste solutions seem to decrease plutonium uptake onto solids. A number of studies show plutonium sorbs effectively onto sodium titanate. Finally, this report presents findings describing the behavior of plutonium vis-à-vis other elements during sludge dissolution in nitric acid based on Hanford tank waste experience gained by lab-scale tests, chemical and radiochemical sample characterization, and full-scale processing in preparation for strontium-90 recovery from PUREX sludges.

  12. Nuclear Resonance Fluorescence to Measure Plutonium Mass in Spent Nuclear Fuel

    E-Print Network [OSTI]

    Ludewigt, Bernhard A

    2011-01-01

    and S.J. Thompson,“Determining Plutonium in Spent Fuel withTobin, “Determination of Plutonium Content in Spent FuelFluorescence to Measure Plutonium Mass in Spent Nuclear Fuel

  13. STUDIES IN THE NUCLEAR CHEMISTRY OF PLUTONIUM, AMERICIUM, AND CURIUM AND MASSES OF THE HEAVIEST ELEMENTS

    E-Print Network [OSTI]

    Glass, Richard Alois

    2011-01-01

    Nuclear Energy Series, Plutonium Project Record, Vol. 14B,Nuclear Energy Series, Plutonium Project Record, Vol. 9, p.Nuclear Energy Series, Plutonium Project Record, Vol. l4B,

  14. Complexation and redox interactions between aqueous plutonium and manganese oxide interfaces

    E-Print Network [OSTI]

    2001-01-01

    The Chemistry of Plutonium (American Nuclear Society,XAS studies with sorbed plutonium on tuff,” J. Synch. Rad.state determination of plutonium aquo ions using x-ray

  15. Fissile material disposition program: Screening of alternate immobilization candidates for disposition of surplus fissile materials

    SciTech Connect (OSTI)

    Gray, L.W.

    1996-01-08

    With the end of the Cold War, the world faces for the first time the need to dismantle vast numbers of ``excess`` nuclear weapons and dispose of the fissile materials they contain, together with fissile residues in the weapons production complex left over from the production of these weapons. If recently agreed US and Russian reductions are fully implemented, tens of thousands of nuclear weapons, containing a hundred tons or more of plutonium and hundreds of tonnes* of highly enriched uranium (HEU), will no longer be needed worldwide for military purposes. These two materials are the essential ingredients of nuclear weapons, and limits on access to them are the primary technical barrier to prospective proliferants who might desire to acquire a nuclear weapons capability. Theoretically, several kilograms of plutonium, or several times that amount of HEU, is sufficient to make a nuclear explosive device. Therefore, these materials will continue to be a potential threat to humanity for as long as they exist.

  16. Plutonium stabilization and handling (PuSH)

    SciTech Connect (OSTI)

    Weiss, E.V.

    1997-01-23

    This Functional Design Criteria (FDC) addresses construction of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. The major sections of the project are: site preparation; SPS Procurement, Installation, and Testing; storage vault modification; and characterization equipment additions. The SPS will be procured as part of a Department of Energy nationwide common procurement. Specific design crit1460eria for the SPS have been extracted from that contract and are contained in an appendix to this document.

  17. EIS-0244: Plutonium Finishing Plant Stabilization, Hanford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS evaluates the impacts on the human environment of: Stabilization of residual, plutonium-bearing materials at the PFP Facility to a form suitable for interim storage at the PFP Facility. Immobilization of residual plutonium-bearing materials at the PFP Facility. Removal of readily retrievable, plutonium-bearing materials left behind in process equipment, process areas, and air and liquid waste management systems as a result of historic uses.

  18. New way to predict plutonium Finding could lead to

    E-Print Network [OSTI]

    Savrasov, Sergej Y.

    New way to predict plutonium safety Finding could lead to improved storage of nuclear weapons of 2Science Front Page 2:14 PM ET Thursday, April 12, 2001 9/5/2003file://E:\\Homepages\\SavrasovHome\\Projects\\Research\\Plutonium, and Privacy Page 2 of 2Science Front Page 2:14 PM ET Thursday, April 12, 2001 9/5/2003file://E:\\Homepages\\SavrasovHome\\Projects\\Research\\Plutonium

  19. Dresden 1 plutonium recycle program. Final report

    SciTech Connect (OSTI)

    Bresnick, S.D.

    1980-01-01

    This is the final report on the Dresden 1 Plutonium Recycle Demonstration Program. It covers the work performed from July 1, 1978 to completion, which includes in-pool inspection of two fuel assemblies, removal of two fuel rods, and post-irradiation examination (PIE) of six fuel rods. Appendix A describes the inspection and rod removal operations, and Appendix B describes the PIE work.

  20. Plutonium utilisation in future UK PWRs

    SciTech Connect (OSTI)

    Thomas, G. M.; Worrall, A. [Nexia Solutions Ltd. (Part of the BNFL Group of Companies), Springfield's Works, Preston, Lancashire (United Kingdom)

    2006-07-01

    Plutonium recycling in the form of Mixed Oxide (MOX) fuels is already a reality in over 30 reactors in Europe (in Belgium, Switzerland, Germany and France). Japan also plans to use MOX in approximately 30% of its reactors in the near future[1]. This paper describes potential near to mid-term disposition strategies for the United Kingdom's stockpile of plutonium. In order to be confident that MOX fuel can be utilised effectively in Pressurised Water Reactors (PWRs) in the UK, details are given of studies carried out recently at Nexia Solutions on PWR cores loaded with MOX containing typical UK plutonium isotopic compositions. Three dimensional steady state neutronic models of a standard Westinghouse four loop PWR design are constructed using state of the art tools (Studsvik of America's Core Management System[2, 3, 4]). Initially, a standard 18-month equilibrium UO{sub 2} fuel cycle is generated, followed by safety analyses and fuel performance calculations to demonstrate its feasibility. This equilibrium UO{sub 2} core is then gradually transitioned through loading patterns containing increasing MOX core loading fractions. Finally, an equilibrium MOX core loading pattern is determined. Technical safety analyses are also carried out on the transition cores and the final equilibrium scenario to ensure that all of the MOX cores are robust from a technical and safety viewpoint. Once these studies are completed the annual fuel throughputs for each scenario can be determined and used to produce options for managing the UK's plutonium stockpile. This work is part of a wider exercise currently being carried out by Nexia Solutions to explore the options for the safe disposition of the UK civil stockpile of separated PUO{sub 2}. (authors)

  1. Equation of State of Uranium and Plutonium

    E-Print Network [OSTI]

    Dalton Ellery Girão Barroso

    2015-07-13

    The objective of this work is to define the parameters of the three-term equation of state for uranium and plutonium, appropriate for conditions in which these materials are subjected to strong shock compressions, as in cylindrical and spherical implosions. The three-term equation of state takes into account the three components of the pressure that resist to compression in the solid: the elastic or "cold" pressure (coulombian repulsion between atoms), the thermal pressure due to vibratory motion of atoms in the lattice of the solid and the thermal pressure of electrons thermally excited. The equation of state defined here permits also to take into account the variation of the specific heat with the transition of the solid to the liquid or gaseous state due to continued growth of temperature in strong shock compressions. In the definition of uranium equation of state, experimental data on the uranium compression, available in the open scientific literature, are used. In the plutonium case, this element was considered initially in the alpha-phase or stabilized in the delta-phase. In the last case, an abrupt and instantaneous transition to the alpha-phase was considered when the delta-phase plutonium is submitted to strong compressions.

  2. LLNL Conducts First Plutonium Shot Using the JASPER Gas Gun ...

    National Nuclear Security Administration (NNSA)

    Conducts First Plutonium Shot Using the JASPER Gas Gun | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile...

  3. Predicted Radiation Output from Several Kilograms of Plutonium...

    Office of Scientific and Technical Information (OSTI)

    Cycle & Fuel Materials(11); Nuclear Physics & Radiation Physics(73) radiation output, passive signature, plutonium oxide Word Cloud More Like This Full Text File size NAView Full...

  4. Geomorphology of plutonium in the Northern Rio Grande

    SciTech Connect (OSTI)

    Graf, W.L.

    1993-03-01

    Nearly all of the plutonium in the natural environment of the Northern Rio Grande is associated with soils and sediment, and river processes account for most of the mobility of these materials. A composite regional budget for plutonium based on multi-decadal averages for sediment and plutonium movement shows that 90 percent of the plutonium moving into the system is from atmospheric fallout. The remaining 10 percent is from releases at Los Alamos. Annual variation in plutonium flux and storage exceeds 100 percent. The contribution to the plutonium budget from Los Alamos is associated with relatively coarse sediment which often behaves as bedload in the Rio Grande. Infusion of these materials into the main stream were largest in 1951, 1952, 1957, and 1968. Because of the schedule of delivery of plutonium to Los Alamos for experimentation and weapons manufacturing, the latter two years are probably the most important. Although the Los Alamos contribution to the entire plutonium budget was relatively small, in these four critical years it constituted 71--86 percent of the plutonium in bedload immediately downstream from Otowi.

  5. Neutrons find "missing" magnetism of plutonium | ornl.gov

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

    Los Alamos National Laboratory 505-667-0471 Neutrons find "missing" magnetism of plutonium Doug Abernathy, left, ARCS instrument scientist at Oak Ridge National Laboratory,...

  6. Design of the improved plutonium canister assay system (IPCAS)

    SciTech Connect (OSTI)

    Abhold, M. E.; Baker, M. C.; Bourret, S. C.; Polk, P. J.; Vo, Duc T.

    2001-01-01

    The improved Plutonium Canister Assay System (iPCAS) is designed to detect gross and partial defects in the declared plutonium content of plutonium and MOX storage canisters during transfer to storage and process areas of the MOX fuel fabrication facility in Kokkasho, Japan. In addition, an associated Gamma Isotopics System (GIS) will be used to confirm facility-declared plutonium isotopics with accuracy sufficient to reduce the amount of destructive isotopic analysis needed. The design of the iPCAS instrument and its associated GIS is described and the expected performance of the instrument is discussed.

  7. Plutonium finishing plant safeguards and security systems replacement study

    SciTech Connect (OSTI)

    Klear, P.F.; Humphrys, K.L.

    1994-12-01

    This document provides the preferred alternatives for the replacement of the Safeguards and Security systems located at the Hanford Plutonium Finishing Plant.

  8. PLUTONIUM-238 RECOVERY FROM IRRADIATED NEPTUNIUM TARGETS USING...

    Office of Scientific and Technical Information (OSTI)

    proposes to re-establish a domestic capability for producing plutonium-238 (238Pu) to fuel radioisotope power systems primarily in support of future space missions. A...

  9. EIS-0276: Rocky Flats Plutonium Storage, Golden, Colorado

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposed action to provide safe interim storage of approximately 10 metric tons of plutonium at the Rocky Flats Environmental Technology Site (RFETS).

  10. President Truman Increases Production of Uranium and Plutonium...

    National Nuclear Security Administration (NNSA)

    Increases Production of Uranium and Plutonium | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  11. Supplementary data for "Relativistic density functional theory modeling of plutonium and

    E-Print Network [OSTI]

    Titov, Anatoly

    Supplementary data for "Relativistic density functional theory modeling of plutonium and americium equilibrium geometries of plutonium and americium oxide molecules (standard .xyz files separated by empty

  12. Procedure for plutonium determination using Pu(VI) spectra

    SciTech Connect (OSTI)

    Walker, L.F.; Temer, D.J.; Jackson, D.D.

    1996-09-01

    This document describes a simple spectrophotometric method for determining total plutonium in nitric acid solutions based on the spectrum of Pu(VI). Plutonium samples in nitric acid are oxidized to Pu(VI) with Ce(IV) and the net absorbance at the 830 nm peak is measured.

  13. Fuel bundle design for enhanced usage of plutonium fuel

    DOE Patents [OSTI]

    Reese, Anthony P. (San Jose, CA); Stachowski, Russell E. (Fremont, CA)

    1995-01-01

    A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced.

  14. The Human Plutonium Injection Experiments William Moss and Roger Eckhardt

    E-Print Network [OSTI]

    Massey, Thomas N.

    that was pertinent to those and LouisHempelmann #12;similar radiation experi- ments with humans. This article177 The Human Plutonium Injection Experiments William Moss and Roger Eckhardt T he human plutonium injection experiments carried out during and after the Manhattan Project have received tremendous noto

  15. PLUTONIUM ISOTOPES I N THE NORTH ATLANTIC KEN 0. BUESSELER

    E-Print Network [OSTI]

    Buesseler, Ken

    PLUTONIUM ISOTOPES I N THE NORTH ATLANTIC by KEN 0. BUESSELER B.A., University of California The a r t i f i c i a l radionuclide Plutonium (Pu) has been introduced i n t o the environment p r i m

  16. Recommended plutonium release fractions from postulated fires. Final report

    SciTech Connect (OSTI)

    Kogan, V.; Schumacher, P.M.

    1993-12-01

    This report was written at the request of EG&G Rocky Flats, Inc. in support of joint emergency planning for the Rocky Flats Plant (RFP) by EG&G and the State of Colorado. The intent of the report is to provide the State of Colorado with an independent assessment of any respirable plutonium releases that might occur in the event of a severe fire at the plant. Fire releases of plutonium are of interest because they have been used by EG&G to determine the RFP emergency planning zones. These zones are based on the maximum credible accident (MCA) described in the RFP Final Environmental Impact Statement (FEIS) of 1980, that MCA is assumed to be a large airplane crashing into a RFP plutonium building.The objective of this report was first, to perform a worldwide literature review of relevant release experiments from 1960 to the present and to summarize those findings, and second, to provide recommendations for application of the experimental data to fire release analyses at Rocky Flats. The latter step requires translation between experimental and expected RFP accident parameters, or ``scaling.`` The parameters of particular concern are: quantities of material, environmental parameters such as the intensity of a fire, and the physico-chemical forms of the plutonium. The latter include plutonium metal, bulk plutonium oxide powder, combustible and noncombustible wastes contaminated with plutonium oxide powder, and residues from plutonium extraction processes.

  17. Processing of Non-PFP Plutonium Oxide in Hanford Plants

    SciTech Connect (OSTI)

    Jones, Susan A.; Delegard, Calvin H.

    2011-03-10

    Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford’s Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400°C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP’s Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ~0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)3•9H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4.

  18. PLUTONIUM-238 PRODUCTION TARGET DESIGN STUDIES

    SciTech Connect (OSTI)

    Hurt, Christopher J [ORNL; Wham, Robert M [ORNL; Hobbs, Randall W [ORNL; Owens, R Steven [ORNL; Chandler, David [ORNL; Freels, James D [ORNL; Maldonado, G Ivan [ORNL

    2014-01-01

    A new supply chain is planned for plutonium-238 using existing reactors at the Oak Ridge National Laboratory (ORNL) and Idaho National Laboratory (INL) and existing chemical recovery facilities at ORNL. Validation and testing activities for new irradiation target designs have been conducted in three phases over a 2 year period to provide data for scale-up to production. Target design, qualification, target fabrication, and irradiation of fully-loaded targets have been accomplished. Data from post-irradiation examination (PIE) supports safety analysis and irradiation of future target designs.

  19. Thermal Stability Studies of Candidate Decontamination Agents for Hanford’s Plutonium Finishing Plant Plutonium-Contaminated Gloveboxes

    SciTech Connect (OSTI)

    Scheele, Randall D.; Cooper, Thurman D.; Jones, Susan A.; Ewalt, John R.; Compton, James A.; Trent, Donald S.; Edwards, Matthew K.; Kozelisky, Anne E.; Scott, Paul A.; Minette, Michael J.

    2005-09-29

    This report provides the results of PNNL's and Fluor's studies of the thermal stabilities of potential wastes arising from decontamination of Hanford's Plutonium Finishing Plant's plutonium contaminated gloveboxes. The candidate wastes arising from the decontamination technologies ceric nitrate/nitric acid, RadPro, Glygel, and Aspigel.

  20. Standard test method for nondestructive assay of plutonium, tritium and 241 Am by calorimetric assay

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    Standard test method for nondestructive assay of plutonium, tritium and 241 Am by calorimetric assay

  1. Standard practice for the ion exchange separation of uranium and plutonium prior to isotopic analysis

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    Standard practice for the ion exchange separation of uranium and plutonium prior to isotopic analysis

  2. Co-Design: Fabrication of Unalloyed Plutonium

    SciTech Connect (OSTI)

    Korzekwa, Deniece R. [Los Alamos National Laboratory; Knapp, Cameron M. [Los Alamos National Laboratory; Korzekwa, David A. [Los Alamos National Laboratory; Gibbs, John W [Northwestern University

    2012-07-25

    The successful induction casting of plutonium is a challenge which requires technical expertise in areas including physical metallurgy, surface and corrosion chemistry, materials science, electromagnetic engineering and a host of other technologies all which must be applied in concert. Here at LANL, we are employing a combined experimental and computational approach to design molds and develop process parameters needed to produce desired temperature profiles and improved castings. Computer simulations are performed using the commercial code FLOW-3D and the LANL ASC computer code TRUCHAS to reproduce the entire casting process starting with electromagnetic or radiative heating of the mold and metal and continuing through pouring with coupled fluid flow, heat transfer and non-isothermal solidification. This approach greatly reduces the time required to develop a new casting designs and also increases our understanding of the casting process, leading to a more homogeneous, consistent product and better process control. We will discuss recent casting development results in support of unalloyed plutonium rods for mechanical testing.

