National Library of Energy BETA

Sample records for disposition authority number

  1. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

    Energy Savers [EERE]

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  2. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

    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 PartiesBuildingBudget ||Department ofRequest for Records Disposition

  3. Records Disposition

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

    1988-09-13

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

  4. Records Disposition

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

    1980-05-28

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

  5. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    1998-02-01

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

  6. Modal Dispositionalism 

    E-Print Network [OSTI]

    Barthuly, Joshua

    2015-05-01

    Let a modal truth be any truth that is about modal entities, such as essences, abilities, or dispositional properties, or that contains modal expressions such as: possibly, necessarily, may, must, could, would, can, and so on. Examples of modal...

  7. REQUEST FOR RECORDS DISPOSITION AUTHORITY

    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 About1996HowFOA Applicant WebinarSouthern California Edison onFOR RECORDS

  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. 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.

  10. EVILS AND DISPOSITIONS 

    E-Print Network [OSTI]

    Flattery, Tobias

    2012-04-18

    ? The privation theorist must ontologically account for evils in some way. As a provisional statement, on the account I propose, privative evils are understood in terms of dispositional properties, or powers, which a being that suffers the evil lacks but ought...

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

    SciTech Connect (OSTI)

    1994-04-30

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

  12. PF-4 actinide disposition strategy

    SciTech Connect (OSTI)

    Margevicius, Robert W [Los Alamos National Laboratory

    2010-05-28

    The dwindling amount of Security Category I processing and storage space across the DOE Complex has driven the need for more effective storage of nuclear materials at LANL's Plutonium Facility's (PF-4's) vault. An effort was begun in 2009 to create a strategy, a roadmap, to identify all accountable nuclear material and determine their disposition paths, the PF-4 Actinide Disposition Strategy (PADS). Approximately seventy bins of nuclear materials with similar characteristics - in terms of isotope, chemical form, impurities, disposition location, etc. - were established in a database. The ultimate disposition paths include the material to remain at LANL, disposition to other DOE sites, and disposition to waste. If all the actions described in the document were taken, over half of the containers currently in the PF-4 vault would been eliminated. The actual amount of projected vault space will depend on budget and competing mission requirements, however, clearly a significant portion of the current LANL inventory can be either dispositioned or consolidated.

  13. 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)

  14. DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM |

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

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  15. Savannah River Site Waste Disposition Project

    Office of Environmental Management (EM)

    Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste...

  16. Major Risk Factors to the Integrated Facility Disposition Project...

    Office of Environmental Management (EM)

    Major Risk Factors to the Integrated Facility Disposition Project Major Risk Factors to the Integrated Facility Disposition Project The scope of the Integrated Facility Disposition...

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

    SciTech Connect (OSTI)

    Walker, Stuart

    2013-07-01

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

  18. Policy on Asset Disposition Policy on Asset Disposition

    E-Print Network [OSTI]

    Sridhar, Srinivas

    than two years and a unit cost of more than $5,000. Federal Capital Assets ­ (capitalizable assets and disposes of these assets in accordance with the Uniform Administrative Requirements, Cost Principles property, whether capital or non-capital assets, but does not apply to disposition of real property. II

  19. MINIMIZING WASTE AND COST IN DISPOSITION OF LEGACY RESIDUES

    SciTech Connect (OSTI)

    J. BALKEY; M. ROBINSON

    2001-05-01

    Research is being conducted at the Los Alamos National Laboratory (LANL) which is directed toward development of a quantitative basis for disposition of actinide-bearing process residues (both legacy residues and residues generated from ongoing programmatic operations). This research is focused in two directions: (1) identifying minimum negative consequence (waste, dose, cost) dispositions working within regulatory safeguards termination criteria, and (2) evaluating logistics/consequences of across-the-board residue discards such as authorized at Rocky Flats under a safeguards termination variance. The first approach emphasizes Laboratory commitments to environmental stewardship, worker safety, and fiscal responsibility. This approach has been described as the Plutonium Disposition Methodology (PDM) in deference to direction provided by DOE Albuquerque. The second approach is born of the need to expedite removal of residues from storage for programmatic and reasons and residue storage safety concerns. Any disposition path selected must preserve the legal distinction between residues as Special Nuclear Material (SNM) and discardable materials as waste in order to insure the continuing viability of Laboratory plutonium processing facilities for national security operations.

  20. Neutron Assay System for Confinement Vessel Disposition

    SciTech Connect (OSTI)

    Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

    2012-07-13

    Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

  1. Weapons Dismantlement and Disposition NNSS Capabilities

    SciTech Connect (OSTI)

    Pat Arnold

    2011-12-01

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

  2. EM Waste and Materials Disposition & Transportation

    Office of Environmental Management (EM)

    On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief...

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

    Office of Environmental Management (EM)

    & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste inventories in a safe and compliant...

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

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

    TO: DISTRIBUTION FROM: Michael Owen (signed) Director, Office of Worker and Community Transition Department of Energy Washington, DC 20505 January 22, 2003 Disposition of...

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

    Office of Environmental Management (EM)

    Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 -...

  6. Hanford Tank Waste Retrieval, Treatment, and Disposition Framework...

    Office of Environmental Management (EM)

    Hanford Tank Waste Retrieval, Treatment, and Disposition Framework Hanford Tank Waste Retrieval, Treatment, and Disposition Framework Forty years of plutonium production at the...

  7. 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.

  8. Site license price adjustments for NPGowned journals with open access options Nature Publishing Group offers a number of options for authors wishing to publish with us, from

    E-Print Network [OSTI]

    Cai, Long

    Site license price adjustments for NPGowned journals with open access options Nature Publishing Group offers a number of options for authors wishing to publish with us, from open accessonly this is a real challenge for institutions, funders and publishers and we're examining how we might make things

  9. 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.

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  11. 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.

  12. 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.

  13. Request For Records Disposition Authority | Department of Energy

    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 About1996HowFOA Applicantof Years | DepartmentRelatedSouthern|(Per 42Department

  14. Request For Records Disposition Authority | Department of Energy

    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 About1996HowFOA Applicantof Years | DepartmentRelatedSouthern|(Per

  15. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergyPresidentialThis 3-D rendering ofForm documents the circumstancesLawrence

  16. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergyPresidentialThis 3-D rendering ofForm documents the

  17. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergyPresidentialThis 3-D rendering ofForm documents theAEC - Power Reactor

  18. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergyPresidentialThis 3-D rendering ofForm documents theAEC -

  19. Request For Records Disposition Authority | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergyPresidentialThis 3-DMarchLLC Open Annual Report I. Basic(December

  20. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

    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 PartiesBuildingBudget ||Department of

  1. 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...

  2. A COMPUTATIONAL THEORY OF DISPOSITIONS Lotfi A. Zadeh

    E-Print Network [OSTI]

    right, etc. Dispositions play a central role in human reasoning, since much of human knowledge and, especially, commousense knowledge, may be viewed as a collection of dispositions. The concept described in this paper is that a disposition may be viewed as a proposition with suppressed, or, more

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

    SciTech Connect (OSTI)

    J. T. Beck

    2007-04-26

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

  4. 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.

  5. 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.

  6. Disposition of excess plutonium using ``off-spec`` MOX pellets as a sintered ceramic waste form

    SciTech Connect (OSTI)

    Armantrout, G.A.; Jardine, L.J.

    1996-02-01

    The authors describe a potential strategy for the disposition of excess weapons plutonium in a way that minimizes (1) technological risks, (2) implementation costs and completion schedules, and (3) requirements for constructing and operating new or duplicative Pu disposition facilities. This is accomplished by an optimized combination of (1) using existing nuclear power reactors to ``burn`` relatively pure excess Pu inventories as mixed oxide (MOX) fuel and (2) using the same MOX fuel fabrication facilities to fabricate contaminated or impure excess Pu inventories into an ``off-spec`` MOX solid ceramic waste form for geologic disposition. Diversion protection for the SCWF to meet the ``spent fuel standard`` introduced by the National Academy of Sciences can be achieved in at least three ways. (1) One can utilize the radiation field from defense high-level nuclear waste by first packaging the SCWF pellets in 2- to 4-L cans that are subsequently encapsulated in radioactive glass in the Defense Waste Processing Facility (DWPF) glass canisters (a ``can-in-canister`` approach). (2) One can add {sup 137}Cs (recovered from defense wastes at Hanford and currently stored as CsCl in capsules) to an encapsulating matrix such as cement for the SCWF pellets in a small hot-cell facility and thus fabricate large monolithic forms. (3) The SCWF can be fabricated into reactor fuel-like pellets and placed in tubes similar to fuel assemblies, which can then be mixed in sealed repository containers with irradiated spent nuclear fuel for geologic disposition.

  7. Plutonium-bearing materials feed report for the DOE Fissile Materials Disposition Program alternatives

    SciTech Connect (OSTI)

    Brough, W.G. [Lawrence Livermore National Lab., CA (United States); Boerigter, S.T. [Los Alamos National Lab., NM (United States)

    1995-04-06

    This report has identified all plutonium currently excess to DOE Defense Programs under current planning assumptions. A number of material categories win clearly fan within the scope of the MD (Materials Disposition) program, but the fate of the other categories are unknown at the present time. MD planning requires that estimates be made of those materials likely to be considered for disposition actions so that bounding cases for the PEIS (Programmatic Environmental Impact Statement) can be determined and so that processing which may be required can be identified in considering the various alternatives. A systematic analysis of the various alternatives in reachmg the preferred alternative requires an understanding of the possible range of values which may be taken by the various categories of feed materials. One table identifies the current total inventories excess to Defense Program planning needs and represents the bounding total of Pu which may become part of the MD disposition effort for all materials, except site return weapons. The other categories, principally irradiated fuel, rich scrap, and lean scrap, are discussed. Another table summarizes the ranges and expected quantities of Pu which could become the responsibility of the MD program. These values are to be used for assessing the impact of the various alternatives and for scaling operations to assess PEIS impact. Determination of the actual materials to be included in the disposition program will be done later.

  8. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

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

    1991-12-31

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

  9. 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.

  10. 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.

  11. International Journal of Artificial Intelligence in Education Volume# (2011) Number 1560-4292/08/$17.00 YYYY IOS Press and the authors. All rights reserved.

    E-Print Network [OSTI]

    Young, R. Michael

    2011-01-01

    -4292/08/$17.00 © YYYY ­ IOS Press and the authors. All rights reserved. Integrating Learning, Problem Solving

  12. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

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

    Lead Idaho National Laboratory NEET ASI Review Meeting September 17, 2014 Used Fuel Disposition Today's Discussion n Our R&D Objectives n What Guides Our Work n...