  3. Plutonium Detection with Straw Neutron Detectors

    SciTech Connect (OSTI)

    Mukhopadhyay, Sanjoy; Maurer, Richard; Guss, Paul

    2014-03-27

    A kilogram of weapons grade plutonium gives off about 56,000 neutrons per second of which 55,000 neutrons come from spontaneous fission of 240Pu (~6% by weight of the total plutonium). Actually, all even numbered isotopes (238Pu, 240Pu, and 242Pu) produce copious spontaneous fission neutrons. These neutrons induce fission in the surrounding fissile 239Pu with an approximate multiplication of a factor of ~1.9. This multiplication depends on the shape of the fissile materials and the surrounding material. These neutrons (typically of energy 2 MeV and air scattering mean free path >100 meters) can be detected 100 meters away from the source by vehicle-portable neutron detectors. [1] In our current studies on neutron detection techniques, without using 3He gas proportional counters, we designed and developed a portable high-efficiency neutron multiplicity counter using 10B-coated thin tubes called straws. The detector was designed to perform like commercially available fission meters (manufactured by Ortec Corp.) except instead of using 3He gas as a neutron conversion material, we used a thin coating of 10B.

  4. Equation of State of Uranium and Plutonium

    E-Print Network [OSTI]

    Barroso, Dalton Ellery Girão

    2015-01-01

    The objective of this work is to define the parameters of the three-term equation of state for uranium and plutonium, appropriate for conditions in which these materials are subjected to strong shock compressions, as in cylindrical and spherical implosions. The three-term equation of state takes into account the three components of the pressure that resist to compression in the solid: the elastic or "cold" pressure (coulombian repulsion between atoms), the thermal pressure due to vibratory motion of atoms in the lattice of the solid and the thermal pressure of electrons thermally excited. The equation of state defined here permits also to take into account the variation of the specific heat with the transition of the solid to the liquid or gaseous state due to continued growth of temperature in strong shock compressions. In the definition of uranium equation of state, experimental data on the uranium compression, available in the open scientific literature, are used. In the plutonium case, this element was co...

  5. Management of disused plutonium sealed sources

    SciTech Connect (OSTI)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Michael W [Los Alamos National Laboratory; Abeyta, Cristy [Los Alamos National Laboratory

    2010-01-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources since 1999, including more than 2,400 Plutonium (Pu)-238 sealed sources and 653 Pu-239-bearing sources that represent more than 10% of the total sources recovered by GTRI/OSRP to date. These sources have been recovered from hundreds of sites within the United States (US) and around the world. OSRP grew out of early efforts at the Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program, a loan-lease program that serviced 31 countries, as well as domestic users. In the conduct of these recovery operations, GTRI/OSRP has been required to solve problems related to knowledge-of-inventory, packaging and transportation of fissile and heat-source materials, transfer of ownership, storage of special nuclear material (SNM) both at US Department of Energy (DOE) facilities and commercially, and disposal. Unique issues associated with repatriation from foreign countries, including end user agreements required by some European countries and denials of shipment, will also be discussed.

  6. Description and procedures for synchrotron radiation, small molecule, single crystal crystallography of plutonium complexes at ALS beamline 11.3.1

    E-Print Network [OSTI]

    Gorden, A.E.V.; Raymond, K.N.; Shuh, D.K.

    2008-01-01

    Crystallography of Plutonium Complexes at ALS Beamlineof the Structural Parameters of Plutonium Complexes by Smallpreparation and growth of the plutonium complexes (crystals)

  7. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, J.P.

    1992-03-17

    A process is described for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.

  8. The mysterious world of plutonium metallurgy: Past and future

    SciTech Connect (OSTI)

    Hecker, S.S.; Hammel, E.F. [Los Alamos National Lab., NM (United States)

    1998-12-31

    The first atomic bomb detonated at the Trinity Site in New Mexico on July 16, 1945, used plutonium, a man-made element discovered < 5 yr earlier. The story of how Manhattan Project scientists and engineers tackled the mysteries of this element and fabricated it into the first atomic bomb is one of the most fascinating in the history of metallurgy and materials. The authors are currently trying to generate renewed interest in plutonium metallurgy because of the challenge posed by President Clinton, i.e., to keep the nuclear stockpile of weapons safe and reliable without nuclear testing. The stockpile stewardship challenge requires either a lifetime extension of the plutonium components or a remanufacture--neither of which can be verified by testing. In turn, this requires that one achieve a better fundamental understanding of plutonium. Of special interest is the effect of self-irradiation on the properties and on the long-term stability of plutonium and its alloys. Additional challenges arise from long-term concerns about disposing of plutonium and dealing with its environmental legacy. It is imperative to interest the next generation of students in these plutonium challenges.

  9. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, John P. (Downers Grove, IL)

    1992-01-01

    A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.

  10. Plutonium immobilization plant using glass in existing facilities at the Savannah River Site

    SciTech Connect (OSTI)

    DiSabatino, A., LLNL

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a glass immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors.

  11. Strategies for denaturing the weapons-grade plutonium stockpile

    SciTech Connect (OSTI)

    Buckner, M.R.; Parks, P.B.

    1992-10-01

    In the next few years, approximately 50 metric tons of weapons-grade plutonium and 150 metric tons of highly-enriched uranium (HEU) may be removed from nuclear weapons in the US and declared excess. These materials represent a significant energy resource that could substantially contribute to our national energy requirements. HEU can be used as fuel in naval reactors, or diluted with depleted uranium for use as fuel in commercial reactors. This paper proposes to use the weapons-grade plutonium as fuel in light water reactors. The first such reactor would demonstrate the dual objectives of producing electrical power and denaturing the plutonium to prevent use in nuclear weapons.

  12. Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels

    E-Print Network [OSTI]

    A. C. Hayes; H. R. Trellue; Michael Martin Nieto; W. B. WIlson

    2011-10-03

    This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

  13. Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels

    E-Print Network [OSTI]

    Hayes, A C; Nieto, Michael Martin; WIlson, W B

    2011-01-01

    This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

  14. Amarillo National Resource Center for Plutonium 1999 plan

    SciTech Connect (OSTI)

    NONE

    1999-01-30

    The purpose of the Amarillo National Resource Center for Plutonium is to serve the Texas Panhandle, the State of Texas and the US Department of Energy by: conducting scientific and technical research; advising decision makers; and providing information on nuclear weapons materials and related environment, safety, health, and nonproliferation issues while building academic excellence in science and technology. This paper describes the electronic resource library which provides the national archives of technical, policy, historical, and educational information on plutonium. Research projects related to the following topics are described: Environmental restoration and protection; Safety and health; Waste management; Education; Training; Instrumentation development; Materials science; Plutonium processing and handling; and Storage.

  15. DRAFT PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT (DPEIS) Prepared for the

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Draft DRAFT PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT (DPEIS) Prepared for the: REMOVAL ENVIRONMENTAL IMPACT STATEMENT REMOVAL AND DISPOSAL OF SEDIMENT AND RESTORATION OF WATER STORAGE AT JOHN REDMOND of Kansas, Kansas Water Office Title: Draft Programmatic Environmental Impact Statement ­ Removal

  16. ANALYTIC COMPLETION (DRAFT) CHARLES REZK

    E-Print Network [OSTI]

    Rezk, Charles

    ANALYTIC COMPLETION (DRAFT) CHARLES REZK Abstract. This is an expository treatment of what we call "analytic completion" of R- modules, which is a kind of completion defined in terms of quotients of power series modules. It is closely related to the left derived functors of adic completion, in which guise

  17. XII.1-Draft ATTACHMENT XII

    E-Print Network [OSTI]

    Kentucky, University of

    from the catalysis research work on Fischer- Tropsch synthesis work and the reaction engineering. Because of its experience with others in the Fischer-Tropsch Synthesis, the Badger Company was invitedXII.1-Draft ATTACHMENT XII Review of Fischer-Tropsch Work by Gulf Oil The Gulf-Badger process leads

  18. EIS-0445: EPA Notice of Availability of the Draft Environmental...

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

    of the Draft Environmental Impact Statement Mountaineer Commercial Scale Carbon Capture and Storage Project, Mason County, West Virginia Notice of Availability of Draft...

  19. EIS-0463: EPA Notice of Availability of Draft Environmental Impact...

    Office of Environmental Management (EM)

    of Draft Environmental Impact Statement Northern Pass Transmission Line Project, New Hampshire EPA announced the availability of the Draft Environmental Impact Statement...

  20. Barriers to CHP with Renewable Portfolio Standards, Draft White...

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

    Barriers to CHP with Renewable Portfolio Standards, Draft White Paper, September 2007 Barriers to CHP with Renewable Portfolio Standards, Draft White Paper, September 2007 The...

  1. The Department of Energy Releases Draft of Cybersecurity Risk...

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

    The Department of Energy Releases Draft of Cybersecurity Risk Management Process (RMP) Guideline for Public Comment (September 2011) The Department of Energy Releases Draft of...

  2. New Draft of Cybersecurity Risk Management Process (RMP) Guideline...

    Office of Environmental Management (EM)

    Draft of Cybersecurity Risk Management Process (RMP) Guideline Now Available for Public Comment (March 2012) New Draft of Cybersecurity Risk Management Process (RMP) Guideline Now...

  3. EIS-0241: Draft Environmental Impact Statement | Department of...

    Office of Environmental Management (EM)

    1: Draft Environmental Impact Statement EIS-0241: Draft Environmental Impact Statement The Department of Energy (DOE) limits electronic access to certain NEPA documents on this...

  4. EIS-0236-S1: Draft Supplemental Programmatic Environmental Impact...

    Energy Savers [EERE]

    EIS-0236-S1: Draft Supplemental Programmatic Environmental Impact Statement EIS-0236-S1: Draft Supplemental Programmatic Environmental Impact Statement This Supplemental DEIS...

  5. EIS-0409: EPA Notice of Availability of the Draft Environmental...

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

    Availability of the Draft Environmental Impact Statement Kemper County Integrated Gasification Combined-Cycle (IGCC) Project, Mississippi Notice of Availability for the Draft...

  6. National Electric Transmission Congestion Study - Draft for Public...

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

    - Draft for Public Comment August 2014 National Electric Transmission Congestion Study - Draft for Public Comment August 2014 On August 19, 2014, the Department issued a Federal...

  7. Agencies Publish Draft Environmental Impact Statement on Energy...

    Office of Environmental Management (EM)

    Draft Environmental Impact Statement on Energy Transport Corridor Designations in 11 Western States Agencies Publish Draft Environmental Impact Statement on Energy Transport...

  8. EIS-0477: Draft Environmental Impact Statement | Department of...

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

    77: Draft Environmental Impact Statement EIS-0477: Draft Environmental Impact Statement San Juan Basin Energy Connect Project; San Juan County, New Mexico and La Plata County,...

  9. Panel 2, Renewable Energy & Energy Efficiency Projects: Draft...

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

    the last 30 years: Vogtle LPO Has Financed Deployment of Groundbreaking Projects 4 Draft Renewable Energy & Efficient Energy Projects Solicitation 5 Draft Solicitation Can Provide...

  10. Progress Energy draft regarding Smart Grid RFI: Addressing Policy...

    Energy Savers [EERE]

    Progress Energy draft regarding Smart Grid RFI: Addressing Policy and Logistical Challenges Progress Energy draft regarding Smart Grid RFI: Addressing Policy and Logistical...

  11. EIS-0404: EPA Notice of Availability of the Draft Environmental...

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

    Draft Environmental Impact Statement EIS-0404: EPA Notice of Availability of the Draft Environmental Impact Statement Los Vaqueros Reservoir Expansion Project, California...

  12. Public Review Draft: A Method for Assessing Carbon Stocks, Carbon

    E-Print Network [OSTI]

    Public Review Draft: A Method for Assessing Carbon Stocks, Carbon Sequestration, and Greenhouse, and Zhu, Zhiliang, 2010, Public review draft; A method for assessing carbon stocks, carbon sequestration

  13. HAWAI'I CLEAN ENERGY DRAFT PROGRAMMATIC ENVIRONMENTAL IMPACT...

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

    HAWAI'I CLEAN ENERGY DRAFT PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT SUMMARY (DOEEIS-0459) APRIL 2014 COVER SHEET TITLE: Hawai'i Clean Energy Draft Programmatic Environmental...

  14. UNEP Handbook for Drafting Laws on Energy Efficiency and Renewable...

    Open Energy Info (EERE)

    UNEP Handbook for Drafting Laws on Energy Efficiency and Renewable Energy Resources Jump to: navigation, search Tool Summary LAUNCH TOOL Name: UNEP Handbook for Drafting Laws on...

  15. CEQ Extends Comment Period on Revised Draft Guidance on Consideration...

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

    on Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and the Effects of Climate Change in NEPA Reviews CEQ Extends Comment Period on Revised Draft Guidance on...

  16. DRAFT NEPA Guidance on Consideration of the Effects of Climate...

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

    DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and Greenhouse Gas Emissions DRAFT NEPA Guidance on Consideration of the Effects of Climate Change and...

  17. CEQ Issues Revised Draft Guidance on Consideration of Greenhouse...

    Energy Savers [EERE]

    Revised Draft Guidance on Consideration of Greenhouse Gas Emissions and the Effects of Climate Change in NEPA Reviews CEQ Issues Revised Draft Guidance on Consideration of...

  18. EIS-0312: Draft Environmental Impact Statement | Department of...

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

    2: Draft Environmental Impact Statement EIS-0312: Draft Environmental Impact Statement Fish and Wildlife Implementation Plan This EIS evaluates the environmental impacts associated...

  19. Federal Register Notice for Draft Addendum to Environmental Review...

    Energy Savers [EERE]

    Notice for Draft Addendum to Environmental Review Documents Concerning Exports of Natural Gas from the United States Federal Register Notice for Draft Addendum to...

  20. EA-1976D: Draft Environmental Assessment | Department of Energy

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

    EA-1976D: Draft Environmental Assessment EA-1976D: Draft Environmental Assessment Emera CNG, LLC Compressed Natural Gas Project, Florida DOE's National Energy Technology Laboratory...

  1. DRAFT Fifteenmile Management Plan 5. Fifteenmile Subbasin Management Plan

    E-Print Network [OSTI]

    DRAFT Fifteenmile Management Plan 5. Fifteenmile Subbasin Management Plan DRAFT May 25 2004 Group 5. FIFTEENMILE SUBBASIN MANAGEMENT PLAN Management Plans

  2. EIS-0503: DOE Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    of Draft Environmental Impact Statement New England Clean Power Link Project, Vermont DOE announced the availability of the Draft EIS to evaluate the potential...

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    Energy Savers [EERE]

    Extends Public Comment Period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement DOE Extends Public Comment Period for the Draft Uranium Leasing...

  4. Draft Advanced Nuclear Energy Solicitation Public Meeting Presentation...

    Office of Environmental Management (EM)

    Nuclear Energy Solicitation Public Meeting Presentation Draft Advanced Nuclear Energy Solicitation Public Meeting Presentation Draft Advanced Nuclear Solicitation presentation.pdf...

  5. DOE EAC Electricity Adequacy Report. Transmission Chapter DRAFT...

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

    EAC Electricity Adequacy Report. Transmission Chapter DRAFT- September 18, 2008 DOE EAC Electricity Adequacy Report. Transmission Chapter DRAFT- September 18, 2008 The purpose of...

  6. Blackout 2003: Conference for public review draft report on implementa...

    Energy Savers [EERE]

    for public review draft report on implementation of the task force recommendations Blackout 2003: Conference for public review draft report on implementation of the task force...

  7. EIS-0457: EPA Notice of Availability of a Draft Environmental...

    Office of Environmental Management (EM)

    7: EPA Notice of Availability of a Draft Environmental Impact Statement EIS-0457: EPA Notice of Availability of a Draft Environmental Impact Statement EIS-0457: Albany-Eugene...

  8. EIS-0481: DOE Notice of Availability of Draft Programmatic Environment...

    Energy Savers [EERE]

    DOE Notice of Availability of Draft Programmatic Environmental Impact Statement EIS-0481: DOE Notice of Availability of Draft Programmatic Environmental Impact Statement Engineered...

  9. EIS-0453: DOE Notice of Availability of Draft Environmental Impact...

    Office of Environmental Management (EM)

    DOE Notice of Availability of Draft Environmental Impact Statement EIS-0453: DOE Notice of Availability of Draft Environmental Impact Statement Recapitalization of Infrastructure...

  10. EIS-0450: DOE Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    DOE Notice of Availability of Draft Environmental Impact Statement EIS-0450: DOE Notice of Availability of Draft Environmental Impact Statement TransWest Express Transmission...

  11. EIS-0336: DOE Notice of Availability of the Draft Environmental...

    Office of Environmental Management (EM)

    DOE Notice of Availability of the Draft Environmental Impact Statement and Public Hearings EIS-0336: DOE Notice of Availability of the Draft Environmental Impact Statement and...

  12. EIS-0491: EPA Notice of Availability of Draft Environmental Impact...

    Office of Environmental Management (EM)

    EPA Notice of Availability of Draft Environmental Impact Statement EIS-0491: EPA Notice of Availability of Draft Environmental Impact Statement Lake Charles Liquefaction Project,...

  13. EIS-0396: DOE Notice of Availability of the Draft Programmatic...

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

    DOE Notice of Availability of the Draft Programmatic Environmental Impact Statement EIS-0396: DOE Notice of Availability of the Draft Programmatic Environmental Impact Statement...

  14. EIS-0486: EPA Notice of Availability of Draft Environmental Impact...

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

    EPA Notice of Availability of Draft Environmental Impact Statement EIS-0486: EPA Notice of Availability of Draft Environmental Impact Statement Plains & Eastern Clean Line...

  15. EIS-0491: FERC Notice of Availability of Draft Environmental...

    Energy Savers [EERE]

    1: FERC Notice of Availability of Draft Environmental Impact Statement EIS-0491: FERC Notice of Availability of Draft Environmental Impact Statement Lake Charles Liquefaction...

  16. EIS-0460: EPA Notice of Availability of the Draft Environmental...

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

    the Draft Environmental Impact Statement EIS-0460: EPA Notice of Availability of the Draft Environmental Impact Statement FutureGen 2.0 Project, Morgan County, Illinois The...

  17. EIS-0451: EPA Notice of Availability of a Draft Environmental...

    Energy Savers [EERE]

    51: EPA Notice of Availability of a Draft Environmental Impact Statement EIS-0451: EPA Notice of Availability of a Draft Environmental Impact Statement Hooper Springs Transmission...

  18. EIS-0481: EPA Notice of Availability of Draft Programmatic Environment...

    Office of Environmental Management (EM)

    EPA Notice of Availability of Draft Programmatic Environmental Impact Statement EIS-0481: EPA Notice of Availability of Draft Programmatic Environmental Impact Statement Engineered...

  19. EIS-0499: DOE Notice of Availability of Draft Environmental Impact...

    Office of Environmental Management (EM)

    DOE Notice of Availability of Draft Environmental Impact Statement EIS-0499: DOE Notice of Availability of Draft Environmental Impact Statement Great Northern Transmission Line...

  20. EIS-0499: EPA Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    9: EPA Notice of Availability of Draft Environmental Impact Statement EIS-0499: EPA Notice of Availability of Draft Environmental Impact Statement Great Northern Transmission Line...

  1. EIS-0387: EPA Notice of Availability of the Draft Environmental...

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

    Draft Environmental Impact Statement EIS-0387: EPA Notice of Availability of the Draft Environmental Impact Statement Y-12 National Security Complex Project, Oak Ridge, Tennessee...

  2. EIS-0424: EPA Notice of Availability of the Draft Environmental...

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

    EPA Notice of Availability of the Draft Environmental Impact Statement EIS-0424: EPA Notice of Availability of the Draft Environmental Impact Statement Klickitat Hatchery Complex...

  3. EIS-0483: EPA Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    3: EPA Notice of Availability of Draft Environmental Impact Statement EIS-0483: EPA Notice of Availability of Draft Environmental Impact Statement Estes to Flatiron Substation...

  4. EIS-0495: EPA Notice of Availability of Draft Environmental Impact...

    Office of Environmental Management (EM)

    5: EPA Notice of Availability of Draft Environmental Impact Statement EIS-0495: EPA Notice of Availability of Draft Environmental Impact Statement EIS-0495: Walla Walla Basin...

  5. EIS-0442: EPA Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    42: EPA Notice of Availability of Draft Environmental Impact Statement EIS-0442: EPA Notice of Availability of Draft Environmental Impact Statement Reauthorization of Permits,...

  6. EIS-0505: EPA Notice of Availability of Supplemental Draft Environment...

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

    EPA Notice of Availability of Supplemental Draft Environmental Impact Statement EIS-0505: EPA Notice of Availability of Supplemental Draft Environmental Impact Statement EIS-0505:...

  7. EIS-0400: EPA Notice of Availability of a Draft Environmental...

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

    a Draft Environmental Impact Statement EIS-0400: EPA Notice of Availability of a Draft Environmental Impact Statement Grandby Pumping Plant Switchyard Windy Gap Substation...

  8. EIS-0361: EPA Notice of Availability of the Draft Environmental...

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

    Draft Environmental Impact Statement EIS-0361: EPA Notice of Availability of the Draft Environmental Impact Statement Western Greenbier Co-Production Demonstration Project...

  9. EIS-0403: EPA Notice of Availability of the Draft Programmatic...

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

    Draft Programmatic Environmental Impact Statement EIS-0403: EPA Notice of Availability of the Draft Programmatic Environmental Impact Statement Solar Energy Development in Six...

  10. EIS-0455: EPA Notice of Availability of the Draft Environmental...

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

    Draft Environmental Impact Statement EIS-0455: EPA Notice of Availability of the Draft Environmental Impact Statement Genesis Solar Energy Project, Riverside County, CA...

  11. EIS-0391: EPA Notice of Availability of the Draft Environmental...

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

    the Draft Environmental Impact Statement EIS-0391: EPA Notice of Availability of the Draft Environmental Impact Statement Tank Closure and Waste Management for the Hanford Site,...

  12. CEQ Issues Revised Draft Guidance on Consideration of Greenhouse...

    Office of Environmental Management (EM)

    Draft Guidance on Consideration of Greenhouse Gas Emissions and the Effects of Climate Change in NEPA Reviews CEQ Issues Revised Draft Guidance on Consideration of Greenhouse...

  13. ARRAYS OF BOTTLES OF PLUTONIUM NITRATE SOLUTION

    SciTech Connect (OSTI)

    Margaret A. Marshall

    2012-09-01

    In October and November of 1981 thirteen approaches-to-critical were performed on a remote split table machine (RSTM) in the Critical Mass Laboratory of Pacific Northwest Laboratory (PNL) in Richland, Washington using planar arrays of polyethylene bottles filled with plutonium (Pu) nitrate solution. Arrays of up to sixteen bottles were used to measure the critical number of bottles and critical array spacing with a tight fitting Plexiglas® reflector on all sides of the arrays except the top. Some experiments used Plexiglas shells fitted around each bottles to determine the effect of moderation on criticality. Each bottle contained approximately 2.4 L of Pu(NO3)4 solution with a Pu content of 105 g Pu/L and a free acid molarity H+ of 5.1. The plutonium was of low 240Pu (2.9 wt.%) content. These experiments were sponsored by Rockwell Hanford Operations because of the lack of experimental data on the criticality of arrays of bottles of Pu solution such as might be found in storage and handling at the Purex Facility at Hanford. The results of these experiments were used “to provide benchmark data to validate calculational codes used in criticality safety assessments of [the] plant configurations” (Ref. 1). Data for this evaluation were collected from the published report (Ref. 1), the approach to critical logbook, the experimenter’s logbook, and communication with the primary experimenter, B. Michael Durst. Of the 13 experiments preformed 10 were evaluated. One of the experiments was not evaluated because it had been thrown out by the experimenter, one was not evaluated because it was a repeat of another experiment and the third was not evaluated because it reported the critical number of bottles as being greater than 25. Seven of the thirteen evaluated experiments were determined to be acceptable benchmark experiments. A similar experiment using uranyl nitrate was benchmarked as U233-SOL-THERM-014.

  14. Overview of Modeling and Simulations of Plutonium Aging

    SciTech Connect (OSTI)

    Schwartz, A J; Wolfer, W G

    2007-04-24

    Computer-aided materials research is now an integral part of science and technology. It becomes particularly valuable when comprehensive experimental investigations and materials testing are too costly, hazardous, or of excessive duration; then, theoretical and computational studies can supplement and enhance the information gained from limited experimental data. Such is the case for improving our fundamental understanding of the properties of aging plutonium in the nuclear weapons stockpile. The question of the effects of plutonium aging on the safety, security, and reliability of the nuclear weapons stockpile emerged after the United States closed its plutonium manufacturing facility in 1989 and decided to suspend any further underground testing of nuclear weapons in 1992. To address this, the Department of Energy's National Nuclear Security Administration (NNSA) initiated a research program to investigate plutonium aging, i.e., the changes with time of properties of Pu-Ga alloys employed in the nuclear weapons and to develop models describing these changes sufficiently reliable to forecast them for several decades. The November 26, 2006 press release by the NNSA summarizes the conclusions of the investigation, '...there appear to be no serious or sudden changes occurring, or expected to occur, in plutonium that would affect performance of pits beyond the well-understood, gradual degradation of plutonium materials'. Furthermore, 'These studies show that the degradation of plutonium in our nuclear weapons will not affect warhead reliability for decades', then NNSA Administrator Linton Brooks said. 'It is now clear that although plutonium aging contributes, other factors control the overall life expectancy of nuclear weapons systems'. The origin of plutonium aging is the natural decay of certain plutonium isotopes. Specifically, it is the process of alpha decay in which a plutonium atom spontaneously splits into a 5 MeV alpha particle and an 85keV uranium recoil. The alpha particle traverses the lattice, slowly loosing energy through electronic excitations, acquiring two electrons to become a helium atom, then finally coming to rest approximately 10 microns away with the generation of a few-hundred Frenkel pairs. The uranium recoil immediately displaces a couple-thousand Pu atoms from their original lattice sites. This process, which occurs at a rate of approximately 41 parts-per-million per year, is the source of potential property changes in aging plutonium. Plutonium aging encompasses many areas of research: radiation damage and radiation effects, diffusion of point defects, impurities and alloying elements, solid state phase transformations, dislocation dynamics and mechanical properties, equations of state under extreme pressures, as well as surface oxidation and corrosion. Theory, modeling, and computer simulations are involved to various degrees in many of these areas. The joint research program carried out at Lawrence Livermore National Laboratory and Los Alamos National Laboratory encompassed experimental measurements of numerous properties of newly fabricated reference alloys, archival material that have accumulated the effects of several decades of radioactive decay, and accelerated aging alloys in which the isotropic composition was adjusted to increase the rate of self-irradiation damage. In particular, the physical and chemical processes of nuclear materials degradation were to be studied individually and in great depth. Closely coupled to the experimental efforts are theory, modeling, and simulations. These efforts, validated by the experiments, aim to develop predictive models to evaluate the effects of age on the properties of plutonium. The need to obtain a scientific understanding of plutonium aging has revitalized fundamental research on actinides and plutonium in particular. For example, the experimental discovery of superconductivity in Pu-based compounds, the observation of helium bubbles in naturally aged material, and the measurement of phonon dispersion properties in gallium-stabilized delta plu

  15. Plutonium and Americium Geochemistry at Hanford: A Site Wide Review

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Felmy, Andrew R.

    2012-08-23

    This report was produced to provide a systematic review of the state-of-knowledge of plutonium and americium geochemistry at the Hanford Site. The report integrates existing knowledge of the subsurface migration behavior of plutonium and americium at the Hanford Site with available information in the scientific literature regarding the geochemistry of plutonium and americium in systems that are environmentally relevant to the Hanford Site. As a part of the report, key research needs are identified and prioritized, with the ultimate goal of developing a science-based capability to quantitatively assess risk at sites contaminated with plutonium and americium at the Hanford Site and the impact of remediation technologies and closure strategies.

  16. Worker Involvement Improves Safety at Hanford Site's Plutonium Finishing Plant

    Broader source: Energy.gov [DOE]

    Employees at the Hanford site are working together to find new and innovative ways to stay safe at the Plutonium Finishing Plant, one of the site’s most complex decommissioning projects.

  17. Standard specification for sintered (Uranium-Plutonium) dioxide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2001-01-01

    1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium. 1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Tit...

  18. Development of the Direct Fabrication Process for Plutonium Immobilization

    SciTech Connect (OSTI)

    Congdon, J.W.

    2001-07-10

    The current baseline process for fabricating pucks for the Plutonium Immobilization Program includes granulation of the milled feed prior to compaction. A direct fabrication process was demonstrated that eliminates the need for granulation.

  19. Crystalline ceramics: Waste forms for the disposal of weapons plutonium

    SciTech Connect (OSTI)

    Ewing, R.C.; Lutze, W. [New Mexico Univ., Albuquerque, NM (United States); Weber, W.J. [Pacific Northwest Lab., Richland, WA (United States)

    1995-05-01

    At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ``logs``; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium.

  20. Plutonium Isotopes in the Terrestrial Environment at the Savannah...

    Office of Scientific and Technical Information (OSTI)

    a mixture of weapons-grade, higher burn-up, and fallout material. This study provides a blue print for long term low level monitoring of plutonium in the environment. Authors:...

  1. Neutronic analysis of a proposed plutonium recycle assembly

    E-Print Network [OSTI]

    Solan, George Michael

    1975-01-01

    A method for the neutronic analysis of plutonium recycle assemblies has been developed with emphasis on relative power distribution prediction in the boundary area of vastly different spectral regions. Such regions are ...

  2. Interactions of Plutonium and Lanthanides with Ordered Mesoporous Materials

    E-Print Network [OSTI]

    Parsons-Moss, Tashi

    2014-01-01

    59 vii Figure 3.15. Pourbaix diagram for plutonium in aThere are several published Pourbaix diagrams that describeis also worth noting that Pourbaix diagrams describe systems

  3. Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0

    SciTech Connect (OSTI)

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15

    Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

  4. Evolving Metallurgical Behaviors in Plutonium from Self-Irradiation

    SciTech Connect (OSTI)

    Chung, B W; Lema, K E; Hiromoto, D S

    2009-05-05

    The plutonium alpha-decay leads to the age-related changes in physical properties. We review our experimental approaches including analytical techniques to assess the effects of extended aging on plutonium alloys, together with our recent results on age-related changes in physical and static mechanical properties. The ultimate goal of this work is to develop capabilities to predict metallurgical evolution driven by aging effects.

  5. Fuel bundle design for enhanced usage of plutonium fuel

    DOE Patents [OSTI]

    Reese, A.P.; Stachowski, R.E.

    1995-08-08

    A nuclear fuel bundle includes a square array of fuel rods each having a concentration of enriched uranium and plutonium. Each rod of an interior array of the rods also has a concentration of gadolinium. The interior array of rods is surrounded by an exterior array of rods void of gadolinium. By this design, usage of plutonium in the nuclear reactor is enhanced. 10 figs.

  6. Decontamination of Battelle-Columbus' Plutonium Facility. Final report

    SciTech Connect (OSTI)

    Rudolph, A.; Kirsch, G.; Toy, H.L. (comps.)

    1984-11-12

    The Plutonium Laboratory, owned and operated by Battelle Memorial Institute's Columbus Division, was located in Battelle's Nuclear Sciences area near West Jefferson, Ohio, approximately 17 miles west of Columbus, Ohio. Originally built in 1960 for plutonium research and processing, the Plutonium Laboratory was enlarged in 1964 and again in 1967. With the termination of the Advanced Fuel Program in March, 1977, the decision was made to decommission the Plutonium Laboratory and to decontaminate the building for unrestricted use. Decontamination procedures began in January, 1978. All items which had come into contact with radioactivity from the plutonium operations were cleaned or disposed of through prescribed channels, maintaining procedures to ensure that D and D operations would pose no risk to the public, the environment, or the workers. The entire program was conducted under the cognizance of DOE's Chicago Operations Office. The building which housed the Plutonium Laboratory has now been decontaminated to levels allowing it to house ordinary laboratory and office operations. A ''Finding of No Significant Impact'' (FNSI) was issued in May, 1980.

  7. Assessment of plutonium exposure in the Enewetak population by urinalysis

    SciTech Connect (OSTI)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.

    1997-07-01

    Since 1980, the inhabitants of Enewetak Atoll have been monitored periodically by scientists from Brookhaven National Laboratory for internally deposited radioactive material. In 1989, the establishment of fission track analysis and of a protocol for shipboard collection of 24-h urine samples significantly improved our ability to assess the internal uptake of plutonium. The purpose of this report is to show the distribution of plutonium concentrations in urine collected in 1989 and 1991, and to assess the associated committed effective doses for the Enewetak population based on a long-term chronic uptake of low-level plutonium. To estimate dose, we derived the plutonium dose-per-unit-uptake coefficients based on the dosimetric system of the International Commission on Radiological Protection. Assuming a continuous uptake, an integrated Jones`s plutonium urine excretion function was developed to interpret the Enewetak urine data. The Appendix shows how these values were derived. The committed effective doses were 0.2 mSv, calculated from the 1991 average plutonium content in 69 urine samples. 29 refs., 3 tabs.

  8. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques NGSI Research Overview and Update on NDA Techniques

    E-Print Network [OSTI]

    A., V. Mozin, S.J. Tobin, L.W. Cambell, J.R. Cheatham, C.R. Freeman, C.J. Gesh,

    2012-01-01

    Determining Plutonium Mass in Spent Fuel with Non-CN-184/137 Determining Plutonium Mass in Spent Fuel withthe Direct Measurement of Plutonium in Spent LWR Fuels by

  9. Microsoft Word - Draft Comprehensive Evaluation News Release...

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

    208-378-5101 Draft report from Federal agencies shows gains for Columbia River Basin fish Portland, Ore. - Federal agencies and their partners outlined today five years of...

  10. Draft Tank Closure & Waste Management EIS - Summary

    Office of Environmental Management (EM)

    91 Draft Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland, Washington Summary U.S. Department of Energy October 2009 Cover Sheet...

  11. DRAFT "Energy Advisory Committee" - Energy Storage Subcommittee...

    Energy Savers [EERE]

    Report: Revision 2 DRAFT "Energy Advisory Committee" - Energy Storage Subcommittee Report: Revision 2 Energy storage plays a vital role in all forms of business and affects the...

  12. EIS-0250: Draft Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE)

    Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain (July 1999)

  13. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

    SciTech Connect (OSTI)

    1997-09-01

    Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

  14. Follow-up on the Management of Plutonium-239 Sealed Sources Recovery...

    Office of Environmental Management (EM)

    on the Management of Plutonium-239 Sealed Sources Recovery Activities, OAS-M-06-09 Follow-up on the Management of Plutonium-239 Sealed Sources Recovery Activities, OAS-M-06-09 The...

  15. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, February 1, 1998--April 30, 1998

    SciTech Connect (OSTI)

    NONE

    1998-06-01

    Activities from the Amarillo National Resource Center for Plutonium are described. Areas of work include materials science of nuclear and explosive materials, plutonium processing and handling, robotics, and storage.

  16. PLUTONIUM LOADING CAPACITY OF REILLEX HPQ ANION EXCHANGE COLUMN - AFS-2 PLUTONIUM FLOWSHEET FOR MOX

    SciTech Connect (OSTI)

    Kyser, E.; King, W.; O'Rourke, P.

    2012-07-26

    Radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the dependence of column loading performance on the feed composition in the H-Canyon dissolution process for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). These loading experiments show that a representative feed solution containing {approx}5 g Pu/L can be loaded onto Reillex{trademark} HPQ resin from solutions containing 8 M total nitrate and 0.1 M KF provided that the F is complexed with Al to an [Al]/[F] molar ratio range of 1.5-2.0. Lower concentrations of total nitrate and [Al]/[F] molar ratios may still have acceptable performance but were not tested in this study. Loading and washing Pu losses should be relatively low (<1%) for resin loading of up to 60 g Pu/L. Loading above 60 g Pu/L resin is possible, but Pu wash losses will increase such that 10-20% of the additional Pu fed may not be retained by the resin as the resin loading approaches 80 g Pu/L resin.

  17. The Effect of Sedimentation on Plutonium Transport in Fourmile Branch

    SciTech Connect (OSTI)

    Chen, K.F.