  13. 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...

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

    Office of Environmental Management (EM)

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

  15. Idaho High-Level Waste & Facilities Disposition, Final Environmental...

    Office of Environmental Management (EM)

    must prepare an Environmental Impact Statement (EIS). Copies of the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement are available at the...

  16. ,"U.S. Natural Gas Monthly Supply and Disposition Balance"

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

    Monthly Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data...

  17. ,"U.S. Natural Gas Annual Supply and Disposition Balance"

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

    Annual Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data...

  18. Portsmouth RI/FS Report for the Site-Wide Waste Disposition Evaluation...

    Energy Savers [EERE]

    RIFS Report for the Site-Wide Waste Disposition Evaluation Project Portsmouth RIFS Report for the Site-Wide Waste Disposition Evaluation Project This Remedial Investigation and...

  19. International Journal of Artificial Intelligence in Education Volume# (YYYY) Number 1560-4292/08/$17.00 YYYY IOS Press and the authors. All rights reserved.

    E-Print Network [OSTI]

    Mostow, Jack

    -4292/08/$17.00 © YYYY ­ IOS Press and the authors. All rights reserved. Toward Exploiting EEG Input in a Reading Tutor

  20. Dismantlement and Disposition | National Nuclear Security Administration

    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 Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a CConversion| Nationaland Disposition |

  1. Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Jeremy Gwin and Douglas Frenette

    2010-04-08

    This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy [DOE] Order DOE O 5400.5, “Radiation Protection of the Public and the Environment”). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the contractor. A decision was reached between the NTS regulator and NSTec, opting for alternative authorized limits from DOE Headquarters. In doing so, NSTec personnel performed a dose model using the DOE-approved modeling code RESRAD-BUILD v3.5 to evaluate scenarios. The parameters used in the dose model were conservative. NSTec’s Radiological Engineering Calculation, REC-2010-001, “Public Dose Estimate from the EMAD 25 Ton Locomotive,” concluded that the four scenarios evaluated were below the 25-millirem per year limit, the “likely” dose scenarios met the “few millirem in a year” criteria, and that the EMAD 25-ton locomotive met the radiological requirements to be released with residual radioactivity to the public.

  2. Author's copy. Final version published by Elsevier in Energy Procedia volume 1 number 1, pages 2809-2816, February 2009. Proceedings of the 9th International Conference on Greenhouse Gas Control Technologies (GHGT-

    E-Print Network [OSTI]

    Information System; storage capacities; aquifers; coual deposits; depleted fields; risk assessment 1Author's copy. Final version published by Elsevier in Energy Procedia volume 1 number 1, pages 2809 to look for potential storage zones in France D. Bonijoly1 , M. Ha-Duong6 , A. Leynet11 ; A. Bonneville2

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

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

  4. 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.

  5. 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.

  6. Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives

    SciTech Connect (OSTI)

    Dimenna, R.A.; Jacobs, R.A.; Taylor, G.A.; Durate, O.E.; Paul, P.K.; Elder, H.H.; Pike, J.A.; Fowler, J.R.; Rutland, P.L.; Gregory, M.V.; Smith III, F.G.; Hang, T.; Subosits, S.G.; Campbell, S.G.

    2001-03-26

    The High Level Waste (HLW) Salt Disposition Systems Engineering Team was formed on March 13, 1998, and chartered to identify options, evaluate alternatives, and recommend a selected alternative(s) for processing HLW salt to a permitted wasteform. This requirement arises because the existing In-Tank Precipitation process at the Savannah River Site, as currently configured, cannot simultaneously meet the HLW production and Authorization Basis safety requirements. This engineering study was performed in four phases. This document provides the technical bases, assumptions, and results of this engineering study.

  7. Americium/Curium Disposition Life Cycle Planning Study

    SciTech Connect (OSTI)

    Jackson, W.N.; Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

    1998-04-30

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

  8. 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.

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

    Broader source: Energy.gov [DOE]

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

  10. Off-scale salary dispositions It is very important that the dispositions of off-scale salaries be specified in departmental letters

    E-Print Network [OSTI]

    California at San Diego, University of

    Off-scale salary dispositions It is very important that the dispositions of off-scale salaries in determining the correct disposition. Market off-scale salaries New: A department may propose a "new" market off-scale salary award in the following circumstances: 1) a market off-scale salary is being requested

  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. Disposition of excess weapons plutonium from dismantled weapons

    SciTech Connect (OSTI)

    Jardine, L.J.

    1997-01-01

    With the end of the Cold War and the implementation of various nuclear arms reduction agreements, US and Russia have been actively dismantling tens of thousands of nuclear weapons. As a result,large quantities of fissile materials, including more than 100 (tonnes?) of weapons-grade Pu, have become excess to both countries` military needs. To meet nonproliferation goals and to ensure the irreversibility of nuclear arms reductions, this excess weapons Pu must be placed in secure storage and then, in timely manner, either used in nuclear reactors as fuel or discarded in geologic repositories as solid waste. This disposition in US and Russia must be accomplished in a safe, secure manner and as quickly as practical. Storage of this Pu is a prerequisite to any disposition process, but the length of storage time is unknown. Whether by use as fuel or discard as solid waste, disposition of that amount of Pu will require decades--and perhaps longer, if disposition operations encounter delays. Neither US nor Russia believes that long-term secure storage is a substitute for timely disposition of excess Pu, but long-term, safe, secure storage is a critical element of all excess Pu disposition activities.

  13. DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

    SciTech Connect (OSTI)

    Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

    2003-02-27

    The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.

  14. Title: Author(s):

    Office of Scientific and Technical Information (OSTI)

    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 MunicipalTechnicalInformation FederatedInformationTITLE: AUTHOR(S)Patterns,(Journal A uttwr(s):

  15. Analysis and section of processes for the disposition of excess fissile material from nuclear weapon dismantlement in the United States

    SciTech Connect (OSTI)

    Myers, B.R.; Armantrout, G.A. [Lawrence Livermore National Lab., CA (United States); Erickson, R. [Los Alamos National Lab., NM (United States)

    1995-02-01

    The end of the cold war and the acceleration of nuclear disarmament efforts by the United States (US) and Russia are generating large quantities of surplus fissile nuclear materials that are no longer needed for military purposes. The safe and secure disposition of this surplus material to prevent theft or reuse in weapons has become a high priority for the US Department of Energy (USDOE). Many options exist for storage and disposition (use or disposal) of these surplus materials. The criteria, which have been developed from the basis for a preliminary ``screening`` of options, to eliminate from further consideration those options that do not meet minimal requirements. Factors, or attributes, contained in the screening and selection criteria include: (1) resistance to theft and diversion by unauthorized parties, (2) resistance to retrieval, extraction, and reuse by the host nation, (3) technical viability, (4) environmental, safety, and health impacts, (5) cost effectiveness, (6) timeliness, (7) fostering of progress and cooperation with Russia and others, (8) public and institutional acceptance, and (9) additional benefits. The evaluation of environmental impacts, in accordance with the US National Environmental Policy Ac (NEPA) process, is an integral part of the overall evaluation process. Because of the variety of physical and chemical forms of the nuclear material inventory, and because of the large number of possible disposition technologies and final forms, several hundred possible pathways to disposition have been defined and have undergone a systematic selection process. Also, because nuclear material disposition will have far ranging impacts, extensive public, in the form of public and stakeholder, input was integral to the selection process.

  16. 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.

  17. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23

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

  18. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Jones, R.; Carter, J.

    2010-10-13

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

  19. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Carter, J.

    2011-01-03

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

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

    SciTech Connect (OSTI)

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

    1995-10-01

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

  1. Poster Title LA-UR Number Author(s) Thumbnail

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

    Public Meeting LA-UR-11-10650 Debbie Apodaca Pesiri Los Alamos National Laboratory Stormwater Individual Permit Areas May 2011 Public Meeting LA-UR-11-10650 Steve Veenis Site...

  2. Poster Title LA-UR Number Author(s) Thumbnail

    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 wouldMass mapSpeedingProgram Guidelines This document outlines the majorL. Shi, J. del

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

    SciTech Connect (OSTI)

    Glenn, J.; Patterson, J.; DeRoos, K.; Patterson, J.E.; Mitchell, K.G.

    2012-07-01

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

  4. DOE/EA-1239 Environmental Assessment Disposition...

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

    the Atomic Energy Act, that (i) it has the fll capacity, power and authority to enter into and perfor this Sales Contract and the transactions contemplated herein, and (ii)...

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2011-06-22

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

  6. PHYSICAL AND CHEMICAL MEASUREMENTS NEEDED TO SUPPORT DISPOSITION OFSAVANNAH RIVER SITE RADIOACTIVE HIGH LEVEL WASTE SLUDGE

    SciTech Connect (OSTI)

    Hamm, B

    2007-05-17

    Radioactive high level waste (HLW) sludge generated as a result of decades of production and manufacturing of plutonium, tritium and other nuclear materials is being removed from storage tanks and processed into a glass waste-form for permanent disposition at the Federal Repository. Characterization of this HLW sludge is a prerequisite for effective planning and execution of sludge disposition activities. The radioactivity of HLW makes sampling and analysis of the sludge very challenging, as well as making opportunities to perform characterization rare. In order to maximize the benefit obtained from sampling and analysis, a recommended list of physical property and chemical measurements has been developed. This list includes distribution of solids (insoluble and soluble) and water; densities of insoluble solids, interstitial solution, and slurry rheology (yield stress and consistency); mineral forms of solids; and primary elemental and radioactive constituents. Sampling requirements (number, type, volume, etc.), sample preparation techniques, and analytical methods are discussed in the context of pros and cons relative to end use of the data. Generation of useful sample identification codes and entry of results into a centralized database are also discussed.

  7. Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies

    SciTech Connect (OSTI)

    Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

    2010-01-01

    We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.

  8. Update of the Used Fuel Disposition Campaign Implementation Plan

    SciTech Connect (OSTI)

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

    2014-09-01

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

  9. 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.