    2002-02-21

    The major mechanisms of radioactive material transport and fate in surface water are sources, dilution, advection and dispersion of radionuclides by flow and surface waves, radionuclide decay, and interaction between sediment and radionuclides. STREAM II, an aqueous transport module of the Savannah River Site emergency response WIND system, accounts for the source term, and the effects of dilution, advection and dispersion. Although the model has the capability to account for nuclear decay, due to the short time interval of interest for emergency response, the effect of nuclear decay is very small and so it is not employed. The interactions between the sediment and radionuclides are controlled by the flow conditions and physical and chemical characteristics of the radionuclides and the sediment constituents. The STREAM II version used in emergency response must provide results relatively quickly; it therefore does not model the effects of sediment deposition/resuspension. This study estimates the effects of sediment deposition/resuspension on aqueous plutonium transport in Fourmile Branch. There are no measured data on plutonium transport through surface water available for direct model calibration. Therefore, a literature search was conducted to find the range of plutonium partition coefficients based on laboratory experiments and field measurements. A sensitivity study of the calculated plutonium peak concentrations as a function of the input parameter of partition coefficient was then performed. Finally, an estimation of the plutonium partition coefficient was made for the Fourmile Branch.

  18. DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    SciTech Connect (OSTI)

    BERLIN, G.T.

    2004-01-21

    This paper describes the technical approach being used to demolish a plutonium-contaminated processing facility at the Hanford Site. This project represents the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent one of the first plutonium facilities in the DOE complex to be demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contamination structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially-available equipment, materials, and services, this project is demonstrating that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or construct large enclosures. The project is utilizing an excavator with purpose-built concrete shears, diamond circular saws, water misting and fogging equipment, specialized fixatives and dust suppressant mixtures, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Between the months of October and December 2003, approximately 85 percent of the footprint of the 233-S Facility had been demolished and properly disposed. Demolition of the remaining and more technically-challenging portion of the facility is expected to be completed by April 2004.

  19. Chloride-catalyzed corrosion of plutonium in glovebox atmospheres

    SciTech Connect (OSTI)

    Burgess, M. [ed.; Haschke, J.M.; Allen, T.H.; Morales, L.A.; Jarboe, D.M.; Puglisi, C.V.

    1998-04-01

    Characterization of glovebox atmospheres and the black reaction product formed on plutonium surfaces shows that the abnormally rapid corrosion of components in the fabrication line is consistent with a complex salt-catalyzed reaction involving gaseous hydrogen chloride (HCl) and water. Analytical data verify that chlorocarbon and HCl vapors are presented in stagnant glovebox atmospheres. Hydrogen chloride concentrations approach 7 ppm at some locations in the glovebox line. The black corrosion product is identified as plutonium monoxide monohydride (PuOH), a product formed by hydrolysis of plutonium in liquid water and salt solutions at room temperature. Plutonium trichloride (PuCl{sub 3}) produced by reaction of HCl at the metal surface is deliquescent and apparently forms a highly concentrated salt solution by absorbing moisture from the glovebox atmosphere. Rapid corrosion is attributed to the ensuing salt-catalyzed reaction between plutonium and water. Experimental results are discussed, possible involvement of hydrogen fluoride (HF) is examined, and methods of corrective action are presented in this report.

  20. Plutonium disposition study phase 1b final report

    SciTech Connect (OSTI)

    NONE

    1993-09-15

    This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerning the PDR Phase 1a report are included in Appendix A.

  1. PRESSURE DEVELOPMENT IN SEALED CONTAINERS WITH PLUTONIUM BEARING MATERIALS

    SciTech Connect (OSTI)

    Duffey, J.; Livingston, R.

    2010-02-01

    Gas generation by plutonium-bearing materials in sealed containers has been studied. The gas composition and pressure are determined over periods from months to years. The Pu-bearing materials studied represent those produced by all of the major processes used by DOE in the processing of plutonium and include the maximum amount of water (0.5% by weight) allowed by DOE's 3013 Standard. Hydrogen generation is of high interest and the Pu-bearing materials can be classed according to how much hydrogen is generated. Hydrogen generation by high-purity plutonium oxides packaged under conditions typical for actual 3013 materials is minimal, with very low generation rates and low equilibrium pressures. Materials with chloride salt impurities have much higher hydrogen gas generation rates and result in the highest observed equilibrium hydrogen pressures. Other materials such as those with high metal oxide impurities generate hydrogen at rates in between these extremes. The fraction of water that is converted to hydrogen gas as equilibrium is approached ranges from 0% to 25% under conditions typical of materials packaged to the 3013 Standard. Generation of both hydrogen and oxygen occurs when liquid water is present. The material and moisture conditions that result in hydrogen and oxygen generation for high-purity plutonium oxide and chloride salt-bearing plutonium oxide materials have been characterized. Other gases that are observed include nitrous oxide, carbon dioxide, carbon monoxide, and methane.

  2. Plutonium-238 observations as a test of modeled transport and surface deposition of meteoric smoke particles

    E-Print Network [OSTI]

    Chipperfield, Martyn

    Plutonium-238 observations as a test of modeled transport and surface deposition of meteoric smoke chemistry-climate model (CCM) to simulate the transport and deposition of plutonium- 238 oxide nanoparticles. P. Chipperfield, and J. M. C. Plane (2013), Plutonium-238 observations as a test of modeled

  3. Spallation-Fission Competition in Heaviest Elements; Helium Ion Induced Reactions in Plutonium Isotopes

    E-Print Network [OSTI]

    Glass, Richard A.; Carr, Robert J.; Cobble, James W.; Seaborg, Glenn T.

    1956-01-01

    Nuclear Energy Series, Plutonium Project Record, Vol. 1 4Nuclear Energy S e r i e s , Plutonium P r o j e c t RecordNuclear Energy S e r i e s , Plutonium P r o j e c t Record,

  4. Orientation Imaging Microscopy of Plutonium: Grain Structure and Oxidation David P. Moore1

    E-Print Network [OSTI]

    Orientation Imaging Microscopy of Plutonium: Grain Structure and Oxidation David P. Moore1 , Amanda the microstructure and oxidation of plutonium (Pu) in recent years. Two of the more powerful techniques for studying widely used in many areas of materials science, their application to plutonium is still largely

  5. j . Phycol. 17, 346-352 (1981) SORPTION OF PLUTONIUM-237 BY TWO SPECIES OF

    E-Print Network [OSTI]

    Yen, Jeannette

    1981-01-01

    j . Phycol. 17, 346-352 (1981) SORPTION OF PLUTONIUM-237 BY TWO SPECIES OF MARINE PHYTOPLANKTON factor; phytoplankton, ma- rine; radionuclide; plutonium-237; sorption kinetics, pas- sive mechanism in the biological control of radionuclide distribtuion in aquatic systems. Algae, when exposed to plutonium

  6. Acoustic Measurements of the Elastic Properties and Quality of Plutonium and Uranium Based Oxide Fuels

    E-Print Network [OSTI]

    Acoustic Measurements of the Elastic Properties and Quality of Plutonium and Uranium Based Oxide ranged from depleted uranium oxide to mixtures of plutonium and depleted uranium oxide (MOX) and mixed.8Pu0.2 92 121 152.6 63.3 281Plutonium Futures -- The Science 2010, September 19-23, 2010, Keystone, CO

  7. Standard practice for preparation and dissolution of plutonium materials for analysis

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquants of the dissolved samples are dispensed on a weight basis when one of the analyses must be highly reliable, such as plutonium assay; otherwise they are dispensed on a volume basis. 1.2 The treatments, in order of presentation, are as follows: Procedure Title Section Dissolution of Plutonium Metal with Hydrochloric Acid 9.1 Dissolution of Plutonium Metal with Sulfuric Acid 9.2 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxide by the Sealed-Reflux Technique 9.3 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxides by Sodium Bisulfate Fusion 9.4 Dissolution of Uranium-Plutonium Mixed Oxides and Low-Fired Plutonium Oxide in Beakers 9.5 1.3 The values stated in SI units are to be re...

  8. Evidence for Hydrogen Induced Vacancies in Plutonium Metal Scott Richmond, Joseph Anderson, Jeff Abes

    E-Print Network [OSTI]

    Evidence for Hydrogen Induced Vacancies in Plutonium Metal Scott Richmond, Joseph Anderson, Jeff@lanl.gov INTRODUCTION The solubility of hydrogen in plutonium metal was recently measured [1]. Based on the solubility data, the properties of plutonium and helium release data, the authors will show that hydrogen induced

  9. Neutron and gamma-ray cross-correlation measurements of plutonium oxide powder

    E-Print Network [OSTI]

    Eustice, Ryan

    Neutron and gamma-ray cross-correlation measurements of plutonium oxide powder S.D. Clarke a,Ã, M: Cross-correlation Plutonium oxide Special nuclear material Liquid scintillator MCNP-PoliMi a b s t r a c t For the first time, measurements of the time-dependent cross-correlation distributions of plutonium oxide have

  10. Relativistic density functional theory modeling of plutonium and americium higher oxide molecules

    E-Print Network [OSTI]

    Titov, Anatoly

    Relativistic density functional theory modeling of plutonium and americium higher oxide molecules of plutonium and americium higher oxide molecules Andréi Zaitsevskii,1,2,a) Nikolai S. Mosyagin,2,3 Anatoly V of plutonium and americium higher oxide molecules (actinide oxidation states VI through VIII) by two

  11. Density and Tensile Properties Changed by Aging Plutonium

    SciTech Connect (OSTI)

    Chung, B W; Choi, B W; Thompson, S R; Woods, C H; Hopkins, D J; Ebbinghaus, B B

    2005-03-14

    We present volume, density, and tensile property change observed from both naturally and accelerated aged plutonium alloys. Accelerated alloys are plutonium alloys with a fraction of Pu-238 to accelerate the aging process by approximately 18 times the rate of unaged weapons-grade plutonium. After thirty-five equivalent years of aging on accelerated alloys, the dilatometry shows the samples at 35 C have swelled in volume by 0.12 to 0.14% and now exhibit a near linear volume increase due to helium in-growth while showing possible surface effects on samples at 50 C and 65 C. The engineering stress of the accelerated alloy at 18 equivalent years increased significantly compared to at 4.5 equivalent years.

  12. Thermal Cycling on Fatigue Failure of the Plutonium Vitrification Melter

    SciTech Connect (OSTI)

    Jordan, Jeffrey; Gorczyca, Jennifer

    2009-02-11

    One method for disposition of excess plutonium is vitrification into cylindrical wasteforms. Due to the hazards of working with plutonium, the vitrification process must be carried out remotely in a shielded environment. Thus, the equipment must be easily maintained. With their simple design, induction melters satisfy this criterion, making them ideal candidates for plutonium vitrification. However, due to repeated heating and cooling cycles and differences in coefficients of thermal expansion of contacting materials fatigue failure of the induction melter is of concern. Due to the cost of the melter, the number of cycles to failure is critical. This paper presents a method for determining the cycles to failure for an induction melter by using the results from thermal and structural analyses as input to a fatigue failure model.

  13. Supercritical fluid carbon dioxide cleaning of plutonium parts

    SciTech Connect (OSTI)

    Hale, S.J.

    1991-12-31

    Supercritical fluid carbon dioxide is under investigation in this work for use as a cleaning solvent for the final cleaning of plutonium parts. These parts must be free of organic residue to avoid corrosion in the stockpile. Initial studies on stainless steel and full-scale mock-up parts indicate that the oils of interest are easily and adequately cleaned from the metal surfaces with supercritical fluid carbon dioxide. Results from compatibility studies show that undesirable oxidation or other surface reactions are not occurring during exposure of plutonium to the supercritical fluid. Cleaning studies indicate that the oils of interest are removed from the plutonium surface under relatively mild conditions. These studies indicate that supercritical fluid carbon dioxide is a very promising cleaning medium for this application.

  14. Plutonium (III) and uranium (III) nitrile complexes

    SciTech Connect (OSTI)

    Enriquez, A. E.; Matonic, J. H.; Scott, B. L.; Neu, M. P.

    2002-01-01

    Iodine oxidation of uranium and plutonium metals in tetrahydrofuran and pyridine form AnI{sub 3}(THF){sub 4} and AnI{sub 3}(py){sub 4} (An = Pu, U). These compounds represent convenient entries Into solution An(III) chemistry in organic solvents. Extensions of the actinide metal oxidation methodology in nitrile solvents by I{sub 2}, AgPF{sub 6}, and TIPF{sub 6} are presented here. Treatment of Pu{sup 0} in acetonitrile with iodine yields a putative PuI{sub 3}(NCMe){sub x} intermediate which can be trapped with the tripodal nitrogen donor ligand tpza (tpza = (tris[(2-pyrazinyl)methyl]amine)) and forms the eight-coordinate complex (tpza)PuI{sub 3}(NCMe). Treatment of excess U{sup 0} metal by iodine in acetonitrile afforded a brown crystalline mixed valence complex, [U(NCMe){sub 9}][UI{sub 6}][I], instead of UI{sub 3}(NCMe){sub 4}. The analogous reaction in bezonitrile forms red crystalline UI{sub 4}(NCPh){sub 4}. In contrast, treatment of UI{sub 3}(THF){sub 4} with excess acetonitrile cleanly generates [U(NCMe){sub 9}][I]{sub 3}. Oxidation of Pu{sup 0} by either TI(I) or Ag(I) hexafluorophosphate salts generates a nine-coordinate homoleptic acetonitrile adduct [Pu(NCMe){sub 9}][PF{sub 6}]{sub 3}. Attempts to oxidize U{sub 0} with these salts were unsuccessful.

  15. A perspective on safeguarding and monitoring of excess military plutonium

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1994-10-02

    The purpose of this paper is to provide a perspective and framework for the development of safeguarding and monitoring procedures for the various stages of disposition of excess military plutonium. The paper briefly outlines and comments on some of the issues involved in safeguarding and monitoring excess military plutonium as it progresses from weapons through dismantlement, to fabrication as reactor fuel, to use in a reactor, and finally to storage and disposal as spent fuel. {open_quotes}Military{close_quotes} refers to ownership, and includes both reactor-grade and weapon-grade plutonium. {open_quotes}Excess{close_quotes} refers to plutonium (in any form) that a government decides is no longer needed for military use and can be irrevocably removed from military stockpiles. Many of the issues and proposals presented in this paper are based on, or are similar to, those mentioned in the National Academy of Sciences (NAS) report on excess military plutonium. Safeguards for plutonium disposition are discussed elsewhere in terms of requirements established by the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (NRC), and the International Atomic Energy Agency (IAEA). Here, the discussion is less specific. The term {open_quotes}safeguarding{close_quotes} is used broadly to refer to materials control and accountancy (MC&A), containment and surveillance (C&S), and physical protection of nuclear materials by the state that possesses those materials. This is also referred to as material protection, control, and accountancy (MPCA). The term {open_quotes}safeguarding{close_quotes} was chosen for brevity and to distinguish MPCA considered in this paper from international or IAEA safeguards. {open_quotes}Monitoring{close_quotes} is used to refer to activities designed to assure another party (state or international organization) that the nuclear materials of the host state (the United States or Russia) are secure and not subject to unauthorized use.

  16. PLUTONIUM-URANIUM EXTRACTION (PUREX) FACILITY ALARACT DEMONSTRATION FOR FILTER HOUSING

    SciTech Connect (OSTI)

    LEBARON GJ

    2008-11-25

    This document presents an As Low As Reasonably Achievable Control Technology (ALARACT) demonstration for evaluating corrosion on the I-beam supporting filter housing No.9 for the 291-A-l emission unit of the Plutonium-Uranium Extraction (PUREX) Facility, located in the 200 East Area of the Hanford Site. The PUREX facility is currently in surveillance and maintenance mode. During a State of Washington, Department of Health (WDOH) 291-A-l emission unit inspection, a small amount of corrosion was observed at the base of a high-efficiency particulate air (HEPA) filter housing. A series of internal and external inspections identified the source of the corrosion material as oxidation of a small section of one of the carbon steel I-beams that provides support to the stainless steel filter housing. The inspections confirmed the corrosion is isolated to one I-beam support location and does not represent any compromise of the structural support or filter housing integrity. Further testing and inspections of the support beam corrosion and its cause were conducted but did not determine the cause. No definitive evidence was found to support any degradation of the housing. Although no degradation of the housing was found, a conservative approach will be implemented. The following actions will be taken: (1) The current operating filter housing No.9 will be removed from service. (2) The only remaining available filter housings (No.1, No.2, and No.3) will be placed in service. These filter housings have new HEPA filters fitted with stainless steel frames and faceguards which were installed in the spring of 2007. (3) Filter housings No.5 and No.10 will be put on standby as backups. To document the assessment of the unit, a draft ALARACT filter housing demonstration for the PUREX filter housing was prepared, and informally provided to WDOH on August 7, 2008. A follow up WDOH response to the draft ALARACT filter housing demonstration for the PUREX filter housing questioned whether deteriorated galvanized filter faceguards discovered during an internal filter housing inspection met American Society of Mechanical Engineers (ASME) AG-l or Military Specification (MIL) 51068 standards. The filter system was designed and installed prior to the issuance of AG-l, February 1986; however, MIL 51068 did require galvanized faceguards. The faceguards are not necessary for filtration or structural purposes; it is concluded that the system is in compliance with the intent of the applicable standard. Appendix B provides supporting information to address this issue.

  17. A technical basis for proliferation-resistant plutonium disposition

    SciTech Connect (OSTI)

    Laidler, J.; DeVolpi, A.

    1995-12-01

    Final disposition of fissile materials cannot be reached without intermediate stages. Major uncertainties now exist in the physical and chemical form suitable for ultimate disposition. Forecasts are heavily dependent on interim experience and on policy evolution. Meanwhile, technical options for disposition can be examined and tested. Two of these options -- pyrochemical conditioning and vitrification -- have been the subject of research and development at Argonne. Using these technologies, weapons plutonium could be demilitarized by being blended with spent fuel. End-products suitable for disposal of weapons plutonium are particularly controversial because of factors associated with alternative energy uses, potential recovery for weapons, nuclear safeguards, criticality safety, and changing standards.

  18. XANES Identification of Plutonium Speciation in RFETS Samples

    SciTech Connect (OSTI)

    LoPresti, V.; Conradson, S.D.; Clark, D.L.

    2009-06-03

    Using primarily X-ray absorption near edge spectroscopy (XANES) with standards run in tandem with samples, probable plutonium speciation was determined for 13 samples from contaminated soil, acid-splash or fire-deposition building interior surfaces, or asphalt pads from the Rocky Flats Environmental Technology Site (RFETS). Save for extreme oxidizing situations, all other samples were found to be of Pu(IV) speciation, supporting the supposition that such contamination is less likely to show mobility off site. EXAFS analysis conducted on two of the 13 samples supported the validity of the XANES features employed as determinants of the plutonium valence.

  19. Draft Agenda | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8,Department of2 Federal Register /1 PiotrDraft AdvancedAgenda

  20. Draft Meeting Summary Page 1

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalentLaboratory |Sector FullDOEUrsulaNatural GasCCommittee-Draft

  1. Plutonium immobilization plant using glass in new facilities at the Savannah River Site

    SciTech Connect (OSTI)

    DiSabatino, A.

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a glass immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors.

  2. Minutes of the 28th Annual Plutonium Sample Exchange Meeting. Part II: metal sample exchange

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    Contents of this publication include the following list of participating laboratories; agenda; attendees; minutes of October 25 and 26 meeting; and handout materials supplied by speakers. The handout materials cover the following: statistics and reporting; plutonium - chemical assay 100% minus impurities; americium neptunium, uranium, carbon and iron data; emission spectroscopy data; plutonium metal sample exchange; the calorimetry sample exchange; chlorine determination in plutonium metal using phyrohydrolysis; spectrophotometric determination of 238-plutonium in oxide; plutonium measurement capabilities at the Savannah River Plant; and robotics in radiochemical laboratory.

  3. Computation Results from a Parametric Study to Determine Bounding Critical Systems of Homogeneously Water-Moderated Mixed Plutonium--Uranium Oxides

    SciTech Connect (OSTI)

    Shimizu, Y.

    2001-01-11

    This report provides computational results of an extensive study to examine the following: (1) infinite media neutron-multiplication factors; (2) material bucklings; (3) bounding infinite media critical concentrations; (4) bounding finite critical dimensions of water-reflected and homogeneously water-moderated one-dimensional systems (i.e., spheres, cylinders of infinite length, and slabs that are infinite in two dimensions) that were comprised of various proportions and densities of plutonium oxides and uranium oxides, each having various isotopic compositions; and (5) sensitivity coefficients of delta k-eff with respect to critical geometry delta dimensions were determined for each of the three geometries that were studied. The study was undertaken to support the development of a standard that is sponsored by the International Standards Organization (ISO) under Technical Committee 85, Nuclear Energy (TC 85)--Subcommittee 5, Nuclear Fuel Technology (SC 5)--Working Group 8, Standardization of Calculations, Procedures and Practices Related to Criticality Safety (WG 8). The designation and title of the ISO TC 85/SC 5/WG 8 standard working draft is WD 14941, ''Nuclear energy--Fissile materials--Nuclear criticality control and safety of plutonium-uranium oxide fuel mixtures outside of reactors.'' Various ISO member participants performed similar computational studies using their indigenous computational codes to provide comparative results for analysis in the development of the standard.

  4. Plutonium solution storage in plastic bottles: Operational experience and safety issues

    SciTech Connect (OSTI)

    Conner, W.V.

    1995-03-15

    Computer spread sheet models were developed to gain a better understanding of the factors that lead to pressurization and failure of plastic bottles containing plutonium solutions. These models were developed using data obtained from the literature on gas generation rates for plutonium solutions. Leak rates from sealed plastic bottles were obtained from bottle leak tests conducted at Rocky Flats. Results from these bottle leak tests showed that narrow mouth four liter bottles will seal much better than wide mouth four liter bottles. The gas generation rate and leak rate data were used to develop models for predicting the rate of pressurization and maximum pressures expected in sealed bottles of plutonium solution containing various plutonium and acid concentrations. The computer models were used to develop proposed time limits for storing or transporting plutonium solutions in sealed plastic bottles. For plutonium solutions containing < 1.5 g/l, maximum safe storage times from 4 weeks to 12 months are proposed. The maximum safe storage times vary depending upon the plutonium concentration in the solution. Low concentration plutonium solutions can be stored safely for longer periods of time than high concentration plutonium solutions. For solutions containing > 1.5 g/l plutonium, storage in sealed bottles should not be allowed. However, transportation of higher concentration plutonium solution in sealed bottles is required, and safe transportation times of 1 shift to 6 days are proposed.

  5. Standard test method for plutonium by Iron (II)/Chromium (VI) amperometric titration

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This test method covers the determination of plutonium in unirradiated nuclear-grade plutonium dioxide, uranium-plutonium mixed oxides with uranium (U)/plutonium (Pu) ratios up to 21, plutonium metal, and plutonium nitrate solutions. Optimum quantities of plutonium to measure are 7 to 15 mg. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  6. Final Draft *** Final Draft *** Final Draft Hanford Advisory Board 2013 Program of Work

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverse (Journal Article) | SciTechSubmittedEcologist Final Site-WideDraft *** Final

  7. Business Plan in Brief : Draft.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    1994-06-01

    Competition is revolutionizing the electricity industry, and utilities may never be the same. In the past two decades, government deregulation has transformed the airline, cable television, natural gas, and telecommunications industries. Now, with the passage of new laws which have spurred the growth of independent power and opened up transmission access, the electric utility industry has become the laboratory for change. Here in the Northwest, dramatic changes in the electric industry mean that the Bonneville Power Administration (BPA) is facing real competition. Our customers have more choices than they had in the past. BPA`s draft Business Plan is a direct response to this changing environment. The plan presents how we propose to adapt to the new competitive marketplace. This is a summary of the plan and some of the important issues it raises for regional discussion. The draft plan contains much more detail on all the topics mentioned here. Business Plan is BPA`s first attempt to integrate the long-term strategic plans of the various parts of the agency with a strategic financial plan. Change is evident throughout the plan--change in our operating environment, in our strategic direction, in our customer and constituent relationships, and in BPA itself as an organization.

  8. Evaluation of source-term data for plutonium aerosolization

    SciTech Connect (OSTI)

    Haschke, J.M.

    1992-07-01

    Relevant data are reviewed and evaluated in an effort to define the time dependence and maximum value of the source term for plutonium aerosolization during a fuel fire. The rate of plutonium oxidation at high temperatures is a major determinant of the time dependence. Analysis of temperature-time data for oxidation of plutonium shows that the rate is constant (0.2 g PUO{sub 2}/cm{sup 2} of metal surface per min) and independent of temperature above 500{degrees}C. Total mass and particle distributions are derived for oxide products formed by reactions of plutonium metal and hydride. The mass distributions for products of all metal-gas reactions are remarkably similar with approximately 0.07 mass% of the oxide particles having geometric diameters {le} 10 {mu}m. In comparison, 25 mass% of the oxide formed by the PuH{sub 2}+O{sub 2} reaction is in this range. Experimental values of mass fractions released during oxidation are evaluated and factors that alter the release fraction are discussed.

  9. Plutonium Focus Area research and development plan. Revision 1

    SciTech Connect (OSTI)

    1996-11-01

    The Department of Energy (DOE) committed to a research and development program to support the technology needs for converting and stabilizing its nuclear materials for safe storage. The R and D Plan addresses five of the six material categories from the 94-1 Implementation Plan: plutonium (Pu) solutions, plutonium metals and oxides, plutonium residues, highly enriched uranium, and special isotopes. R and D efforts related to spent nuclear fuel (SNF) stabilization were specifically excluded from this plan. This updated plan has narrowed the focus to more effectively target specific problem areas by incorporating results form trade studies. Specifically, the trade studies involved salt; ash; sand, slag, and crucible (SS and C); combustibles; and scrub alloy. The plan anticipates possible disposition paths for nuclear materials and identifies resulting research requirements. These requirements may change as disposition paths become more certain. Thus, this plan represents a snapshot of the current progress and will continue to be updated on a regular basis. The paper discusses progress in safeguards and security, plutonium stabilization, special isotopes stabilization, highly-enriched uranium stabilization--MSRE remediation project, storage technologies, engineered systems, core technology, and proposed DOE/Russian technology exchange projects.

  10. Plutonium distribution: Summary of public and governmental support issues

    SciTech Connect (OSTI)

    Pasternak, A.

    1995-03-31

    Obtaining strong public and governmental support for the plutonium disposition program and for the projects comprising the selected disposition options will be essential to the success of the program in meeting non-proliferation goals established as national policy. This paper summarizes issues related to public and governmental support for plutonium disposition. Recommendations are offered which rest on two fundamental assumptions: (1) public and political support derive from public trust and confidence, and (2) despite widespread support for U.S. non-proliferation goals, establishing and operating facilities to carry out the program will entail controversy. Documentation for the Administration`s policy on non-proliferation as it relates to plutonium disposition is cited and summarized as background for ongoing planning efforts by the Department of Energy (DOE). Consensus is a reasonable goal for efforts to secure public and governmental support for the plutonium disposition program and its elements; unanimity is very unlikely. The program will be aided by the popular recognition of the importance of the nation`s non-proliferation goals, the potential for an energy dividend if an energy production option is selected ({open_quotes}Swords to Plowshares{close_quotes} metaphor), the possibility of influencing disposition decisions in other countries, and the clear need to do something with the excess material ({open_quotes}the no action alternative{close_quotes} will not suffice).

  11. Disposition of weapons-grade plutonium in Westinghouse reactors 

    E-Print Network [OSTI]

    Alsaed, Abdelhalim Ali

    1996-01-01

    We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four...

  12. Dissolution Behavior of Plutonium Containing Zirconia-Magnesia Ceramics

    SciTech Connect (OSTI)

    Kiel Holliday; Thomas Hartmann; Gary Cerefice; Ken Czerwinski

    2012-03-01

    This study explores the dissolution properties of zirconia-magnesia ceramics containing plutonium as the basis of an inert atrix nuclear fuel. The magnesium oxide phase remains pure MgO, while the zirconia incorporates a small amount of magnesium oxide along with all of the plutonium oxide and erbium oxide. The performance of the material under reactor and repository environments was examined. Reactor conditions are examined using a pressure vessel to expose the material to 300 degrees C water. To assess the performance of the material as a waste form it was submerged in 90 degrees C water for 1000 h. In both aqueous dissolution studies there was minimal release of less than 0.8 wt.% of plutonium from the material. To examine the potential for recycling, the dissolution behavior of the fuel matrix was examined in acidic solutions: pure nitric acid and a nitric acid-hydrofluoric acid-peroxide solution. Both acidic media exhibit potential for dissolving plutonium from the zirconia matrix. The experiments performed in this study are meant to lay a foundation for the chemical performance of zirconia-magnesia inert matrix fuel containing fissile material and burnable poison.

  13. Plutonium Consumption Program, CANDU Reactor Project final report

    SciTech Connect (OSTI)

    Not Available

    1994-07-31

    DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro`s Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel.

  14. SECRETARIAL REVIEW DRAFT REGULATORY IMPACT REVIEW /

    E-Print Network [OSTI]

    Draft ­ February 2014 ii Table of Contents Executive Summary....................................................................................16 2.6.3.3 Quota share price, ex-vessel value...................................................................................24 2.6.3.6 Transfer price caveats

  15. DRAFT FOR SECRETARIAL REVIEW ENVIRONMENTAL ASSESSMENT

    E-Print Network [OSTI]

    DRAFT FOR SECRETARIAL REVIEW ENVIRONMENTAL ASSESSMENT AND REGULATORY IMPACT REVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 NEPA REQUIREMENTS/ENVIRONMENTAL IMPACTS OF THE ALTERNATIVES . . . . . . . . 4 2.1 Environmental Impacts of the Alternatives

  16. DRAFT FOR SECRETARIAL REVIEW ENVIRONMENTAL ASSESSMENT

    E-Print Network [OSTI]

    DRAFT FOR SECRETARIAL REVIEW ENVIRONMENTAL ASSESSMENT and REGULATORY IMPACT REVIEW OF AMENDMENT 25.2 Alternatives . . . . . . . . . . . . . . . . . . . 9 2.0 NEPA REQUIREMENTS: ENVIRONMENTAL IMPACTS OF THE ALTERNATIVES . . . . . . . . . . . . . . . . . . . . . . 11 2.1 Environmental Impacts of the Alternatives

  17. DRAFT LM 2016–2025 Strategic Plan

    Office of Energy Efficiency and Renewable Energy (EERE)

    We invite you to review the draft LM 2016–2025 Strategic Plan which is now posted for public comment. We are updating the current Strategic Plan that covers the years 2011 through 2020. We...

  18. PalgravePrecautionary Draft -Comments Solicited

    E-Print Network [OSTI]

    Niebur, Ernst

    PalgravePrecautionary Draft - Comments Solicited Precautionary Saving and Precautionary Wealth This is an entry for The New Palgrave Dictionary of Economics, 2nd Ed. Keywords: Precautionary saving, prudence, consumption function, buffer stock saving Archive http

  19. Response to comments received from the State of Colorado and the public on the Environmental Assessment for resumption of thermal stabilization of plutonium oxide in Building 707

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    The Department of Energy (DOE) prepared this document to respond to comments from the State of Colorado and the public on the draft Environmental Assessment (EA) for the Resumption of Thermal Stabilization of Plutonium Oxide in Building 707 at the Rocky Flats Plant (RFP) in Golden, Colorado. The draft EA was provided to the State of Colorado and the public on September 8, 1993, for a comment period of 60 days. The Department`s National Environmental Policy Act (NEPA) Implementing Procedures (10 Code of Federal Regulations [CFR] 1021.301) requires that prior to approval of the EA, DOE is to allow the host State and Indian Tribe a period of from 14 to 30 days to review and comment on the EA. The Department established a comment period of 60 days for this EA in response to requests by the public during the first public meeting on July 7, 1993, before preparation of the EA. Other issues raised at the July 7 meeting included the range of alternatives to be considered, the time period for preparation of the EA, and the amount of material to be thermally stabilized. These and other comments made by the public at that meeting were carefully considered in preparation of the EA. In addition to providing the preapproval draft EA to the State of Colorado, DOE distributed the EA to all persons and groups on the RFP public information mailing list and placed the EA and reference documents in the DOE Public Reading Rooms in the RFP area. A public meeting was held on October 6, 1993, to hear public comments on the draft EA. All comments on the draft EA, those received both at the October 6 public meeting and through correspondence, have been reproduced in their entirety in this Response to Comments document. Responses to the commenters` questions and concerns are provided, and changes made to the body of the EA are indicated in the responses. All comments received have been considered in the revision of the EA.

  20. LITERATURE REVIEW FOR OXALATE OXIDATION PROCESSES AND PLUTONIUM OXALATE SOLUBILITY

    SciTech Connect (OSTI)

    Nash, C.

    2012-02-03

    A literature review of oxalate oxidation processes finds that manganese(II)-catalyzed nitric acid oxidation of oxalate in precipitate filtrate is a viable and well-documented process. The process has been operated on the large scale at Savannah River in the past, including oxidation of 20 tons of oxalic acid in F-Canyon. Research data under a variety of conditions show the process to be robust. This process is recommended for oxalate destruction in H-Canyon in the upcoming program to produce feed for the MOX facility. Prevention of plutonium oxalate precipitation in filtrate can be achieved by concentrated nitric acid/ferric nitrate sequestration of oxalate. Organic complexants do not appear practical to sequester plutonium. Testing is proposed to confirm the literature and calculation findings of this review at projected operating conditions for the upcoming campaign. H Canyon plans to commence conversion of plutonium metal to low-fired plutonium oxide in 2012 for eventual use in the Mixed Oxide Fuel (MOX) Facility. The flowsheet includes sequential operations of metal dissolution, ion exchange, elution, oxalate precipitation, filtration, and calcination. All processes beyond dissolution will occur in HB-Line. The filtration step produces an aqueous filtrate that may have as much as 4 M nitric acid and 0.15 M oxalate. The oxalate needs to be removed from the stream to prevent possible downstream precipitation of residual plutonium when the solution is processed in H Canyon. In addition, sending the oxalate to the waste tank farm is undesirable. This report addresses the processing options for destroying the oxalate in existing H Canyon equipment.

  1. Draft Environmental Assessment Sleeping Giant Hydropower Project

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8,Department of2 Federal Register /1 PiotrDraft3:Draft

  2. Draft ANU Library/Archives Volunteer Program Guidelines Page | 1 Draft Volunteer Program Guidelines: ANU

    E-Print Network [OSTI]

    into account the national standards for volunteering. It draws on the expertise of other library Draft ANU Library/Archives Volunteer Program Guidelines Page | 1 Draft Volunteer Program Guidelines: ANU Library/Archives Purpose To set out the guidelines for the Library/Archives Volunteer Program

  3. Development and Verification for the Control Method Using Surplus Pressure of Primary Pumps in Chiller Plant Systems for Air Conditioning which Adopts Primary/Secondary Piping Systems PPT 

    E-Print Network [OSTI]

    Matsushita, N.; Fujimura, M.; Sumiyoshi, D.; Akashi, Y.

    2012-01-01

    (chiller side) and secondary flow loop (load side). It is a huge energy loss, because the primary pumps use their head to lead much flow to the decoupler. Therefore, we have developed new control method using surplus pressure of the primary pump to reduce...

  4. The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition

    SciTech Connect (OSTI)

    Tulenko, J.S.; Wang, J.; Acosta, C.