  10. Accelerating the disposition of transuranic waste from LANL - 9495

    SciTech Connect (OSTI)

    Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

    2009-01-01

    Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

  11. Portsmouth Waste Disposition Record of Decision | Department of Energy

    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 energyDepartment of Energy PortsmouthWaste Disposition

  12. Non-proliferation issues for the disposition of fissile materials using reactor alternatives

    SciTech Connect (OSTI)

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

    1996-02-01

    The Department of Energy (DOE) is analyzing long-term storage on options for excess weapons-usable fissile materials. A number of the disposition alternatives are being considered which involve the use of reactors. The various reactor alternatives are all very similar and include front-end processes that could convert plutonium to a usable form for fuel fabrication, a MOX fuel fab facility, reactors to bum the MOX fuel and ultimate disposal of spent fuel in some geologic repository. They include existing, partially completed, advanced or evolutionary light water reactors and Canadian deuterium uranium (CANDU) reactors. In addition to the differences in the type of reactors, other variants on these alternatives are being evaluated to include the location and number of the reactors, the location of the mixed oxide (MOX) fabrication facility, the ownership of the facilities (private or government) and the colocation and/or separation of these facilities. All of these alternatives and their variants must be evaluated with respect to non-proliferation resistance. Both domestic and international safeguards support are being provided to DOE`s Fissile Materials Disposition Program (FMDP) and includes such areas as physical protection, nuclear materials accountability and material containment and surveillance. This paper will focus on how the non-proliferation objective of reducing security risks and strengthening arms reduction will be accomplished and what some of the nonproliferation issues are for the reactor alternatives. Proliferation risk has been defined in terms of material form, physical environment, and the level of security and safeguards that is applied to the material. Metrics have been developed for each of these factors. The reactor alternatives will be evaluated with respect to these proliferation risk factors at each of the unit process locations in the alternative.

  13. Multimedia Authoring III: Web Authoring

    E-Print Network [OSTI]

    Dahlquist, Kam D.

    Multimedia Authoring III: Web Authoring · Many multimedia applications today have a Web manifestation, whether it is the application itself or something about the application, like a DVD info Web site · The Web can "wrap" other types of content as well: Flash, audio, video · The Web provides technologies

  14. May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION

    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 nAand DOE Safetyof Energy ThisSitesStoragePlanning Efforts |3) 05-90

  15. A model for computer frustration: the role of instrumental and dispositional factors

    E-Print Network [OSTI]

    Shneiderman, Ben

    A model for computer frustration: the role of instrumental and dispositional factors on incident 20742, USA Available online 16 April 2004 Abstract Frustration is almost universally accepted

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

    Broader source: Energy.gov [DOE]

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

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

    SciTech Connect (OSTI)

    Bowers, J.A.

    2000-01-03

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

  18. 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.

  19. 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.

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

  1. 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.

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

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

    1999-09-29

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

  3. -Actin: disposition, quantities, and estimated effects on lung recoil and compliance

    E-Print Network [OSTI]

    -Actin: disposition, quantities, and estimated effects on lung recoil and compliance E. H. OLDMIXON, Jr. -Actin: disposition, quantities, and estimated effects on lung recoil and compliance. J Appl by measuring dispo- sition and quantities of -smooth muscle actin in rat and guinea pig lungs and modeling its

  4. Policy on Retention and Disposition of University Records Policy on Retention and

    E-Print Network [OSTI]

    Sridhar, Srinivas

    Policy on Retention and Disposition of University Records 06/01/2012 Policy on Retention and Disposition of University Records I. Purpose and Scope This policy and its implementing procedures will assist, as well as to optimize the use of storage space and minimize the cost of record retention. This policy

  5. 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.

  6. 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.

  7. Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx

    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 GasAdjustments (BillionProvedTravelInformation Resources»Jim ManionBrochureFACA and EMMaterials and Disposition

  8. CXD 4605, Disposition Excess Equipment from Alpha 1 (4605)

    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 OutreachProductswsicloudwsiclouddenDVA N C E D B LReports from the CloudGEGR-N Goods POCTBT |CUD-55Disposition

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

    SciTech Connect (OSTI)

    WEST LD

    2011-01-13

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

  10. Author Select

    Office of Scientific and Technical Information (OSTI)

    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 MunicipalTechnical Report:Speeding accessby a contractor ofvarDOE PAGES11 PPPL-AtmosphericAuthor

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

    SciTech Connect (OSTI)

    None

    2010-04-01

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

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

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

    1998-05-01

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

  13. Acceleration of Los Alamos National Laboratory transuranic waste disposition

    SciTech Connect (OSTI)

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

    2007-07-01

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

  14. ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

    SciTech Connect (OSTI)

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

    2007-01-04

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

  15. Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite

    SciTech Connect (OSTI)

    Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

    2008-01-15

    Specimens of titanate ceramics containing approximately 10 mass% 238Pu were tested to determine the long-term effects of radiation-induced damage from the ? decay of 239Pu that would have been disposed of in the nuclear-waste repository at Yucca Mountain. These tests provided information on the changes in bulk properties such as dimensions, densities, and chemical durability. Although these materials become amorphous at low doses, the specimens remained physically strong. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, in combination with results reported previously on similar materials, the material remains a physically viable material for the disposition of surplus weapons-grade Pu.

  16. 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.

  17. Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite

    SciTech Connect (OSTI)

    Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

    2008-01-15

    This is the second of two papers on the results of radiation-induced damage accumulation in titanate ceramics that potentially could be used for weapons grade plutonium disposition. In the first paper we discussed the results from pyrochlore (betafite) based ceramics. In this paper, we discuss the effects of radiation-induced damage on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics from the alpha decay of 238Pu. Macro (bulk) and micro (X-ray diffraction) swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. It took approximately 740 days (2.6?1018 ?/g) for the specimens to become X-ray amorphous—longer for the swelling to saturate. Unlike what we observed for the pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)?10-3 g/(m2?d). Very little pH dependence was observed for zirconolite specimens and, like we observed for the pyrochlore-bearing ceramics in this study, there was no dependence on the amount of radiation-induced damage. As with the pyrochlore, these materials did not become substantially friable with increasing radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

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

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2010-10-01

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

  19. 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...

  20. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  1. 105-N basin sediment disposition phase-two sampling and analysis plan

    SciTech Connect (OSTI)

    Smith, R. C.

    1997-03-14

    The sampling and analysis plan for Phase 2 of the 105-N Basin sediment disposition task defines the sampling and analytical activities that will be performed to support characterization of the sediment and selection of an appropriate sediment disposal option.

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

    E-Print Network [OSTI]

    Cerefice, Gary Steven

    1999-01-01

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

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

    SciTech Connect (OSTI)

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

    2010-01-01

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

  4. I am applying for authorization to use DataTel number listed below for purchasing from Printing Services' online storefront. By submitting this form I am accepting any and all payment responsibilities

    E-Print Network [OSTI]

    Branoff, Theodore J.

    storefront. Check all conditions which you require: I Authorize all orders up to $ ______________ per fiscal Services' online storefront. By submitting this form I am accepting any and all payment responsibilities for a single order. I wish to approve all orders prior to shipping. The fiscal agent will be notified via email

  5. 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.

  6. 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.

  7. Evaluation of existing United States` facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition

    SciTech Connect (OSTI)

    Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

    1995-12-31

    A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications.

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

    SciTech Connect (OSTI)

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

    2002-02-26

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

  9. Disposition of nuclear waste using subcritical accelerator-driven systems

    SciTech Connect (OSTI)

    Venneri, F.; Li, N.; Williamson, M.; Houts, M.; Lawrence, G.

    1998-12-01

    Studies have shown that the repository long-term radiological risk is from the long-lived transuranics and the fission products Tc-99 and I-129, thermal loading concerns arise mainly form the short-lived fission products Sr-90 and Cs-137. In relation to the disposition of nuclear waste, ATW is expected to accomplish the following: (1) destroy over 99.9% of the actinides; (2) destroy over 99.9% of the Tc and I; (3) separate Sr and Cs (short half-life isotopes); (4) separate uranium; (5) produce electricity. In the ATW concept, spent fuel would be shipped to a ATW site where the plutonium, other transuranics and selected long-lived fission products would be destroyed by fission or transmutation in their only pass through the facility. This approach contrasts with the present-day reprocessing practices in Europe and Japan, during which high purity plutonium is produced and used in the fabrication of fresh mixed-oxide fuel (MOX) that is shipped off-site for use in light water reactors.

  10. 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.

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

    SciTech Connect (OSTI)

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

    2009-09-10

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

  12. Features, Events and Processes for the Used Fuel Disposition Campaign

    SciTech Connect (OSTI)

    Blink, J A; Greenberg, H R; Caporuscio, F A; Houseworth, J E; Freeze, G A; Mariner, P; Cunnane, J C

    2010-12-15

    The Used Fuel Disposition (UFD) Campaign within DOE-NE is evaluating storage and disposal options for a range of waste forms and a range of geologic environments. To assess the potential performance of conceptual repository designs for the combinations of waste form and geologic environment, a master set of Features, Events, and Processes (FEPs) has been developed and evaluated. These FEPs are based on prior lists developed by the Yucca Mountain Project (YMP) and the international repository community. The objective of the UFD FEPs activity is to identify and categorize FEPs that are important to disposal system performance for a variety of disposal alternatives (i.e., combinations of waste forms, disposal concepts, and geologic environments). FEP analysis provides guidance for the identification of (1) important considerations in disposal system design, and (2) gaps in the technical bases. The UFD FEPs also support the development of performance assessment (PA) models to evaluate the long-term performance of waste forms in the engineered and geologic environments of candidate disposal system alternatives. For the UFD FEP development, five waste form groups and seven geologic settings are being considered. A total of 208 FEPs have been identified, categorized by the physical components of the waste disposal system as well as cross-cutting physical phenomena. The combination of 35 waste-form/geologic environments and 208 FEPs is large; however, some FEP evaluations can cut across multiple waste/environment combinations, and other FEPs can be categorized as not-applicable for some waste/environment combinations, making the task of FEP evaluation more tractable. A FEP status tool has been developed to document progress. The tool emphasizes three major areas that can be statused numerically. FEP Applicability documents whether the FEP is pertinent to a waste/environment combination. FEP Completion Status documents the progress of the evaluation for the FEP/waste/environment combination. FEP Importance documents the potential importance for the FEP/waste/environment combination to repository performance.

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

    E-Print Network [OSTI]

    Columbia University

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

  14. Pharmacokinetic disposition of lidocaine and its metabolites following a single intravenous dose in healthy and proteinuric dogs 

    E-Print Network [OSTI]

    Wilkie, William Scott

    2002-01-01

    collection when disposition of lidocaine is used as a test of hepatic dysfunction. The second goal was to compare the disposition of lidocaine and its metabolites in normal dogs (G1) and dogs with Alport syndrome, a hereditary proteinuric nephritis (G2...

  15. MOTOR POOL RESERVATIONS Reservation Number:_______________

    E-Print Network [OSTI]

    Ottino, Julio M.

    of Department Chair or Organization Advisor: ________________________________________ Chart String Number: Fund: ______________________________________________________________________ Name of Department or Organization: _____________________________________________________ Name reservations require the "Organization Authorization for University Vehicles" form to be faxed to Motor Pool

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

    SciTech Connect (OSTI)

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

    2012-12-11

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

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

    SciTech Connect (OSTI)

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

    2012-12-20

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

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

    Broader source: Energy.gov [DOE]

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

  19. Reactor options for disposition of excess weapon plutonium: Selection criteria and decision process for assessment

    SciTech Connect (OSTI)

    Edmunds, T.; Buonpane, L.; Sicherman, A.; Sutcliffe, W.; Walter, C.; Holman, G.

    1994-01-01

    DOE is currently considering a wide range of alternatives for disposition of excess weapon plutonium, including using plutonium in mixed oxide fuel for light water reactors (LWRs). Lawrence Livermore National Laboratory (LLNL) has been tasked to assist DOE in its efforts to develop a decision process and criteria for evaluating the technologies and reactor designs that have been proposed for the fission disposition alternative. This report outlines an approach for establishing such a decision process and selection criteria. The approach includes the capability to address multiple, sometimes conflicting, objectives, and to incorporate the impact of uncertainty. The approach has a firm theoretical foundation and similar approaches have been used successfully by private industry, DOE, and other government agencies to support and document complex, high impact technology choice decisions. Because of their similarity and relatively simple technology, this report focuses on three light water reactors studied in Phase 1 of the DOE Plutonium Disposition Study. The decision process can be extended to allow evaluation of other reactor technologies and disposition options such as direct disposal and retrievable storage.

  20. 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.

  1. A. E. K.Ris Ris-M-Dl^ Title and author(s)

    E-Print Network [OSTI]

    A. E. K.Risø Risø-M-Dl^ Title and author(s) Application of Statistical Linear El -it:tic Fracture illustrations Date October 1 -}? $ Department or group R e a c t o r Group's own registration number(s) 25 crack, same time and ated as statisti- ty functions, tial cracks, f failure prob- program utilizing ce

  2. 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.

  3. Job Salary Prediction Anonymous Author(s)

    E-Print Network [OSTI]

    Freitas, Nando de

    050 051 052 053 Job Salary Prediction Anonymous Author(s) Affiliation Address email Abstract Kaggle based classifieds company, hosted a Kaggle competition with the goal of improving job salary pre- dictions for job postings in which the salary does not appear. Using various lin- ear models, random

  4. Used fuel disposition campaign international activities implementation plan.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2011-06-29

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

  5. Other Contracting Authority NNSA ORGANIZATION HCA LIMIT PHONE NUMBER

    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 AEnergy Managing853926Families | Department of EnergyThanks to funding

  6. Change Number

    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 OutreachProductswsicloudwsiclouddenDVA N C E D BGene Network ShapingDate: M-16-04-04 Federal FacilityChange Number

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

    E-Print Network [OSTI]

    Funkhouser, Rena Rebecca

    2008-10-10

    Aggressiveness, nervousness, flightiness, gregariousness and overall disposition were evaluated in F2 Nellore-Angus embryo transfer calves (n = 443) from 13 full sib families and in half Bos indicus, half Bos taurus ...

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

    SciTech Connect (OSTI)

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

    2011-06-27

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

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

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

  10. 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.

  11. 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.

  12. 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.

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

    SciTech Connect (OSTI)

    Williams, K.A.

    1999-10-01

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

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

    SciTech Connect (OSTI)

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

    1994-10-01

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

  15. Development and implementation of attractiveness Level E criteria and the plutonium disposition methodology

    SciTech Connect (OSTI)

    Christensen, D.C.; Robinson, M.A.

    1998-03-01

    Historically, the Department of Energy used the Economic Discard Limits (EDLs), those Special Nuclear Material (SNM) concentrations in residue matrices below which production of new SNM was more economic than SNM recovery, as a basis for discard decisions. In 1994, a joint team from DOE Defense Programs (DP) and Environmental Management (EM) determined that the EDLs were no longer a valid discriminator and directed that SNM disposition consider instead 12 specific criteria, foremost of which are waste minimization, environmental impacts, safety, proliferation concerns, and cost. In response, the Los Alamos National Laboratory developed a technical basis for determining SNM bearing materials unattractive for proliferation purposes and a quantitative method for predicting materials disposition consequences as a basis for decision making called the plutonium disposition methodology. The objective of attractiveness Level E criteria is to insure that waste is unattractive for proliferation or terrorist purposes. Level E criteria is about 0.17 kg Pu per 208 liter drum (requiring diversion of a minimum of 54 drums, assuming 100% recovery efficiency).

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

    SciTech Connect (OSTI)

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

    2009-06-01

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

  17. Development of an alternate pathway for materials destined for disposition to WIPP

    SciTech Connect (OSTI)

    Ayers, Georgette Y [Los Alamos National Laboratory; Mckerley, Bill [Los Alamos National Laboratory; Veazey, Gerald W [Los Alamos National Laboratory; Ricketts, Thomas E [Los Alamos National Laboratory

    2010-01-01

    The Los Alamos National Laboratory currently has an inventory of process residues that may be viable candidates for disposition to the Waste Isolation Pilot Project (WIPP) located at Carlsbad, New Mexico. A recent 'Attractiveness Level D' exemption allows for the discard of specified intractable materials regardless of the percent plutonium. However, the limits with respect to drum loadings must be met. Cementation is a key component of the aqueous nitrate flowsheet and serves as a 'bleed-off' stream for impurities separated from the plutonium during processing operations. The main 'feed' to the cementation operations are the 'bottoms' from the evaporation process. In the majority of cases, the cemented bottoms contain less than the allowed amount per drum for WIPP acceptance. This project would expand the route to WIPP for items that have no defined disposition path, are difficult to process, have been through multiple passes, have no current recovery operations available to recover the plutonium and that are amenable to cementation. This initial work will provide the foundation for a full scale disposition pathway of the candidate materials. Once the pathway has been expanded and a cementation matrix developed, routine discard activities will be initiated.

  18. 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.

  19. 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.

  20. Recycling Authorizations: Toward Secondary and Approximate Authorizations Model

    E-Print Network [OSTI]

    of matching best suitable approximate authorizations. 1 Introduction Although, every authorization decision

  1. Sealed Source Security and Disposition: Progress and Prospects - 13515

    SciTech Connect (OSTI)

    Jennison, Meaghan [National Nuclear Security Administration, Washington, DC (United States)] [National Nuclear Security Administration, Washington, DC (United States); Martin, David W. [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States)] [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States); Cuthbertson, Abigail [US DOE, Washington, DC (United States)] [US DOE, Washington, DC (United States)

    2013-07-01

    Due to their high activity and portability, unsecured or abandoned sealed sources could cause significant health or environmental damage. Further, some of these sources could be used either individually or in aggregate in radiological dispersal devices commonly referred to as 'dirty bombs', resulting in significant social disruption and economic impacts in the billions of dollars. Disposal access for disused sealed sources, however, has been a serious challenge. From 2008 to 2012, sealed source disposal was available to only 14 states; additionally, waste acceptance criteria for sealed sources at the low-level waste disposal facilities in operation both prior to and after 2012 exclude some common yet potentially dangerous sealed sources. Recent developments, however, suggest that significant improvement in addressing this challenge is possible, although challenges remain. These developments include 1) the initiation of operations at the Waste Control Specialists (WCS) commercial low-level radioactive waste (LLRW) disposal facility in Andrews County, Texas; 2) the potential for significant revisions of the U.S. Nuclear Regulatory Commission's (NRC) 1995 'Final Branch Technical Position on Concentration Averaging and Encapsulation' (1995 BTP); and 3) the Utah Department of Environmental Quality's (UDEQ) approval of a license variance for sealed source disposal at the EnergySolutions LLRW disposal facility near Clive, Utah. (authors)

  2. Ramsey Numbers Involving Cycles Stanislaw P. Radziszowski

    E-Print Network [OSTI]

    Radziszowski, Stanislaw P.

    Ramsey Numbers Involving Cycles Stanislaw P. Radziszowski Department of Computer Science Rochester and data on Ramsey numbers involving cycles. This survey is based on the author's 2009 revi- sion #12 of the Dynamic Survey DS1, "Small Ramsey Numbers", at the Electronic Journal of Combinatorics. Table of Contents

  3. Number Theory I: Tools and Diophantine Equations

    E-Print Network [OSTI]

    Cohen, Henri

    covered by two other books of the author [Coh0] and [Coh1]. The central (although not unique) theme in integers, rational numbers, or more generally in algebraic numbers. This theme is in particular the central of the reader that he or she is familiar with the standard basic theory of number fields, up to and including

  4. 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.

  5. Data quality objectives for Ion Exchange Module (IXM) disposition

    SciTech Connect (OSTI)

    Choi, I.

    1995-01-31

    This Data Quality Objective (DQO) document presents the data needs and accuracy requirements for sampling ion exchange modules at the K Basins, 100 K Area, to determine if there is a hydrogen gas buildup within the modules. This document was produced by PNL, with the assistance of Neptune and Associates, and was partly funded (for facilitator) by DOE-HQ as a demonstration DQO for EM activities. PNL involved a number of PNL, WHC and support contract staff (including external technical consultants) in meetings to define the data needed, along with the necessary accuracy, to resolve issues associated with hydrogen accumulation in Ion Exchange Modules (IXMS) that were generated prior to July 1994 and only have one nuc-fil vent. IXMs generated after July 1994 have multiple nuc-fil vents and do not require sampling. PNL transmitted this DQO to WHC on January 31, 1995. This Supporting Document is to assure that the document is captured into the document retrieval system. WHC review focused on the acceptability of the technical conclusions such that the data collected will meet minimum operational, safety and environmental needs.

  6. DOE NE Used Fuel Disposition FY2015 Working Group Presentations http://energy.sandia.gov/energy/nuclear-energy/ne-workshops/ufd-working-group-2015/

    E-Print Network [OSTI]

    DOE NE Used Fuel Disposition FY2015 Working Group Presentations http://energy.sandia.gov/energy/nuclear-energy 1 of 5 #12;DOE NE Used Fuel Disposition FY2015 Working Group Presentations http://energy.sandia.gov/energy/nuclear-energy Level Waste Rigali UFD WG 2015-06-10 Wed Afternoon 1245 Salt Repository Research Actinide and Microbial

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

    SciTech Connect (OSTI)

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

    1998-12-01

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

  8. ,"U.S. Natural Gas Monthly Supply and Disposition Balance"

    U.S. Energy Information Administration (EIA) 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| Open Energy Informationmonthly gasoline price to fall to $3.43U.S.longec 188 U.S.1SalesMonthly Supply and Disposition

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

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

  10. 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.