    2004-10-06

    The University of Florida has underway an ongoing research program to validate the economic, operational and performance benefits of developing an inert matrix fuel (IMF) for the disposition of the U.S. weapons plutonium (Pu) and for the recycle of reprocessed Pu. The current fuel form of choice for Pu disposition for the Department of Energy is as a mixed oxide (MOX) (PuO2/UO2). We will show analyses that demonstrate that a Silicon Carbide (SiC) IMF offers improved performance capabilities as a fuel form for Pu recycle and disposition. The reason that UF is reviewing various materials to serve as an inert matrix fuel is that an IMF fuel form can offer greatly reduced Pu and transuranic isotope (TRU) production and also improved thermal performance characteristics. Our studies showed that the Pu content is reduced by an order of magnitude while centerline fuel temperatures are reduced approximately 380 degrees centigrade compared to MOX. These reduced temperatures result in reduced stored heat and thermal stresses in the pellet. The reduced stored heat reduces the consequences of the loss of coolant accident, while the reduced temperatures and thermal stresses yield greatly improved fuel performance. Silicon Carbide is not new to the nuclear industry, being a basic fuel material in gas cooled reactors.

  5. The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition

    SciTech Connect (OSTI)

    Tulenko, J.S.; Wang, J.; Acosta, C.

    2004-10-03

    The University of Florida has underway an ongoing research program to validate the economic, operational and performance benefits of developing an inert matrix fuel (IMF) for the disposition of the U.S. weapons plutonium (Pu) and for the recycle of reprocessed Pu. The current fuel form of choice for Pu disposition for the Department of Energy is as a mixed oxide (MOX) (PuO2/UO2). We will show analyses that demonstrate that a Silicon Carbide (SiC) IMF offers improved performance capabilities as a fuel form for Pu recycle and disposition. The reason that UF is reviewing various materials to serve as an inert matrix fuel is that an IMF fuel form can offer greatly reduced Pu and transuranic isotope (TRU) production and also improved thermal performance characteristics. Our studies showed that the Pu content is reduced by an order of magnitude while centerline fuel temperatures are reduced approximately 380 degrees centigrade compared to MOX. These reduced temperatures result in reduced stored heat and thermal stresses in the pellet. The reduced stored heat reduces the consequences of the loss of coolant accident, while the reduced temperatures and thermal stresses yield greatly improved fuel performance. Silicon Carbide is not new to the nuclear industry, being a basic fuel material in gas cooled reactors.

  6. RADIOLOGICAL CONTROLS FOR PLUTONIUM CONTAMINATED PROCESS EQUIPMENT REMOVAL FROM 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINSHING PLANT (PFP)

    SciTech Connect (OSTI)

    MINETTE, M.J.

    2007-05-30

    The 232-Z facility at Hanford's Plutonium Finishing Plant operated as a plutonium scrap incinerator for 11 years. Its mission was to recover residual plutonium through incinerating and/or leaching contaminated wastes and scrap material. Equipment failures, as well as spills, resulted in the release of radionuclides and other contamination to the building, along with small amounts to external soil. Based on the potential threat posed by the residual plutonium, the U.S. Department of Energy (DOE) issued an Action Memorandum to demolish Building 232-2, Comprehensive Environmental Response Compensation, and Liability Act (CERC1.A) Non-Time Critical Removal Action Memorandum for Removal of the 232-2 Waste Recovery Process Facility at the Plutonium Finishing Plant (04-AMCP-0486).

  7. PFPF canister counter for foreign plutonium (PCAS-3) hardware operations and procedures manual

    SciTech Connect (OSTI)

    Menlove, H.O.; Baca, J.; Kroncke, K.E.; Miller, M.C. ); Takahashi, S.; Seki, S.; Inose, S.; Yamamoto, T. )

    1993-01-01

    A neutron coincidence counter has been designed for the measurement of plutonium powder contained in tall storage canisters. The counter was designed for installation in the Plutonium Fuel Production Facility fabrication plant. Each canister contains from one to five cans of PuO[sub 2]. The neutron counter measures the spontaneous-fission rate from the plutonium and, when this is combined with the plutonium isotopic ratios, the plutonium mass is determined. The system can accommodate plutonium loadings up to 12 kg, with 10 kg being a typical loading. Software has been developed to permit the continuous operation of the system in an unattended mode. Authentication techniques have been developed for the system. This manual describes the system and its operation and gives performance and calibration parameters for typical applications.

  8. PFPF canister counter for foreign plutonium (PCAS-3) hardware operations and procedures manual

    SciTech Connect (OSTI)

    Menlove, H.O.; Baca, J.; Kroncke, K.E.; Miller, M.C.; Takahashi, S.; Seki, S.; Inose, S.; Yamamoto, T.

    1993-01-01

    A neutron coincidence counter has been designed for the measurement of plutonium powder contained in tall storage canisters. The counter was designed for installation in the Plutonium Fuel Production Facility fabrication plant. Each canister contains from one to five cans of PuO{sub 2}. The neutron counter measures the spontaneous-fission rate from the plutonium and, when this is combined with the plutonium isotopic ratios, the plutonium mass is determined. The system can accommodate plutonium loadings up to 12 kg, with 10 kg being a typical loading. Software has been developed to permit the continuous operation of the system in an unattended mode. Authentication techniques have been developed for the system. This manual describes the system and its operation and gives performance and calibration parameters for typical applications.

  9. Thermal and Physical Properties of Plutonium Dioxide Produced from the Oxidation of Metal: a Data Summary

    SciTech Connect (OSTI)

    Wayne, David M.

    2014-01-13

    The ARIES Program at the Los Alamos National Laboratory removes plutonium metal from decommissioned nuclear weapons, and converts it to plutonium dioxide in a specially-designed Direct Metal Oxidation furnace. The plutonium dioxide is analyzed for specific surface area, particle size distribution, and moisture content. The purpose of these analyses is to certify that the plutonium dioxide powder meets or exceeds the specifications of the end-user, and the specifications for the packaging and transport of nuclear materials. Analytical results from plutonium dioxide from ARIES development activities, from ARIES production activities, from muffle furnace oxidation of metal, and from metal that was oxidized over a lengthy time interval in air at room temperature, are presented. The processes studied produce plutonium dioxide powder with distinct differences in measured properties, indicating the significant influence of oxidation conditions on physical properties.

  10. Dry sample storage system for an analytical laboratory supporting plutonium processing

    SciTech Connect (OSTI)

    Treibs, H.A.; Hartenstein, S.D.; Griebenow, B.L.; Wade, M.A.

    1990-07-25

    The Special Isotope Separation (SIS) plant is designed to provide removal of undesirable isotopes in fuel grade plutonium by the atomic vapor laser isotope separation (AVLIS) process. The AVLIS process involves evaporation of plutonium metal, and passage of an intense beam of light from a laser through the plutonium vapor. The laser beam consists of several discrete wavelengths, tuned to the precise wavelength required to ionize the undesired isotopes. These ions are attracted to charged plates, leaving the bulk of the plutonium vapor enriched in the desired isotopes to be collected on a cold plate. Major portions of the process consist of pyrochemical processes, including direct reduction of the plutonium oxide feed material with calcium metal, and aqueous processes for purification of plutonium in residues. The analytical laboratory for the plant is called the Material and Process Control Laboratory (MPCL), and provides for the analysis of solid and liquid process samples.

  11. Delocalization and occupancy effects of 5f orbitals in plutonium intermetallics using L3-edge resonant X-ray emission spectroscopy

    E-Print Network [OSTI]

    Booth, C. H.

    2014-01-01

    5f orbitals in uranium and plutonium intermetallics, Proc.E. Colineau, G. H. Lander, Plutonium-based superconductivityproduced by self-damage in plutonium, Proc. Natl. Acad. Sci.

  12. Plutonium Finishing Plant (PFP) Final Safety Analysis Report (FSAR) [SEC 1 THRU 11

    SciTech Connect (OSTI)

    ULLAH, M K

    2001-02-26

    The Plutonium Finishing Plant (PFP) is located on the US Department of Energy (DOE) Hanford Site in south central Washington State. The DOE Richland Operations (DOE-RL) Project Hanford Management Contract (PHMC) is with Fluor Hanford Inc. (FH). Westinghouse Safety Management Systems (WSMS) provides management support to the PFP facility. Since 1991, the mission of the PFP has changed from plutonium material processing to preparation for decontamination and decommissioning (D and D). The PFP is in transition between its previous mission and the proposed D and D mission. The objective of the transition is to place the facility into a stable state for long-term storage of plutonium materials before final disposition of the facility. Accordingly, this update of the Final Safety Analysis Report (FSAR) reflects the current status of the buildings, equipment, and operations during this transition. The primary product of the PFP was plutonium metal in the form of 2.2-kg, cylindrical ingots called buttoms. Plutonium nitrate was one of several chemical compounds containing plutonium that were produced as an intermediate processing product. Plutonium recovery was performed at the Plutonium Reclamation Facility (PRF) and plutonium conversion (from a nitrate form to a metal form) was performed at the Remote Mechanical C (RMC) Line as the primary processes. Plutonium oxide was also produced at the Remote Mechanical A (RMA) Line. Plutonium processed at the PFP contained both weapons-grade and fuels-grade plutonium materials. The capability existed to process both weapons-grade and fuels-grade material through the PRF and only weapons-grade material through the RMC Line although fuels-grade material was processed through the line before 1984. Amounts of these materials exist in storage throughout the facility in various residual forms left from previous years of operations.

  13. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP Project W-460

    SciTech Connect (OSTI)

    WEISS, E.V.

    2000-03-06

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

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

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1995-08-08

    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.

  15. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalent Bonding Low-Cost2 DOE HQSiteo n n eDPF 2004 Morgan

  16. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalent Bonding Low-Cost2 DOE HQSiteo n n eDPF 2004 MorganSRS Will

  17. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalent Bonding Low-Cost2 DOE HQSiteo n n eDPF 2004 MorganSRS WillCareer

  18. DRAFT

    Office of Environmental Management (EM)

    Transportation External Coordination Working Group Meeting Albuquerque, New Mexico April 21-23, 2004 The U.S. Department of Energy (DOE), Transportation External Coordination...

  19. DRAFT

    Office of Environmental Management (EM)

    Approved 9-30-09 NORTHERN NEW MEXICO CITIZENS' ADVISORY BOARD (NNMCAB) Environmental Monitoring, Surveillance and Remediation Committee Recommendation to the Department of Energy...

  20. DRAFT

    Office of Environmental Management (EM)

    5 Approved May 14, 2009 1 2 3 4 5 6 7 8 9 10 NORTHERN NEW MEXICO CITIZENS' ADVISORY BOARD Recommendation to the Department of Energy 2009-05 Recommendation for 2011 Priorities for...

  1. DRAFT

    Office of Environmental Management (EM)

    4 Approved May 14, 2009 1 2 3 4 5 6 7 8 9 10 11 12 NORTHERN NEW MEXICO CITIZEN'S ADVISORY BOARD Recommendation to the Department of Energy No. 2009-04 Priorities for ARRA Stimulus...

  2. DRAFT

    Office of Environmental Management (EM)

    to the Department of Energy Los Alamos Site Office No. 2009-09 Northern New Mexico Citizens' Advisory Board Support for Community Outreach on Environmental Management...

  3. Draft

    Energy Savers [EERE]

    Restoration," DOE New, August 8, 1991. 290. EM Weekly, May 7, 1991, p. 3. 291. "Fresh Infusion of Cleanup Funds Cause.. Dufty to Recant Budget Gripe," Inside Energy (April 22,...

  4. DRAFT

    Office of Environmental Management (EM)

    Presentations Procurements Foreign Travel Tech Transfer (WFO, CRADA, NDA, Copyrights, Invention Disclosure DOE TECHNOLOGY TRANSFER SECURITY AREAS: Oversight and Review Obligations...

  5. DRAFT

    Office of Environmental Management (EM)

    of 1976 SHPO State Historic Preservation Office SWMU solid waste management unit U.S.C. United States Code UNDERSTANDING SCIENTIFIC NOTATION NNSA has used scientific notation in...

  6. DRAFT

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

    in energy demand for groundwater pumping 3. Water-energy planning at the State level a. California Water Plan Update i. Energy implications of resource management strategies ii....

  7. DRAFT

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

    the nuclear field should be made aware of the requirements associated with "Fitness for Duty" * A strategy to get more students interested in all of the above areas should be...

  8. DRAFT

    National Nuclear Security Administration (NNSA)

    restriction, or job transfer dB decibel dBA decibel A-weighted DOE U.S. Department of Energy EA environmental assessment EPA U.S. Environmental Protection Agency ESA Endangered...

  9. DRAFT

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

    Nuclear Workforce Initiative: Filling A Local Critical Career Need November 2009 Executive Summary In the brief span of one year, the Savannah River Site Community Reuse...

  10. DRAFT

    Energy Savers [EERE]

    HRPP includes: (1) Property especially designed or prepared (EDP) for use in the nuclear fuel cycle illustrative list in 10 CFR 110 (Reference l), including items listed in the...

  11. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electricLaboratory | version of the1996of EnergyIdahoS . D E P A R T4,3

  12. Draft

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-in electricLaboratoryofNotices | Department ofOfficial,Dr.Closing the Circle:

  13. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HAB Packet HanfordDOE ProjectREMOTE-HANDLED TRU76411-2225E M007 i

  14. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HAB Packet HanfordDOE ProjectREMOTE-HANDLED TRU76411-2225E M007

  15. DRAFT

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1 OF2Guidance toTons (short) Acres

  16. DRAFT

    National Nuclear Security Administration (NNSA)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal01 Sandia National 1 PAGE 1 OF2Guidance toTons (short)

  17. DRAFT

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i pStateDOEAnalysis,Department of U.S. DEPARTMENT ScottConservationOutline

  18. DRAFT

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 20153 METHODSDOE/LaborSeptember 6,531970, 2012 Roland

  19. draft

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About1996HowFOAShowingFuelWeatherize »EvePlantEnergyinspectionDEPARTMENT3

  20. Draft

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit theCovalentLaboratory |Sector FullDOEUrsula GoodenoughRecentDOE/EA-1412

  1. Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

    SciTech Connect (OSTI)

    Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Jones, Susan A.; Rapko, Brian M.

    2014-08-05

    This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.

  2. Weapons and commercial plutonium ultimate disposition choices: Destroy ``completely`` or store forever

    SciTech Connect (OSTI)

    Bowman, C.D.

    1994-07-01

    All of the options under consideration for weapons and commercial plutonium disposition ultimately boil down to the choices of either ``complete`` destruction or storage ``forever.`` None of the reactor-based plutonium burning systems demonstrated over the past 50 years of reactor development consume this material completely. Ultimately considerable unburned plutonium must be stored ``forever`` from those systems. Plutonium is considered to be dangerous both as a weapons material and as a health hazard. While properly stored plutonium might never make its way back by natural phenomena into the environment as a health hazard, stored plutonium is always accessible to recovery for malevolent purposes. It must be guarded wherever in the world it is stored for as long as it continues to exist. Complete destruction of the plutonium eliminates this material as a concern of future generations. Los Alamos National Laboratory accelerator-driven technology promises to allow safe and complete destruction of this material. Furthermore it appears that in the process of destruction the neutron rich features of the weapons plutonium provides benefits to society that place a value on weapons plutonium exceeding that of highly enriched uranium. A realistic time scale for development and deployment of burial technology either with or without partial burning in reactors is expected to be comparable with or to exceed the time for development and deployment of the accelerator-driven destruction method under study at Los Alamos.

  3. Voluntary Protection Program Onsite Review, Plutonium Finishing Plant Closure Project- May 2007

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Plutonium Finishing Plant Closure Project is continuing to perform at a level deserving DOE-VPP Star recognition.

  4. Use of Gadolinium as a Primary Criticality Control in Disposing Waste Containing Plutonium at SRS

    SciTech Connect (OSTI)

    Andrew, Vincent

    2005-01-04

    Use of gadolinium as a neutron poison has been proposed for disposing of several metric tons of excess plutonium at the Savannah River Site (SRS). The plutonium will first be dissolved in nitric acid in small batches. Gadolinium nitrate will then be added to the plutonium nitrate solution. The Gd-poisoned plutonium solution will be neutralized and transferred to large under-ground tanks. The pH of small batches of neutralized plutonium solution will be adjusted prior to addition of the glass frit for eventual production as glass logs. The use of gadolinium as the neutron poison would minimize the number of glass logs generated from this disposition. The primary criticality safety concerns regarding the disposal process are: (1) maintaining neutron moderation under all processing conditions since gadolinium has a very large absorption cross section for thermal neutrons, (2) characteristics of plutonium and gadolinium precipitation during the neutralization process, (3) mixing characteristics of the precipitate to ensure that plutonium would remain homogeneously mixed with gadolinium, and (4) potential separation of plutonium and gadolinium during nitric and formic acids addition. A number of experiments were conducted at the Savannah River National Laboratory to study the behavior of plutonium and gadolinium at various stages of the disposition process.

  5. Structural Characterization of and Plutonium Sorption on Mesoporous and Nanoparticulate Ferrihydrite

    E-Print Network [OSTI]

    Brogan, Luna Kestrel Schwaiger

    2012-01-01

    cation. . . . . . . . . . . . . . . . . Pourbaix diagram forPourbaix diagram for plutonium in an aqueous solutionoxidation state distribution. A Pourbaix diagram can also be

  6. DOE Will Dispose of 34 Metric Tons of Plutonium by Turning it...

    National Nuclear Security Administration (NNSA)

    Will Dispose of 34 Metric Tons of Plutonium by Turning it into Fuel for Civilian Reactors | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People...

  7. DOE to Prepare a Supplemental Environmental Impact Statement...

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

    Environmental Impact Statement (EIS) that identifies a plutonium vitrification facility and use of H-Canyon as the preferred alternatives for surplus plutonium not planned...