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

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

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

  12. SRNL report for the tank waste disposition integrated flowsheet: Corrosion testing

    SciTech Connect (OSTI)

    Wyrwas, R. B.

    2015-09-30

    A series of cyclic potentiodynamic polarization (CPP) tests were performed in support of the Tank Waste Disposition Integrated Flowsheet (TWDIF). The focus of the testing was to assess the effectiveness of the SRNL model for predicting the amount of nitrite inhibitor needed to prevent pitting induced by increasing halide concentrations. The testing conditions were selected to simulate the dilute process stream that is proposed to be returned to tank farms from treating the off-gas from the low activity waste melter in the Waste Treatment and Immobilization Plant.

  13. Disposition of excess weapon plutonium in deep boreholes - site selection handbook

    SciTech Connect (OSTI)

    Heiken, G.; Woldegabriel, G.; Morley, R.; Plannerer, H.; Rowley, J.

    1996-09-01

    One of the options for disposing of excess weapons plutonium is to place it near the base of deep boreholes in stable crystalline rocks. The technology needed to begin designing this means of disposition already exists, and there are many attractive sites available within the conterminous United States. There are even more potential sites for this option within Russia. The successful design of a borehole system must address two criteria: (1) how to dispose of 50 metric tons of weapons plutonium while making it inaccessible for unauthorized retrieval, and (2) how to prevent contamination of the accessible biosphere, defined here as the Earth`s surface and usable groundwaters.

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

    SciTech Connect (OSTI)

    Marra, J

    2006-11-15

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

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26

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

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

    SciTech Connect (OSTI)

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

    2002-02-26

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

  17. OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY

    E-Print Network [OSTI]

    Veiga, Pedro Manuel Barbosa

    OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY June 30, 2010 #12;OKLAHOMA STATE UNIVERSITY MEDICAL Authority Members Oklahoma State University Medical Authority Tulsa, Oklahoma We have audited the accompanying statements of financial position of the Oklahoma State University Medical Authority (the

  18. OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY

    E-Print Network [OSTI]

    Veiga, Pedro Manuel Barbosa

    OKLAHOMA STATE UNIVERSITY MEDICAL AUTHORITY June 30, 2009 #12;OKLAHOMA STATE UNIVERSITY MEDICAL Authority Members Oklahoma State University Medical Authority Tulsa, Oklahoma We have audited the accompanying statements of financial position of the Oklahoma State University Medical Authority (the

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

    SciTech Connect (OSTI)

    1998-03-01

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

  20. 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.

  1. Work Authorization System

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

    2005-04-21

    To establish a work authorization and control process for work performed by designated site and facility management contractors, and other contractors as determined by the procurement executive, consistent with the budget execution and program evaluation requirements of the Department of Energy's (DOE's) Planning, Programming, Budgeting, and Evaluation process. Cancels DOE O 412.1.

  2. Work Authorization System

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

    2005-04-21

    To establish a work authorization and control process for work performed by designated site and facility management contractors, and other contractors as determined by the procurement executive, consistent with the budget execution and program evaluation requirements of the Department of Energy's Planning, Programming, Budgeting, and Evaluation process. Admin Chg 1, dated 5-21-2014, cancels DOE O 412.1A.

  3. Work Authorization System

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

    1999-04-20

    It establishes a work authorization and control process for work performed by designated management and operating (M&O), management and integrating (M&I), environmental restoration management contracts (ERMC) and other contracts determined by the Procurement Executive (hereafter referred to as M&O contractors). Cancels DOE O 5700.7C. Canceled by DOE O 412.1A.

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

    E-Print Network [OSTI]

    Columbia University

    of solid wastes and advance sustainable waste management in the U.S. to the level of several leading! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on data provided by the waste management agencies of the fifty states. The SOG survey was not carried out

  5. The Effects of Music-Mathematics Integrated Curriculum and Instruction on Elementary Students’ Mathematics Achievement and Dispositions 

    E-Print Network [OSTI]

    An, Song

    2012-07-16

    and the disposition between the two groups. The students in the music group received music-mathematics integrated lessons. A quasi-experiment time series design with multiple pretests, mid-tests and posttests was utilized for investigating the effects of music...

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

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-02-26

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

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

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16 September 2014 ABSTRACT: Green River Locks and Dams 3 through 6 and Barren River Lock and Dam 1 were. The Green River Locks and Dams 5 and 6 ceased operations in 1951 due to a marked decline in navigation

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

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Blink, James A.; Rechard, Robert Paul; Perry, Frank; Jenkins-Smith, Hank C.; Carter, Joe; Nutt, Mark; Cotton, Tom

    2010-09-01

    This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

  9. Dispositional reflections 

    E-Print Network [OSTI]

    Brummans, Boris H. J. M.

    2005-02-17

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

  10. Organizational Evaluation and Authority 

    E-Print Network [OSTI]

    Scott, Richard W.; Dornbusch, Sanford M.; Busching, Bruce C.; Laing, James D.

    2015-07-21

    condition for internal pressures for change in the authority system--in short, for instability of the system. Both conception and theory are limited in scope to organizations which fulfill these conditions: 1) Organizational sanctions are distributed..., at least in part, on the basis of evaluations made of participants. 2) Evaluators who influence the distribution of organizational sanctions attempt to base their evaluations, at least in part, on the performance of organizational tasks by participants...

  11. 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.

  12. 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.

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

    SciTech Connect (OSTI)

    Marra, J

    2006-01-19

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

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

    SciTech Connect (OSTI)

    Marra, J

    2006-11-21

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

  15. 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.

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

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09

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

  18. On Ramsey Numbers

    E-Print Network [OSTI]

    Dhananjay P. Mehendale

    2006-05-24

    In this paper we define new numbers called the Neo-Ramsay numbers. We show that these numbers are in fact equal to the Ramsay numbers. Neo-Ramsey numbers are easy to compute and for finding them it is not necessary to check all possible graphs but enough to check only special kind of graphs having a well-defined adjacency pattern.

  19. Regulation Adopted by Vote of the Faculty of the Harvard Law School on May 12, 1959, with regard to Disposition of Third Year Written Work

    E-Print Network [OSTI]

    Wolfe, Patrick J.

    to Disposition of Third Year Written Work Papers The following regulation applies to papers, received submitted in satisfaction of the third year written work requirement, the written work requirements: _______________________________________________ Date:____________________ Year:____________________ #12;

  20. Logical Attestation: An Authorization Architecture

    E-Print Network [OSTI]

    Schneider, Fred B.

    , Credentials-Based Authorization 1. Introduction Secure coprocessors, such as industry standard Trusted

  1. 1 -Routing Number 2 -Account Number

    E-Print Network [OSTI]

    Chen, Yiling

    you will need: · Your Harvard University Id Number (HUID) · Your HUID pin number · Your Checking/Savings on the right side of the screen under Payroll and Compensation. #12;*Please, in an effort to save paper and if you do not wish to receive a paper copy of the check. Click the small box above the SAVE button. CLICK

  2. State authorization manual. Volume 1

    SciTech Connect (OSTI)

    Brugler-Jones, S.

    1990-10-01

    The State Authorization Manual (SAM) (Vol. I) provides guidance for States applying for program revisions to their authorized RCRA State program. The SAM is an updated version of the 1988 State Consolidated RCRA Authorization Manual (SCRAM). It focuses on program revision applications rather than initial applications since most States have received initial authorization for the RCRA program. The SCRAM should continue to be used to assist States not yet authorized under the RCRA program.

  3. Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials

    SciTech Connect (OSTI)

    NONE

    1995-03-29

    Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

  4. Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives

    SciTech Connect (OSTI)

    NONE

    1997-01-01

    This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-04-24

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

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

    SciTech Connect (OSTI)

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

    2007-02-12

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

  7. Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program

    SciTech Connect (OSTI)

    Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

    1997-12-01

    This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

  8. Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition

    SciTech Connect (OSTI)

    Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

    2001-06-01

    Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

  9. TRANSFER OF EXCESS NUCLEAR MATERIAL FROM LOS ALAMOS TO SAVANNAH RIVER SITE FOR LONG-TERM DISPOSITION

    SciTech Connect (OSTI)

    C. W. HOTH; L. A. FOSTER; T. F YARBRO

    2001-06-01

    Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

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

    SciTech Connect (OSTI)

    Duncan, A.

    2007-12-31

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

  11. 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.

  12. Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money

    SciTech Connect (OSTI)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-02-26

    The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude.

  13. Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze; Dr. Koji Shirai

    2012-07-01

    Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

  14. 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.

  15. SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 8 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

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

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D{sub (Cs)}) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  16. Shannon Capacity Ramsey Numbers

    E-Print Network [OSTI]

    Radziszowski, Stanislaw P.

    Shannon Capacity Ramsey Numbers Old links between Shannon and Ramsey New links between Shannon and Ramsey Bounds on Shannon Capacity and Ramsey Numbers from Product of Graphs Xiaodong Xu1 Stanislaw Institute of Technology, NY, USA March 2014 1/24 #12;Shannon Capacity Ramsey Numbers Old links between

  17. Integration of health physics, safety and operational processes for management and disposition of recycled uranium wastes at the Fernald Environmental Management Project (FEMP)

    SciTech Connect (OSTI)

    Barber, James; Buckley, James

    2003-02-23

    Fluor Fernald, Inc. (Fluor Fernald), the contractor for the U. S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP), recently submitted a new baseline plan for achieving site closure by the end of calendar year 2006. This plan was submitted at DOE's request, as the FEMP was selected as one of the sites for their accelerated closure initiative. In accordance with the accelerated baseline, the FEMP Waste Management Project (WMP) is actively evaluating innovative processes for the management and disposition of low-level uranium, fissile material, and thorium, all of which have been classified as waste. These activities are being conducted by the Low Level Waste (LLW) and Uranium Waste Disposition (UWD) projects. Alternatives associated with operational processing of individual waste streams, each of which poses potentially unique health physics, industrial hygiene and industrial hazards, are being evaluated for determination of the most cost effective and safe met hod for handling and disposition. Low-level Mixed Waste (LLMW) projects are not addressed in this paper. This paper summarizes historical uranium recycling programs and resultant trace quantity contamination of uranium waste streams with radionuclides, other than uranium. The presentation then describes how waste characterization data is reviewed for radiological and/or chemical hazards and exposure mitigation techniques, in conjunction with proposed operations for handling and disposition. The final part of the presentation consists of an overview of recent operations within LLW and UWD project dispositions, which have been safely completed, and a description of several current operations.

  18. THE UNIVERSITY OF TEXAS HEALTH SCIENCE CENTER AT SAN ANTONIO DIRECT DEPOSIT AUTHORIZATION FORM

    E-Print Network [OSTI]

    Nicholson, Bruce J.

    adopted or amended. If I am currently a UTHSC student, I understand that I am authorizing Student. Department: ____________________________Work Telephone Number: _________________ B. FINANCIAL INSTITUTION

  19. Multiple Sclerosis Journal The Author(s) 2013

    E-Print Network [OSTI]

    Gaser, Christian

    Multiple Sclerosis Journal 0(0) 1­8 © The Author(s) 2013 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav DOI: 10.1177/1352458513478673 msj.sagepub.com MULTIPLE SCLEROSIS MSJ JOURNAL Introduction (MRIs) are the most striking finding in multiple sclerosis (MS) and they have become the most important

  20. Predicting Job Salaries from Text Descriptions Anonymous Author(s)

    E-Print Network [OSTI]

    Freitas, Nando de

    050 051 052 053 Predicting Job Salaries from Text Descriptions Anonymous Author(s) Affiliation Address descriptions of the posted jobs. Many listings provide a salary, but as many as half do not. For those listings that do not provide a salary, it is useful to predict a salary based on the description of that job. We

  1. FAQ for Case Study Authors

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

    Reviews FAQ for Case Study Authors Science Engagement Move your data Programs & Workshops Science Requirements Reviews Network Requirements Reviews Documents and Background...

  2. Number Theory Seminar

    E-Print Network [OSTI]

    $author.value

    2014-12-03

    Dec 3, 2014 ... TBA, Rachel Davis ... September 26, Rachel Davis .... Dessins d'Enfants · Indiana Pi Bill · Notes and Publications · Number Theory Seminar ...

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

    SciTech Connect (OSTI)

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

    2013-08-08

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

  4. PROJECT STRATEGY FOR THE REMEDIATION AND DISPOSITION OF LEGACY TRANSURANIC WASTE AT THE SAVANNAH RIVER SITE, South Carolina, USA

    SciTech Connect (OSTI)

    Rodriguez, M.

    2010-12-17

    This paper discusses the Savannah River Site Accelerated Transuranic (TRU) Waste Project that was initiated in April of 2009 to accelerate the disposition of remaining legacy transuranic waste at the site. An overview of the project execution strategy that was implemented is discussed along with the lessons learned, challenges and improvements to date associated with waste characterization, facility modifications, startup planning, and remediation activities. The legacy waste was generated from approximately 1970 through 1990 and originated both on site as well as at multiple US Department of Energy sites. Approximately two thirds of the waste was previously dispositioned from 2006 to 2008, with the remaining one third being the more hazardous waste due to its activity (curie content) and the plutonium isotope Pu-238 quantities in the waste. The project strategy is a phased approach beginning with the lower activity waste in existing facilities while upgrades are made to support remediation of the higher activity waste. Five waste remediation process lines will be used to support the full remediation efforts which involve receipt of the legacy waste container, removal of prohibited items, venting of containers, and resizing of contents to fit into current approved waste shipping containers. Modifications have been minimized to the extent possible to meet the accelerated goals and involve limited upgrades to address life safety requirements, radiological containment needs, and handling equipment for the larger waste containers. Upgrades are also in progress for implementation of the TRUPACT III for the shipment of Standard Large Boxes to the Waste Isolation Pilot Plant, the US TRU waste repository. The use of this larger shipping container is necessary for approximately 20% of the waste by volume due to limited size reduction capability. To date, approximately 25% of the waste has been dispositioned, and several improvements have been made to the overall processing plan as well as facility processing rates. These lessons learned, challenges, and improvements will be discussed to aid other sites in their efforts to conduct similar activities.

  5. Author's personal copy Cosmogenic 7

    E-Print Network [OSTI]

    Usoskin, Ilya G.

    Author's personal copy Cosmogenic 7 Be and 22 Na in Finland: Production, observed periodicities a Radiation and Nuclear Safety Authority, Regional Laboratory in Northern Finland, Rovaniemi, Finland b Sodankyl¨a Geophysical Observatory, Oulu Unit, University of Oulu, Finland c Ioffe Physical

  6. Waste Management Coordinating Lead Authors

    E-Print Network [OSTI]

    Columbia University

    10 Waste Management Coordinating Lead Authors: Jean Bogner (USA) Lead Authors: Mohammed Abdelrafie Ahmed, C. Diaz, A. Faaij, Q. Gao, S. Hashimoto, K. Mareckova, R. Pipatti, T. Zhang, Waste Management University Press, Cambridge, United Kingdom and New York, NY, USA. #12;586 Waste Management Chapter 10 Table

  7. Authority and Review Chart Exhibit A R = REVIEW A = AUTHORITY

    E-Print Network [OSTI]

    Zhou, Yuanyuan

    Authority and Review Chart Exhibit A R = REVIEW A = AUTHORITY ¹ OFF-SCALE NOT HANDLED PER POLICY Chancellor Academic Affairs ASST PROF (LRF, In Residence, Clinical X) Appointment R R R³ R R R R R4 R A Merit/ Reappointment A A³ R A R A Merit with off-scale salary increase R R³ R R R R R A Merit with 6th Year Market os

  8. AUTHORITY

    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 p a l De p u t y A s sconveyance of9,Septemeber 19, 2014

  9. Big Numbers | Jefferson Lab

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

    with a length of 35 cm, which certainly helps . With Avogadro's number and the density of liquid hydrogen, we have about 1024 protons per cm2. We then take the beam of 160...

  10. KPA Activity Number

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

    September 2002 Page 1 KPA Activity Number KPA Activity SEM Section SME Work Product SQSE Web Site http:cio.doe.govsqse REQUIREMENTS MANAGEMENT RM-1 The software engineering...

  11. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    SciTech Connect (OSTI)

    Shropshire, D.E.; Herring, J.S.

    2004-10-03

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim storage, packaging, transportation, waste forms, waste treatment, decontamination and decommissioning issues; and low-level waste (LLW) and high-level waste (HLW) disposal.

  12. Disposition of smoked cannabis with high {Delta}{sup 9}-tetrahydrocannabinol content: A kinetic model

    SciTech Connect (OSTI)

    Hunault, Claudine C., E-mail: claudine.hunault@rivm.n [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Eijkeren, Jan C.H. van [Expertise Center for Methodology and Information Services, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Mensinga, Tjeert T. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Clinic for treatment of drug addiction in Northern, Vondellaan 71-73, 9721 LB, Groningen (Netherlands); Vries, Irma de [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Leenders, Marianne E.C. [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division of Perioperative and Emergency Care, University Medical Center Utrecht, 3584 CX (Netherlands); Meulenbelt, Jan [National Poisons Information Center, National Institute for Public Health and the Environment, Bilthoven (Netherlands); Division Intensive Care Center, University Medical Center Utrecht, 3584 CX, Utrecht (Netherlands); Institute for Risk Assessment Sciences, Utrecht University, Utrecht (Netherlands)

    2010-08-01

    Introduction: No model exists to describe the disposition and kinetics of inhaled cannabis containing a high THC dose. We aimed to develop a kinetic model providing estimates of the THC serum concentrations after smoking cannabis cigarettes containing high THC doses (up to 69 mg THC). Methods: Twenty-four male non-daily cannabis users smoked cannabis cigarettes containing 29.3 mg, 49.1 mg, and 69.4 mg THC. Blood samples were collected over a period of 0-8 h and serum THC concentrations were measured. A two-compartment open model was fitted on the individual observed data. Results: Large inter-individual variability was observed in the pharmacokinetic parameters. The median pharmacokinetic parameters generated by the model were C{sub max} = 175 ng/mL, T{sub max} = 14 min, and AUC{sub 0-8h} = 8150 ng x min/mL for the 69.4 mg THC dose. Median model results show an almost linear dose response relation for C{sub max}/Dose = 2.8 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 136 x 10{sup -6} min/mL. However, for increasing dose level, there was a clear decreasing trend: C{sub max}/Dose = 3.4, 2.6 and 2.5 x 10{sup -6}/mL and AUC{sub 0-8h}/Dose = 157, 133 and 117 x 10{sup -6} min/mL for the 29.3, 49.1 and 69.4 mg dose, respectively. Within the restriction of 8 h of observation, the apparent terminal half life of THC was 150 min. Conclusion: The model offers insight into the pharmacokinetics of THC in recreational cannabis users smoking cannabis containing high doses of THC mixed with tobacco. The model is an objective method for providing serum THC concentrations up to 8 h after smoking cannabis with a high THC content (up to 23%).

  13. Collaborative Authoring of Walden's Paths 

    E-Print Network [OSTI]

    Li, Yuanling

    2012-10-19

    The World Wide Web contains rich collections of digital materials that can be used in education and learning settings. The collaborative authoring prototype of Walden's Paths targets two groups of users: educators and ...

  14. Author Order and Research Quality

    E-Print Network [OSTI]

    Kissan, Joseph; Laband, David N.; Patil, Vivek

    2005-01-01

    We observe a great deal of heterogeneity in the manner in which author orderings are assigned both across and within academic markets. To better understand this phenomenon, we develop and analyze a stochastic model of ...

  15. Danish Energy Authority Final report

    E-Print Network [OSTI]

    1 Danish Energy Authority Final report Kaliningrad Regional District Heating Network 2004 - 2006 2006 #12;Kaliningrad District Heating Network Project 2004 - 2006 2 Table of content The report........................................................................................................... 7 1.4.1 District heating in the Region

  16. Retrofitting the Tennessee Valley Authority

    E-Print Network [OSTI]

    Zeiber, Kristen (Kristen Ann)

    2013-01-01

    As the flagship of the New Deal, the Tennessee Valley Authority (TVA) was a triumph of regional and environmental design that has since fallen on hard times. When writer James Agee toured the region in 1935, he described ...

  17. POLICY NUMBER 2006-18 April 10, 2012

    E-Print Network [OSTI]

    Oliver, Douglas L.