  8. Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

  9. Standard test method for nondestructive assay of plutonium in scrap and waste by passive neutron coincidence counting

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    Standard test method for nondestructive assay of plutonium in scrap and waste by passive neutron coincidence counting

  10. Sept 2001 Rough Draft OFFM Policy Letter 02-1.doc | Department...

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

    Sept 2001 Rough Draft OFFM Policy Letter 02-1.doc Sept 2001 Rough Draft OFFM Policy Letter 02-1.doc Sept 2001 Rough Draft OFFM Policy Letter 02-1.doc More Documents & Publications...

  11. EIS-0283-S2: EPA Notice of Availability of the Final Supplemental...

    Energy Savers [EERE]

    Notice of Availability of the Final Supplemental Environmental Impact Statement Surplus Plutonium Disposition Supplemental Environmental Impact Statement EPA announced the...

  12. Measurement of plutonium in spent nuclear fuel by self-induced x-ray fluorescence

    SciTech Connect (OSTI)

    Hoover, Andrew S; Rudy, Cliff R; Tobin, Steve J; Charlton, William S; Stafford, A; Strohmeyer, D; Saavadra, S

    2009-01-01

    Direct measurement of the plutonium content in spent nuclear fuel is a challenging problem in non-destructive assay. The very high gamma-ray flux from fission product isotopes overwhelms the weaker gamma-ray emissions from plutonium and uranium, making passive gamma-ray measurements impossible. However, the intense fission product radiation is effective at exciting plutonium and uranium atoms, resulting in subsequent fluorescence X-ray emission. K-shell X-rays in the 100 keV energy range can escape the fuel and cladding, providing a direct signal from uranium and plutonium that can be measured with a standard germanium detector. The measured plutonium to uranium elemental ratio can be used to compute the plutonium content of the fuel. The technique can potentially provide a passive, non-destructive assay tool for determining plutonium content in spent fuel. In this paper, we discuss recent non-destructive measurements of plutonium X-ray fluorescence (XRF) signatures from pressurized water reactor spent fuel rods. We also discuss how emerging new technologies, like very high energy resolution microcalorimeter detectors, might be applied to XRF measurements.

  13. Ris-R-1321(EN) On Weapons Plutonium in the Arctic

    E-Print Network [OSTI]

    and transfer of plutonium to benthic biota is low. Paper II, concludes that the resuspension of accident debris the catchment area to lakes than plutonium and radio lead. Paper III, is a method description of inventory.4 Resuspension on land 33 3.5 Biota 34 4 Concluding Remarks and Future Research 34 Paper I 43 Paper II 63 Paper

  14. Functional Design Criteria plutonium stabilization and handling (PUSH) project W-460

    SciTech Connect (OSTI)

    NELSON, D.W.

    1999-09-02

    This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

  15. Implications of Plutonium isotopic separation on closed fuel cycles and repository design

    SciTech Connect (OSTI)

    Forsberg, C.

    2013-07-01

    Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

  16. History and stabilization of the Plutonium Finishing Plant (PFP) complex, Hanford Site

    SciTech Connect (OSTI)

    Gerber, M.S., Fluor Daniel Hanford

    1997-02-18

    The 231-Z Isolation Building or Plutonium Metallurgy Building is located in the Hanford Site`s 200 West Area, approximately 300 yards north of the Plutonium Finishing Plant (PFP) (234-5 Building). When the Hanford Engineer Works (HEW) built it in 1944 to contain the final step for processing plutonium, it was called the Isolation Building. At that time, HEW used a bismuth phosphate radiochemical separations process to make `AT solution,` which was then dried and shipped to Los Alamos, New Mexico. (AT solution is a code name used during World War II for the final HEW product.) The process was carried out first in T Plant and the 224-T Bulk Reduction Building and B Plant and the 224-B Bulk Reduction Building. The 224-T and -B processes produced a concentrated plutonium nitrate stream, which then was sent in 8-gallon batches to the 231-Z Building for final purification. In the 231-Z Building, the plutonium nitrate solution underwent peroxide `strikes` (additions of hydrogen peroxide to further separate the plutonium from its carrier solutions), to form the AT solution. The AT solution was dried and shipped to the Los Alamos Site, where it was made into metallic plutonium and then into weapons hemispheres.` The 231-Z Building began `hot` operations (operations using radioactive materials) with regular runs of plutonium nitrate on January 16, 1945.

  17. Symmetry and Stability of Plutonium: The Influence of Electronic Structure K. T. Moore,1,* P. Soderlind,1

    E-Print Network [OSTI]

    Laughlin, David E.

    Symmetry and Stability of Plutonium: The Influence of Electronic Structure K. T. Moore,1,* P. So-functional theory, we calculate the bond strengths between the 12 nearest neighbors in plutonium for both pure Pu rather than face-centered cubic Fm3m, showing that the anomalously large anisotropy of plutonium

  18. Annealing of Aged Plutonium Jeremy N. Mitchell, Adam M. Farrow, Franz J. Freibert, and Daniel S. Schwartz

    E-Print Network [OSTI]

    Annealing of Aged Plutonium Jeremy N. Mitchell, Adam M. Farrow, Franz J. Freibert, and Daniel S Alamos, NM 87545 jeremy@lanl.gov INTRODUCTION Face-centered cubic -phase is stable in pure plutonium properties of plutonium, including solute content, thermal history, and processing history. The radioactive

  19. Plutonium in groundwater at the 100K-Area of the U.S. DOE Hanford Site

    E-Print Network [OSTI]

    Buesseler, Ken

    Plutonium in groundwater at the 100K-Area of the U.S. DOE Hanford Site Minhan Daia,b , Ken O distribution, redox state and isotopic composition of plutonium (Pu) in groundwater at the 100K-Area at the U distribution. D 2004 Elsevier B.V. All rights reserved. Keywords: Plutonium; Isotopic composition; Size

  20. Recovery of Plutonium from Refractory Residues Using a Sodium Peroxide Pretreatment Process

    SciTech Connect (OSTI)

    Rudisill, T.S.

    2003-10-23

    The recycle of plutonium from refractory residues is a necessary activity for the nuclear weapon production complex. Traditionally, high-fired plutonium oxide (PuO2) was leached from the residue matrix using a nitric acid/fluoride dissolving flowsheet. The recovery operations were time consuming and often required multiple contacts with fresh dissolving solution to reduce the plutonium concentration to levels where residual solids could be discarded. Due to these drawbacks, the development of an efficient process for the recovery of plutonium from refractory materials is desirable. To address this need, a pretreatment process was developed. The development program utilized a series of small-scale experiments to optimize processing conditions for the fusion process and demonstrate the plutonium recovery efficiency using ceramic materials developed as potential long-term storage forms for PuO2 and an incinerator ash from the Rocky Flats Environmental Technology Site (Rocky Flats) as te st materials.

  1. Reaction kinetics relevant to the recycle hydride-dehydride process for plutonium recovery

    SciTech Connect (OSTI)

    Haschke, J.M.; Allen, T.H.

    1997-10-01

    Objectives of this one-year, Laboratory Directed Research and Development (LDRD) project were the expansion of fundamental knowledge of plutonium chemistry and the development of information for enhancing plutonium recovery methods and weapons safety. Results of kinetic studies demonstrate that the monoxide monohydride, PuO(H), formed during corrosion of plutonium by water in pyrophoric when dry and acts as an initiator for hydride-catalyzed reaction of the metal with air. The catalyzed corrosion rate of Pu is 10{sup 8} times faster than that in dry air and transforms plutonium into a readily aerosolized material. A potential application for the catalytic reaction is in the direct recovery of plutonium as oxide. Wet PuO(H) is non-pyrophoric and the safety hazard posed by its formation is reduced if the material is not allowed to dry.

  2. Investigation into the feasibility of alternative plutonium shipping forms

    SciTech Connect (OSTI)

    Mishima, J.; Lindsey, C.G.

    1983-06-01

    Pacific Northwest Laboratory (PNL), operated for the Department of Energy by the Battelle Memorial Institute, is conducting a study for the Nuclear Regulatory Commission on the feasibility of altering current plutonium shipping forms to reduce or eliminate the airborne dispersibility of PuO/sub 2/ which might occur during a shipping accident. Plutonium used for fuel fabrication is currently shipped as a PuO/sub 2/ powder with a significant fraction in the respirable size range. If the high-strength container is breached due to stresses imposed during a transportation accident, the PuO/sub 2/ powder could be subject to airborne dispersion. The available information indicated that a potential accident involving fire accompanied by crush/impact forces would lead to failure of current surface shipping containers (no assumptions were made on the possibility of such a severe accident). Criteria were defined for an alternate shipping form to mitigate the effects of such an accident. Candidate techniques and materials were evaluated as alternate shipping forms by a task team consisting of personnel from PNL and Rockwell Hanford Operations (RHO). At this time, the most promising candidate for an alternate plutonium shipping form appears to be pressing PuO/sub 2/ into unsintered (green) pellets. These green pellets satisfy the criteria for a less dispersible form without requiring significant process changes. Discussions of all candidates considered are contained in a series of appendices. Recommendations for further investigations of the applicability of green pellets as an alternate shipping form are given, including the need for a cost-benefit study.

  3. Testing Juntas (draft) Carnegie Mellon University

    E-Print Network [OSTI]

    Goldreich, Oded

    a 1-junta tester: simply run the dictator test on f and ¯f, and also test if f is constant; acceptTesting Juntas (draft) Eric Blais Carnegie Mellon University eblais@cs.cmu.edu February 3, 2010. The problem of testing whether a function is a k-junta or is "far" from being a k-junta is a central problem

  4. Boston Harbor -Deep Draft Navigation Improvement Massachusetts

    E-Print Network [OSTI]

    US Army Corps of Engineers

    of Massachusetts Bay and is the New England region's largest port. The main deep water harbor is comprised for the Chelsea River which has an authorized depth of 38 feet MLLW. Deep water access to the harbor is providedBoston Harbor - Deep Draft Navigation Improvement Massachusetts 21 August 2008 and 18 September

  5. DRAFT LASER SAFETY COMMITTEE CHARTER March, 2014

    E-Print Network [OSTI]

    Knowles, David William

    DRAFT LASER SAFETY COMMITTEE CHARTER March, 2014 Function The Laser Safety Committee (LSC and advice to the LBNL Laser Safety Officer (LSO) on policies and practices regarding the safe conduct and regulatory compliance of laser-related work at LBNL. The goal of the Committee is to assure effective

  6. Draft NISTIR 80061 NIST Cloud Computing2

    E-Print Network [OSTI]

    Draft NISTIR 80061 NIST Cloud Computing2 Forensic Science Challenges NIST Cloud Computing Forensic Computing11 Forensic Science Challenges 12 NIST Cloud Computing Forensic Science Working Group13 Information challenges77 faced by experts when responding to incidents that have occurred in a cloud-computing ecosystem

  7. NEW SOLAR HOMES PARTNERSHIP DRAFT GUIDEBOOK

    E-Print Network [OSTI]

    NEW SOLAR HOMES PARTNERSHIP DRAFT GUIDEBOOK Fourth Edition JANUARY 2012 CEC3002011006CMD2 The New Solar Homes Partnership (NSHP) Program is part of a statewide solar program known as the California Solar Initiative (CSI). The NSHP provides financial incentives for installing solar energy

  8. DRAFT Supplement to the Environmental Assessment For

    E-Print Network [OSTI]

    DRAFT Supplement to the Environmental Assessment For Restructuring the Program for Observer supplements the 2011 Environmental Assessment for Restructuring the Program for Observer Procurement and Deployment in the North Pacific. NMFS prepared this supplement in response to a Court Order to consider

  9. Draft Charter (May 3, 2013) Bill Bradbury

    E-Print Network [OSTI]

    and estuary are integral components of the Columbia River ecosystem and the lifecycle of Columbia River salmon of ocean conditions on anadromous fish survival and use this information to evaluate and adjust inland by completing the following tasks: #12;Draft Charter (May 3, 2013) 2 (A)Identify key information needs

  10. California Energy Commission DRAFT STAFF REPORT

    E-Print Network [OSTI]

    . Steven Mac and Irene Salazar provided the historic consumption data. Mark Ciminelli provided a newCalifornia Energy Commission DRAFT STAFF REPORT UPDATED CALIFORNIA ENERGY DEMAND FORECAST 20112022 MAY 2011 CEC2002011006SD #12;CALIFORNIA ENERGY COMMISSION Chris Kavalec Principal Author Chris

  11. ENGINEERING EDUCATION IN INDIA Draft Final report

    E-Print Network [OSTI]

    Banerjee, Rangan

    ENGINEERING EDUCATION IN INDIA Draft Final report Rangan Banerjee Vinayak P. Muley Sponsored by Observer Research Foundation Energy Systems Engineering, IIT Bombay Powai, Mumbai ­ 400076 September 14, 2007 #12;i Preface In India engineering is one of the preferred choices for good students at the 10

  12. Radiochemistry of uranium, neptunium and plutonium: an updating

    SciTech Connect (OSTI)

    Roberts, R.A.; Choppin, G.R.; Wild, J.F.

    1986-02-01

    This report presents some procedures used in the radiochemical isolation, purification and/or analysis of uranium, neptunium, and plutonium. In this update of the procedures, we have not attempted to discuss the developments in the chemistry of U, Np, and Pu but have restricted the report to the newer procedures, most of which have resulted from the increased emphasis in environmental concern which requires analysis of extremely small amounts of the actinide element in quite complex matrices. The final section of this report describes several schemes for isolation of actinides by oxidation state.

  13. Post-accident inhalation exposure and experience with plutonium

    SciTech Connect (OSTI)

    Shinn, J

    1998-06-01

    This paper addresses the issue of inhalation exposure immediately afterward and for a long time following a nuclear accident. For the cases where either a nuclear weapon burns or explodes prior to nuclear fission, or at locations close to a nuclear reactor accident containing fission products, a major concern is the inhalation of aerosolized plutonium (Pu) particles producing alpha-radiation. We have conducted field studies of Pu- contaminated real and simulated accident sites at Bikini, Johnston Atoll, Tonopah (Nevada), Palomares (Spain), Chernobyl, and Maralinga (Australia).

  14. EIS-0350-S1: EPA Notice of Availability of the Draft Supplemental...

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

    Draft Supplemental Environmental Impact Statement EIS-0350-S1: EPA Notice of Availability of the Draft Supplemental Environmental Impact Statement Nuclear Facility Portion of the...

  15. EIS-0515: BOR and FWS Notice of Availability of Draft Environmental...

    Energy Savers [EERE]

    5: BOR and FWS Notice of Availability of Draft Environmental Impact Statement EIS-0515: BOR and FWS Notice of Availability of Draft Environmental Impact Statement BOR and FWS...

  16. Microsoft Word - Draft EA Press Release 02-12-13 (2)

    National Nuclear Security Administration (NNSA)

    DRAFT NEWS RELEASE News Media Contacts Gayle Fisher, NNSA, 816-997-5476 February 12, 2013 NNSA solicits public comment regarding its Draft Environmental Assessment For transfer of...

  17. Microsoft Word - Draft EBT Analysis_Alcoa -10.10.12 _REDLINE...

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

    12 1 ADMINISTRATOR'S DRAFT EQUIVALENT BENEFITS ANALYSIS DETERMINATION FOR CONTRACT OFFER TO ALCOA INC. October 9, 2012 I. INTRODUCTION This draft Equivalent Benefits analysis...

  18. EIS-0423-S1: DOE Notice of Availability of a Draft Supplemental...

    Office of Environmental Management (EM)

    -S1: DOE Notice of Availability of a Draft Supplemental Environmental Impact Statement EIS-0423-S1: DOE Notice of Availability of a Draft Supplemental Environmental Impact...

  19. EIS-0433-S1: EPA Notice of Availability of a Draft Supplemental...

    Energy Savers [EERE]

    33-S1: EPA Notice of Availability of a Draft Supplemental Environmental Impact Statement EIS-0433-S1: EPA Notice of Availability of a Draft Supplemental Environmental Impact...

  20. EIS-0433-S1: EPA Notice of Availability of a Draft Supplemental...

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

    EPA Notice of Availability of a Draft Supplemental Environmental Impact Statement Keystone XL Project EPA announces the availability fo the Keystone XL Project Draft...

  1. Plutonium contamination in soils in open space and residential areas near Rocky Flats, Colorado

    SciTech Connect (OSTI)

    Litaor, M.I.

    1999-02-01

    Spatial analysis of the {sup 240}Pu:{sup 239}Pu isotopic ratio of 42 soil samples collected around Rocky Flats Plant near Golden, Colorado, was conducted to assess the effect of Rocky Flats Plant activity on the soil environment. Two probability maps that quantified the uncertainty of the spatial distribution of plutonium isotopic ratios were constructed using the sequential Gaussian simulation technique (sGs). Assuming a plutonium isotopic ratio range of 0.152 {+-} 0.003 to 0.169 {+-} 0.009 is characteristic to global fallout in Colorado, and a mean value of 0.155 is representative for the Rocky Flats Plant area, the main findings of the current work were (1) the areas northwest and southwest of Rocky Flats Plant exhibited a plutonium ratio {ge}0.155, this were minimally impacted by the plant activity; (2) he study area east of Rocky Flats Plant exhibited a plutonium isotopic ratio {le}0.155, which is a definitive indicator of Rocky Flats Plant-derived plutonium; and (3) inventory calculations across the study area exhibited large standard error of estimates. These errors were originated from the high variability in plutonium activity over a small sampling scale and the uncertainty in the global fallout isotopic ratio. Using the mean simulated estimates of plutonium isotopic ratio, coupled with plutonium activity measured at 11 soil pits and additional plutonium information published elsewhere, the plutonium loading on the open space and residential areas amounted to 111.2 GBq, with a standard error of estimate of 50.8 GBq.

  2. THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE

    SciTech Connect (OSTI)

    CHARBONEAU, S.L.