    1/ 2 POLICY NUMBER 2006-18 April 10, 2012 POLICY: AUTHORITY TO PURCHASE AND CONTRACT PURPOSE: This policy addresses the University of Connecticut Health Center's purchasing and contracting authority. SCOPE: All University of Connecticut Health Center ("UCHC") faculty and staff. POLICY STATEMENT: UCHC

  18. POLICY NUMBER 2012-04 April 10, 2012

    E-Print Network [OSTI]

    Oliver, Douglas L.

    POLICY NUMBER 2012-04 April 10, 2012 POLICY: CONTRACT SIGNATURE AUTHORITY PURPOSE: This policy UCHC employees, suppliers and contractors. POLICY STATEMENT: Only authorized UCHC personnel may sign contracts on behalf of UCHC. For the purpose of this Policy, a "contract" is defined as a written agreement

  19. Report number codes

    SciTech Connect (OSTI)

    Nelson, R.N.

    1985-05-01

    This publication lists all report number codes processed by the Office of Scientific and Technical Information. The report codes are substantially based on the American National Standards Institute, Standard Technical Report Number (STRN)-Format and Creation Z39.23-1983. The Standard Technical Report Number (STRN) provides one of the primary methods of identifying a specific technical report. The STRN consists of two parts: The report code and the sequential number. The report code identifies the issuing organization, a specific program, or a type of document. The sequential number, which is assigned in sequence by each report issuing entity, is not included in this publication. Part I of this compilation is alphabetized by report codes followed by issuing installations. Part II lists the issuing organization followed by the assigned report code(s). In both Parts I and II, the names of issuing organizations appear for the most part in the form used at the time the reports were issued. However, for some of the more prolific installations which have had name changes, all entries have been merged under the current name.

  20. UCGE Reports Number 20284

    E-Print Network [OSTI]

    Calgary, University of

    ABSTRACT Oil and gas are global fuels obtained primarily from drilling wells in underground terrestrial reservoirs. Vertical drilling is preferred because of its simplicity and therefore low cost, but subsurfaceUCGE Reports Number 20284 Department of Geomatics Engineering Continuous Measurement-While-Drilling

  1. Student Code Number: Thermodynamics

    E-Print Network [OSTI]

    Feeny, Brian

    Student Code Number: Thermodynamics Ph.D. Qualifying Exam Department of Mechanical Engineering;Thermodynamics Qualifier January 2013 Problem 1 Air is compressed in an axial-flow compressor operating at steady of exergy destruction within the compressor, in kJ per kg of air flowing. #12;Thermodynamics Qualifier

  2. UCGE Reports Number 20146

    E-Print Network [OSTI]

    Calgary, University of

    in considerable operational cost savings for many exploration and open-pit mining companies in the energy sectorUCGE Reports Number 20146 Department of Geomatics Engineering Development of a Mobile Equipment Equipment Management System solution. In the open-pit mining industries there is a need for these companies

  3. Australia NO REGISTRATION NUMBER

    E-Print Network [OSTI]

    Portugal Romania Slovenia Spain Turkey UK USA Australia Austria Belgium Cyprus France Germany Greece#12;#12;Australia Austria Belgium Cyprus France Germany Greece Ireland Italy Japan Macedonia Ireland Italy Japan Macedonia Portugal Romania Slovenia Spain Turkey UK USA #12;NO REGISTRATION NUMBER 1

  4. Interference Mitigation in Femtocell Network Using Anonymous Author(s)

    E-Print Network [OSTI]

    Freitas, Nando de

    the power adaptation process of the FUEs and MUE to be a discrete multi agent Markov decision problem 050 051 052 053 Interference Mitigation in Femtocell Network Using Q-learning Anonymous Author problems is the so-called co-tier and cross-tier interference caused by the new femtocell network layer

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

    SciTech Connect (OSTI)

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

    2009-03-01

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

  6. Criminal History Check Disclosure Notice and Release Authorization

    E-Print Network [OSTI]

    Escher, Christine

    background information may include, but are not limited to: address history; criminal records and historyCriminal History Check Disclosure Notice and Release Authorization *Please attach a copy of your% for National criminal history checks. Hiring Department Index Number: __________________ Activity Code

  7. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

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

    2013-09-19

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  8. Final Environmental Assessment and Finding of No Significant Impact: Waste Disposition Activities at the Paducah Site Paducah, Kentucky

    SciTech Connect (OSTI)

    N /A

    2002-11-05

    The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment with in the context of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement is not necessary, and DOE is issuing this Finding of No Significant Impact (FONSI).

  9. n errla lona Guest Author -

    E-Print Network [OSTI]

    F R p · Fiber Remforced Plastics n errla lona·········· Guest Author - Dr. Aftab Mufti. P-Stengthening Using Prestressed Carbon Fiber Sheets In recent years, researthers at EMfA Duhendorl, Switzerland, have been working extensively on ~.I ,trengtllening reinforced concrete member.; u,mg lillht· weight carbon

  10. Designated Responsible Authority (DRA) Training

    E-Print Network [OSTI]

    Minnesota, University of

    · The role of Designated Responsible Authority (DRA) is defined in the Using Vehicles for University Business policy. · The head of each University department with permanently assigned vehicles must appoint. Be familiar with the policies and related documents governing the use of University vehicles, and direct

  11. JOURNAL AUTHORS SURVEY Prepared by

    E-Print Network [OSTI]

    Stevenson, Paul

    JISC/OSI JOURNAL AUTHORS SURVEY Report Prepared by Key Perspectives Ltd 48 Old Coach Road, Playing behind its development 4 2.2 Models and definitions of open access 8 2.2.1 Open access journals 8 2 4.1 Respondent profiles 18 4.2 Awareness of open access journals 18 4.2.1 Extent and longevity

  12. Danish Energy Authority Project Document

    E-Print Network [OSTI]

    for larger existing buildings subject to major renovation 4. Energy performance certification (energyDanish Energy Authority Project Document Implementation of the EU directive on the energy performance of buildings: Development of the Latvian Scheme for energy auditing of buildings and inspection

  13. Danish Energy Authority Final Report

    E-Print Network [OSTI]

    on the energy performance for larger existing buildings subject to major renovation 4. Energy performanceDanish Energy Authority Final Report Implementation of the EU directive on the energy performance of buildings: Development of the Latvian Scheme for energy auditing of buildings and inspection of boilers

  14. With Compliments of the Author

    E-Print Network [OSTI]

    Zhang, Meirong

    Operators and Matrices With Compliments of the Author OaM-08-50 889­899 Zagreb, Croatia Volume 8, Croatia. All correspondence and subscription orders should be addressed to the Editorial Office: www, Croatia Fax: +385 1 6008799 The content of this publication is indexed in Mathematical Reviews (Math

  15. Quantum random number generator

    E-Print Network [OSTI]

    M. Stipcevic; B. Medved Rogina

    2007-01-01

    We report upon a novel principle for realization of a fast nondeterministic random number generator whose randomness relies on intrinsic randomness of the quantum physical processes of photonic emission in semiconductors and subsequent detection by the photoelectric effect. Timing information of detected photons is used to generate binary random digits-bits. The bit extraction method based on restartable clock theoretically eliminates both bias and autocorrelation while reaching efficiency of almost 0.5 bits per random event. A prototype has been built and statistically tested.

  16. Neither Name, Nor Number

    E-Print Network [OSTI]

    Federico Holik

    2011-12-20

    Since its origins, Quantum mechanics has presented problems with the concept of individuality. It is argued that quantum particles do not have individuality, and so, one can speak about "entities without identity". On the contrary, we claim that the problem of quantum non individuality goes deeper, and that one of its most important features is the fact that there are quantum systems for which particle number is not well defined. In this work, we continue this discussion in relation to the problem about the one and the many.

  17. Dispositional Mindfulness and Self-Compassion and their influence on Oxytocin and Parasympathetic Functioning

    E-Print Network [OSTI]

    Bowlin, Stephanie Lynne

    2012-12-31

    ) that predicted cortisol and affective responses (Brown, Weinstein, & Creswell, 2012). Vest Rogers (2009) did not find any effects on trait mindfulness in relation to HF HRV during a sad film clip known to elicit negative emotion. However, the authors noted..., Dubois-Dauphin, Widmer, & Raggenbass, 1992; Gamer & Büchel, 2012; Grippo, Trahanas, Zimmerman, Porges, & Carter, 2009; Uvnas-Moberg, 1997). Recently, intranasal administration of OT was found to produce significant increases in HF HRV (Norman et al., 2011...

  18. Central Characterization Program (CCP) Transuranic Authorized...

    Office of Environmental Management (EM)

    Authorized Methods for Payload Control Central Characterization Program (CCP) Transuranic Authorized Methods for Payload Control This document was used to determine facts and...

  19. Energy Department Authorizes Corpus Christi Liquefaction Project...

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

    Authorizes Corpus Christi Liquefaction Project to Export Liquefied Natural Gas Energy Department Authorizes Corpus Christi Liquefaction Project to Export Liquefied Natural Gas May...

  20. Peoria Tribe: Housing Authority- 2010 Project

    Broader source: Energy.gov [DOE]

    The Housing Authority of the Peoria Tribe of Indians of Oklahoma (Peoria Housing Authority or PHA) will conduct the "PHA Weatherization Training Project."

  1. Obama Administration Announces Billions in Lending Authority...

    Energy Savers [EERE]

    Billions in Lending Authority for Renewable Energy Projects and to Modernize the Grid Obama Administration Announces Billions in Lending Authority for Renewable Energy Projects and...

  2. On Some Zarankiewicz Numbers and Bipartite Ramsey Numbers for

    E-Print Network [OSTI]

    Radziszowski, Stanislaw P.

    On Some Zarankiewicz Numbers and Bipartite Ramsey Numbers for Quadrilateral Janusz Dybizba Ramsey number b(n1, · · · , nk) is the least positive integer b such that any coloring of the edges of Kb Ramsey numbers avoiding quadrilateral. In particular, we prove that b4(2) = 19, and establish new general

  3. COALITION PROVISIONAL AUTHORITY ORDER NUMBER 17 STATUS OF THE COALITION, FOREIGN LIAISON MISSIONS, THEIR

    E-Print Network [OSTI]

    US Army Corps of Engineers

    and development of Iraq, Noting that states are sending Foreign Liaison Mission Personnel to Iraq, Conscious State" means the state providing Coalition Personnel as part of the Coalition in Iraq or the state or individuals not normally resident in Iraq supplying goods and/or services to or on behalf of the Coalition

  4. EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany

    Broader source: Energy.gov [DOE]

    This environmental assessment (EA) will evaluate the potential environmental impacts of a DOE proposal to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition. This used nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear reactors used for research and development purposes.