    2006-02-01

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent-order milestones, milestones completed to date, and the vision of bringing PFP to slab-on-grade. Innovative approaches in planning and regulatory strategies, as well new technologies from within the United States and from other countries and field decontamination techniques developed by workforce personnel, such as the ''turkey roaster'' and the ''lazy Susan'' are covered in detail in the paper. Critical information on issues and opportunities during the performance of the work such as concerns regarding the handling and storage of special nuclear material, concerns regarding criticality safety and the impact of SNM de-inventory at PFP are also provided. The continued success of the PFP D&D effort is due to the detailed, yet flexible, approach to planning that applied innovative techniques and tools, involved a team of experienced independent reviewers, and incorporated previous lessons learned at the Hanford site, Rocky Flats, and commercial nuclear D&D projects. Multi-disciplined worker involvement in the planning and the execution of the work has produced a committed workforce that has developed innovative techniques, resulting in safer and more efficient work evolutions.

  3. New Gas Gun Helping Scientists Better Understand Plutonium Behavior

    SciTech Connect (OSTI)

    Hazi, A

    2005-09-20

    One of the most daunting scientific and engineering challenges today is ensuring the safety and reliability of the nation's nuclear arsenal. To effectively meet that challenge, scientists need better data showing how plutonium, a key component of nuclear warheads, behaves under extreme pressures and temperatures. On July 8, 2003, Lawrence Livermore researchers performed the inaugural experiment of a 30-meter-long, two-stage gas gun designed to obtain those data. The results from a continuing stream of successful experiments on the gas gun are strengthening scientists' ability to ensure that the nation's nuclear stockpile is safe and reliable. The JASPER (Joint Actinide Shock Physics Experimental Research) Facility at the Department of Energy's (DOE's) Nevada Test Site (NTS) is home to the two-stage gas gun. In the gun's first test, an unqualified success, Livermore scientists fired a projectile weighing 28.6 grams and traveling about 5.21 kilometers per second when it impacted an extremely small (about 30-gram) plutonium target. This experiment marked the culmination of years of effort in facility construction, gun installation, system integration, design reviews, and federal authorizations required to bring the experimental facility online. Ongoing experiments have drawn enthusiastic praise from throughout DOE, the National Nuclear Security Administration (NNSA), and the scientific community. NNSA Administrator Linton Brooks said, ''Our national laboratories now have at their disposal a valuable asset that enhances our due diligence to certify the nuclear weapons stockpile in the absence of underground nuclear weapons testing.''

  4. Benchmark Evaluation of Plutonium Hemispheres Reflected by Steel and Oil

    SciTech Connect (OSTI)

    John Darrell Bess

    2008-06-01

    During the period from June 1967 through September 1969 a series of critical experiments was performed at the Rocky Flats Critical Mass Laboratory with spherical and hemispherical plutonium assemblies as nested hemishells as part of a Nuclear Safety Facility Experimental Program to evaluate operational safety margins for the Rocky Flats Plant. These assemblies were both bare and fully or partially oil-reflected. Many of these experiments were subcritical with an extrapolation to critical configurations or critical at a particular oil height. Existing records reveal that 167 experiments were performed over the course of 28 months. Unfortunately, much of the data was not recorded. A reevaluation of the experiments had been summarized in a report for future experimental and computational analyses. This report examines only fifteen partially oil-reflected hemispherical assemblies. Fourteen of these assemblies also had close-fitting stainless-steel hemishell reflectors, used to determine the effective critical reflector height of oil with varying steel-reflector thickness. The experiments and their uncertainty in keff values were evaluated to determine their potential as valid criticality benchmark experiments of plutonium.

  5. Plutonium metal exchange program : current status and statistical analysis

    SciTech Connect (OSTI)

    Tandon, L.; Eglin, J. L.; Michalak, S. E.; Picard, R. R.; Temer, D. J.

    2004-01-01

    The Rocky Flats Plutonium (Pu) Metal Sample Exchange program was conducted to insure the quality and intercomparability of measurements such as Pu assay, Pu isotopics, and impurity analyses. The Rocky Flats program was discontinued in 1989 after more than 30 years. In 2001, Los Alamos National Laboratory (LANL) reestablished the Pu Metal Exchange program. In addition to the Atomic Weapons Establishment (AWE) at Aldermaston, six Department of Energy (DOE) facilities Argonne East, Argonne West, Livermore, Los Alamos, New Brunswick Laboratory, and Savannah River are currently participating in the program. Plutonium metal samples are prepared and distributed to the sites for destructive measurements to determine elemental concentration, isotopic abundance, and both metallic and nonmetallic impurity levels. The program provides independent verification of analytical measurement capabilies for each participating facility and allows problems in analytical methods to be identified. The current status of the program will be discussed with emphasis on the unique statistical analysis and modeling of the data developed for the program. The discussion includes the definition of the consensus values for each analyte (in the presence and absence of anomalous values and/or censored values), and interesting features of the data and the results.

  6. Experimental critical parameters of plutonium metal cylinders flooded with water

    SciTech Connect (OSTI)

    NONE

    1996-07-01

    Forty-nine critical configurations are reported for experiments involving arrays of 3 kg plutonium metal cylinders moderated and reflected by water. Thirty-four of these describe systems assembled in the laboratory, while 15 others are derived critical parameters inferred from 46 subcritical cases. The arrays included 2x2xN, N = 2, 3, 4, and 5, in one program and 3x3x3 configurations in a later study. All were three-dimensional, nearly square arrays with equal horizontal lattice spacings but a different vertical lattice spacing. Horizontal spacings ranged from units in contact to 180 mm center-to-center; and vertical spacings ranged from about 80 mm to almost 400 mm center-to-center. Several nearly-equilateral 3x3x3 arrays exhibit an extremely sensitive dependence upon horizontal separation for identical vertical spacings. A line array of unreflected and essentially unmoderated canned plutonium metal units appeared to be well subcritical based on measurements made to assure safety during the manual assembly operations. All experiments were performed at two widely separated times in the mid-1970s and early 1980s under two programs at the Rocky Flats Plant`s Critical Mass Laboratory.

  7. Treatment of plutonium process residues by molten salt oxidation

    SciTech Connect (OSTI)

    Stimmel, J.; Wishau, R.; Ramsey, K.B.; Montoya, A.; Brock, J.; Heslop, M.; Wernly, K.

    1999-04-01

    Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic matrix from combustible {sup 238}Pu material. Plutonium processing residues are injected into a molten salt bed with an excess of air. The salt (sodium carbonate) functions as a catalyst for the conversion of the organic material to carbon dioxide and water. Reactive species such as fluorine, chlorine, bromine, iodine, sulfur, phosphorous and arsenic in the organic waste react with the molten salt to form the corresponding neutralized salts, NaF, NaCl, NaBr, NaI, Na{sub 2}SO{sub 4}, Na{sub 3}PO{sub 4} and NaAsO{sub 2} or Na{sub 3}AsO4. Plutonium and other metals react with the molten salt and air to form metal salts or oxides. Saturated salt will be recycled and aqueous chemical separation will be used to recover the {sup 238}Pu. The Los Alamos National Laboratory system, which is currently in the conceptual design stage, will be scaled down from current systems for use inside a glovebox.

  8. Research To Underpin The UK Plutonium Disposition Strategy

    SciTech Connect (OSTI)

    Hanson, B.C.; Scales, C.R.; Worrall, A.; Thomas, M. [Nexia Solutions, Risley, Warrington, Cheshire, WA3 6AS (United Kingdom); Davies, P.; Gilchrist, P. [Nuclear Decommissioning Authority, Pelham House, Calderbridge, Cumbria, CA20 1DB (United Kingdom)

    2006-07-01

    In April 2005, the UK Nuclear Decommissioning Authority (NDA) took ownership of most of the civil nuclear liabilities and assets in the UK. These include separated civil plutonium stocks, which are expected to rise to over 100 tonnes. Future UK national policy for disposition remains to be finalised. The feasibility of management options needs to be determined in order to allow the NDA to advise government on the ultimate disposition of this material. Nexia Solutions has a contract with NDA to develop and carry out a research project which will result in a recommendation on the technical feasibility of a number of disposition options, focussing on re-use and immobilisation of plutonium as a waste for disposal. Initial work is already underway evaluating re-use with MOX and IMF fuels and immobilisation using ceramics, glasses and MOX for disposal. The programme is expected to result, circa 2010, in a recommendation of a preferred route for immobilisation and a preferred route for re-use for the UK's civil Pu stocks. (authors)

  9. Comparative behavior of plutonium and americium in the equatorial Pacific

    SciTech Connect (OSTI)

    Noshkin, V.E.; Wong, K.M.; Jokela, T.A.; Brunk, J.L.; Eagle, R.J.

    1983-01-01

    Inventories of /sup 239 +240/Pu and /sup 241/Am greatly in excess of global fallout levels persist in the benthic environments of Bikini and Enewetak Atolls. The amount of /sup 239 +240/Pu mobilized to solution at the atolls can be predicted from a distribution coefficient K/sub d/ of 2.3 x 10/sup 5/ and the mean sediment concentrations. The mobilized /sup 239 +240/Pu has solute-like characteristics and different valence states coexist in solution - the largest fraction of the soluble plutonium is in an oxidized form (+V,VI). The adsorption of plutonium to sediments is not completely reversible because of changes that occur in the relative amounts of the mixed oxidation states in solution with time. Characteristics of /sup 239 +240/Pu described at one location may not necessarily describe its behavior elsewhere. The relative amounts of /sup 241/Am to /sup 239 +240/Pu may be altered in future years because of mobilization and radiological decay.

  10. Plutonium and americium behavior in coral atoll environments

    SciTech Connect (OSTI)

    Noshkin, V.E.; Wong, K.M.; Jokela, T.A.; Brunk, J.L.; Eagle, R.J.

    1984-02-01

    Inventories of /sup 239 +240/Pu and /sup 241/Am greatly in excess of global fallout levels persist in the benthic environments of Bikini and Enewetak Atolls. Quantities of /sup 239 +240/Pu and lesser amounts of /sup 241/Am are continuously mobilizing from these sedimentary reservoirs. The amount of /sup 239 +240/Pu mobilized to solution at any time represents 0.08 to 0.09% of the sediment inventories to a depth of 16 cm. The mobilized /sup 239 +240/Pu has solute-like characteristics and different valence states coexist in solution - the largest fraction of the soluble plutonium is in an oxidized form (+V,VI). The adsorption of plutonium to sediments is not completely reversible because of changes that occur in the relative amounts of the mixed oxidation states in solution with time. Further, any characteristics of /sup 239 +240/Pu described at one location may not necessarily be relevant in describing its behavior elsewhere following mobilization and migration. The relative amounts of /sup 241/Am to /sup 239 +240/Pu in the sedimentary deposits at Enewetak and Bikini may be altered in future years because of mobilization and radiological decay. Mobilization of /sup 239 +240/Pu is not a process unique to these atolls, and quantities in solution derived from sedimentary deposits can be found at other global sites. These studies in the equatorial Pacific have significance in assessing the long-term behavior of the transuranics in any marine environment. 22 references, 1 figure, 13 tables.

  11. LEAD COMMISSIONER DRAFT GUIDEBOOK NEW SOLAR HOMES PARTNERSHIP

    E-Print Network [OSTI]

    LEAD COMMISSIONER DRAFT GUIDEBOOK NEW SOLAR HOMES PARTNERSHIP GUIDEBOOK Seventh Edition Lead COMMISSION Edmund G. Brown, Jr., Governor #12;CALIFORNIA ENERGY COMMISSION Andrew McAllister Lead

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    Office of Environmental Management (EM)

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

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

    Notice of Availability of the Draft Environmental Impact Statement Lake Charles Carbon Capture and Sequestration Project, Lake Charles, Louisiana and Brazoria County, Texas The...

  15. EIS-0445: DOE Notice of Availability of the Draft Environmental...

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

    of the Draft Environmental Impact Statement for the Mountaineer Commercial Scale Carbon Capture and Storage Project, Mason County, West Virginia, DOEEIS-0445 (March 2011 - 76 FR...

  16. Microsoft Word - NOTICE OF AVAILABILITY Draft EA 09FEB2015

    Office of Environmental Management (EM)

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    Office of Environmental Management (EM)

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

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

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  20. EIS-0469: EPA Notice of Availability of a Draft Environmental...

    Office of Environmental Management (EM)

    EIS-0469: EPA Notice of Availability of a Draft Environmental Impact Statement Wilton IV Wind Energy Center; Burleigh County, North Dakota This EIS will evaluate the environmental...

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

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    Energy Savers [EERE]

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    Office of Environmental Management (EM)

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    Office of Environmental Management (EM)

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

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    Energy Savers [EERE]

    of Comment Period on the Draft Integrated, Interagency Pre-Application (IIP) Process for Electric Transmission Projects Requiring Federal Authorizations Extension of Comment...

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

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

    EPA Notice of Availability of the Draft Environmental Impact Statement Lyle Falls Fish Passage Project To Improve Fish Passage to Habitat in the Upper Part of the Watershed,...

  9. FEMP Seeking Public Comment on Draft M&V Guidelines

    Broader source: Energy.gov [DOE]

    FEMP is continuing its request for public comments on the Draft M&V Guidelines: Measurement and Verification for Performance-Based Contracts (Version 4.0).

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

    for the (GGS) to Eliminate 50-Megawatts (MW) Annual Average Operating Limit, Brown County, South Dakota. Notice of Availability for the Draft Environmental Impact...

  11. Department of Energy Issues Draft Renewable Energy and Efficient...

    Energy Savers [EERE]

    Renewable Energy and Efficient Energy Projects Solicitation to Foster Clean Energy Innovation Department of Energy Issues Draft Renewable Energy and Efficient Energy Projects...

  12. DRAFT Carbon Storage R&D Project Review Meeting

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

    Energy Management (BOEM) Melissa Batum, U.S. DOI, BOEM 1 DRAFT PLENARY SESSION - Regional Carbon Sequestration Partnerships Saline Injection Large-Scale Field Projects Moderator:...

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    Energy Savers [EERE]

    Amended Notice of Availability of a Draft Environmental Impact Statement Mohave County Wind Farm Project, Mohave County, Arizona EPA is amending the Notice of Availability for...

  14. EIS-0441: EPA Notice of Availability of a Draft Environmental...

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

    the availability of BLM's Draft Environmental Impact Statement for the Mohave County Wind Farm Project, Mohave County, Arizona. DOE's Western Area Power Administration is a...

  15. EIS-0447: DOE Notice of Availability of Draft Environmental Impact...

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

    Champlain Hudson Power Express Transmission Line Project, New York DOE announces the availability of a draft EIS to evaluate the potential environmental impacts of a DOE proposal...

  16. EIS-0447: EPA Notice of Availability of Draft Environmental Impact...

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

    Impact Statement Champlain Hudson Power Express Transmission Line Project, New York EPA announces the availability of a draft EIS to evaluate the potential environmental...

  17. EA-1902: Draft Environmental Assessment | Department of Energy

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

    a draft EA that evaluates the potential environmental impacts of the proposed Northern Wind Project in Summit, Roberts County, South Dakota. EA-1902-DEA-2014.pdf More Documents &...

  18. Draft Specifications for Application of UNFC-2009 to Renewable...

    Open Energy Info (EERE)

    of UNFC-2009 to Renewable Energy Resources. 12 June 2014 Edition. Geneva, Switzerland: UNECE. Retrieved from "http:en.openei.orgwindex.php?titleDraftSpecifications...

  19. EIS-0425: EPA Notice of Availability of Draft Environmental Impact...

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

    Notice of Availability of Draft Environmental Impact Statement for the Mid-Columbia Coho Restoration Program, DOEEIS-0425 (June 2011 - 76 FR 37111) More Documents & Publications...

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    Office of Environmental Management (EM)

    EIS-0431: DOE Notice of Availability of Draft Environmental Impact Statement Hydrogen Energy California's Integrated Gasification Combined Cycle and Carbon Capture and...

  1. EIS-0431: EPA Notice of Availability of Draft Environmental Impact...

    Energy Savers [EERE]

    EIS-0431: EPA Notice of Availability of Draft Environmental Impact Statement Hydrogen Energy California's Integrated Gasification Combined Cycle and Carbon Capture and...

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

    of Supplemental Draft Environmental Impact Statement Bay Delta Conservation Plan; Sacramento-San Joaquin Delta, California The Environmental Protection Agency announced the...

  3. Revised Draft Hanford Site Solid (Radioactive and Hazardous)...

    Office of Environmental Management (EM)

    Operations Office TITLE: Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE...

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    Energy Savers [EERE]

    EIS-0492: EPA Notice of Availability of Draft Environmental Impact Statement Oregon LNG Export Project (Warrenton, OR) and Washington Expansion Project (between Sumas and...

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    Energy Savers [EERE]

    EIS-0492: FERC Notice of Availability of Draft Environmental Impact Statement Oregon LNG Export Project (Warrenton, OR) and Washington Expansion Project (between Sumas and...

  6. Energy Department Releases Draft Advanced Fossil Energy Solicitation...

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

    of Section 1703. Within the draft solicitation, the Department has included a sample list illustrative of potential technologies for consideration. The Department welcomes...

  7. Revised Draft Guidance on Consideration of Greenhouse Gas Emissions...

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

    departments and agencies should consider the effects of greenhouse gas emissions and climate change in their National Environmental Policy Act reviews. The revised draft...

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

    EPA Notice of Availability of the Draft Environmental Impact Statement Orlando Gasification Project To Provide Cost-Shared Funding for Construction and Operation of Facilities...

  9. Microsoft Word - Draft SA Press Release_March 2011_jb

    National Nuclear Security Administration (NNSA)

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

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  11. EIS-0472: DOE Notice of Availability of a Draft Programmatic...

    Energy Savers [EERE]

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

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

    of the Draft Environmental Impact Statement and Public Hearing Notice for the Texas Clean Energy Project, near Odessa, Ector County, Texas, DOEEIS-0444 (March 2011 - 76...

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

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  15. Draft Revised Guidelines for Implementing Executive Order 11988, "Floodplain Management"

    Broader source: Energy.gov [DOE]

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  16. EIS-0478: EPA Notice of Availability of a Draft Environmental...

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

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

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

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

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

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