  5. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    SciTech Connect (OSTI)

    Bunch, Kyle J. [United States Department of State, Bureau of Arms Control, Verification and Compliance, Office of Verification and Transparency Technologies, Washington, DC (United States); Jones, Anthony M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Benz, Jacob M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Denlinger, Laura Schmidt [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

    2014-05-04

    The ratification and ongoing implementation of the New START Treaty have been widely regarded as noteworthy global security achievements for both the Obama Administration and the Putin (formerly Medvedev) regime. But deeper cuts that move beyond the United States and Russia to engage the P-5 and other nuclear weapons possessor states are envisioned under future arms control regimes, and are indeed required for the P-5 in accordance with their Article VI disarmament obligations in the Nuclear Non-Proliferation Treaty. Future verification needs will include monitoring the cessation of production of new fissile material for weapons, monitoring storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondary stages, and other materials. A fundamental challenge to implementing a nuclear disarmament regime is the ability to thwart unauthorized material diversion throughout the dismantlement and disposition process through strong chain of custody implementation. Verifying the declared presence, or absence, of nuclear materials and weapons components throughout the dismantlement and disposition lifecycle is a critical aspect of the disarmament process. From both the diplomatic and technical perspectives, verification under these future arms control regimes will require new solutions. Since any acceptable verification technology must protect sensitive design information and attributes to prevent the release of classified or other proliferation-sensitive information, non-nuclear non-sensitive modalities may provide significant new verification tools which do not require the use of additional information barriers. Alternative verification technologies based upon electromagnetic and acoustics could potentially play an important role in fulfilling the challenging requirements of future verification regimes. For example, researchers at the Pacific Northwest National Laboratory (PNNL) have demonstrated that low frequency electromagnetic signatures of sealed metallic containers can be used to rapidly confirm the presence of specific components on a yes/no basis without revealing classified information. PNNL researchers have also used ultrasonic measurements to obtain images of material microstructures which may be used as templates or unique identifiers of treaty-limited items. Such alternative technologies are suitable for application in various stages of weapons dismantlement and often include the advantage of an inherent information barrier due to the inability to extract classified weapon design information from the collected data. As a result, these types of technologies complement radiation-based verification methods for arms control. This article presents an overview of several alternative verification technologies that are suitable for supporting a future, broader and more intrusive arms control regime that spans the nuclear weapons disarmament lifecycle. The general capabilities and limitations of each verification modality are discussed and example technologies are presented. Potential applications are defined in the context of the nuclear material and weapons lifecycle. Example applications range from authentication (e.g., tracking and signatures within the chain of custody from downloading through weapons storage, unclassified templates and unique identification) to verification of absence and final material disposition.

  6. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  7. The Distribution of Ramsey Numbers

    E-Print Network [OSTI]

    Lane Clark; Frank Gaitan

    2014-11-10

    We prove that the number of integers in the interval [0,x] that are non-trivial Ramsey numbers r(k,n) (3 <= k <= n) has order of magnitude (x ln x)**(1/2).

  8. Ordered Ramsey numbers David Conlon

    E-Print Network [OSTI]

    Fox, Jacob

    Ordered Ramsey numbers David Conlon Jacob Fox Choongbum Lee Benny Sudakov§ Abstract Given a labeled graph H with vertex set {1, 2, . . . , n}, the ordered Ramsey number r with vertices appearing in the same order as in H. The ordered Ramsey number of a labeled graph H is at least

  9. Hypergraph Ramsey numbers David Conlon

    E-Print Network [OSTI]

    Fox, Jacob

    Hypergraph Ramsey numbers David Conlon Jacob Fox Benny Sudakov Abstract The Ramsey number rk(s, n). In this paper we obtain new estimates for several basic hypergraph Ramsey problems. We give a new upper bound-color Ramsey number r3(n, n, n), which is the minimum N such that every 3-coloring of the triples

  10. Data Compression with Prime Numbers

    E-Print Network [OSTI]

    Gordon Chalmers

    2005-11-16

    A compression algorithm is presented that uses the set of prime numbers. Sequences of numbers are correlated with the prime numbers, and labeled with the integers. The algorithm can be iterated on data sets, generating factors of doubles on the compression.

  11. Collaboration and Commitment to Sealed Source Safety, Security, and Disposition - 13627

    SciTech Connect (OSTI)

    Jennison, Meaghan [National Nuclear Security Administration, Washington, DC (United States)] [National Nuclear Security Administration, Washington, DC (United States); Martin, David W. [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States)] [National Nuclear Security Administration/Energetics Inc., Washington, DC (United States)

    2013-07-01

    EnergySolutions, the Division of Radiation Control at the Utah Department of Environmental Quality (UDEQ), the Conference of Radiation Control Program Directors (CRCPD), and the Department of Energy's Global Threat Reduction Initiative (GTRI) are collaborating on a truly innovative effort to expand opportunities for cost-effective sealed source disposal. These entities have developed a first-of-its-kind initiative to dispose of certain sealed sources at the EnergySolutions disposal facility near Clive, Utah, which normally cannot accept sealed sources of any type. This creative and collaborative effort to improve radiation health, safety, and security exemplifies the spirit and commitment represented by the Richard S. Hodes, M.D. Honor Lecture Award, which is presented annually at the Waste Management Symposia by the Southeast Compact Commission to encourage environmental professionals and political leaders to develop innovative approaches to waste management in the United States. The participants in the collaborative initiative are honored to receive special recognition for their efforts thus far. They also recognize that the hard work remains to be done. (authors)

  12. A Comprehensive Solution for Managing TRU and LLW From Generation to Final Disposition - 13205

    SciTech Connect (OSTI)

    Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M.

    2013-07-01

    A LANL multi-disciplinary team faced the challenge of building and delivering a waste information system capable of managing radioactive, hazardous, and industrial waste from cradle to grave. The result is the Waste Compliance and Tracking System (WCATS) a flexible, adaptive system that has allowed LANL to consolidate its legacy applications into one system, and leverage the advantages of managing all waste types within a single scalable enterprise application. Key functionality required for robust waste operations, include: waste characterization, waste identification, transportation, inventory management, waste processing, and disposal. In order to maintain data quality, field operations such as waste identification, surveillance checklists, wall-to-wall inventory assessments, waste transfers, shipment pickup and receipt, and simple consolidation operations are captured by the operator or technician using mobile computers. Work flow is managed via end-user defined work paths, to ensure that unit operations are performed in the correct order. Regulatory compliance reports and algorithms are provided to support typical U.S. EPA, DOT, NRC, and DOE requirements, including the EPA hazardous waste manifest, NRC LLW manifest, DOE nuclear material at risk, RCRA TSDF inventory rules, and so forth. The WCATS application has allowed LANL to migrate and consolidate its disparate legacy applications. The design and implementation is generalized so that facility owners can customize the user interface, setup facilities and unit operations (i.e., treatment, storage, disposal, characterization, and administrative), define inventory compliance rules, and establish custom work flow requirements. (authors)

  13. Disposition of transuranic residues from plutonium isentropic compression experiment (Pu-ICE) constucted at Z machine

    SciTech Connect (OSTI)

    Goyal, Kapil K [Los Alamos National Laboratory; French, David M [Los Alamos National Laboratory; Humphrey, Betty J [WESTON SOLUTIONS INC.; Gluth, Jeffry [SNL

    2010-01-01

    In 1992, the U.S. Congress passed legislation to discontinue above- and below-ground testing of nuclear weapons. Because of this, the U.S. Department of Energy (DOE) must rely on laboratory experiments and computer-based calculations to verify the reliability of the nuclear stockpile. The Sandia National Laboratories/New Mexico (SNL/NM) Z machine was developed to support the science-based approach for mimicking nuclear explosions and stockpile stewardship. Plutonium (Pu) isotopes with greater than ninety-eight percent enrichment were used in the experiments. In May 2006, SNL/NM received authority that the Z Machine Isentropic Compression Experiments could commence. Los Alamos National Laboratory (LANL) provided the plutonium targets and loaded the target assemblies provided by SNL/NM. Three experiments were conducted from May through July 2006. The residues from each experiment, which weighed up to 913 pounds, were metallic and were packaged into a 55-gallon drum each. SNL/NM conducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste certification for disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a comprehensive approach for documenting generator knowledge for characterization of waste in cooperation with scientists at the two laboratories and addresses a variety of essential topics.

  14. Flexible Visual Authoring Using Operation History

    E-Print Network [OSTI]

    Su, Sara

    Flexible Visual Authoring Using Operation History Sara Su Massachusetts Institute of Technology l Revisiting history Storing and retrieving state Hierarchical authoring Grouping, structure, selections #12;Operations and selections today Uses of history System activity logs, instrumentation (not our focus

  15. GM-Ford-Chrysler: Allocating Loan Authority

    Broader source: Energy.gov [DOE]

    Statement from GM, Ford, and Chrysler: "Allocating the $25 Billion in Direct Loan Authority to Loan Applicants"

  16. State authorization manual. Volume 2. Appendices

    SciTech Connect (OSTI)

    Brugler-Jones, S.

    1990-10-01

    The document provides the supportive appendices for Volume 1 of the State Authorization Manual (SAM), which provides guidance for States applying for program revisions to their authorized RCRA State program. Among the appendices are: various program checklists, lists of revision checklists by cluster, model Federal Register Notices, guidance for State Authorization Files, and guidance for using Wordperfect files and for CFR files.

  17. NUMBER: IT 1.06 SECTION: Information Technology

    E-Print Network [OSTI]

    Morgan, Stephen L.

    1 NUMBER: IT 1.06 SECTION: Information Technology SUBJECT: Acceptable Use of Information Technology Authorized by: William F. Hogue Issued by: Office of Information Technology I. Policy All users of University information technology resources must adhere to applicable state and federal laws, statutes, and regulations

  18. USF System USF USFSP USFSM Number: 6-021

    E-Print Network [OSTI]

    Meyers, Steven D.

    Agreement iv. Preparation of the Capital Improvement Plan B. Authority Campus Master Plans are requiredPOLICY USF System USF USFSP USFSM Number: 6-021 Subject: Campus Master Planning Program Responsible-2-15 _____________________________________________________________________________________________ I. PURPOSE & INTENT The purpose and intent of the USF System Campus Master Planning Program

  19. POLICY NUMBER 2003-05 POLICY: HIPAA MARKETING COMPLIANCE

    E-Print Network [OSTI]

    Kim, Duck O.

    POLICY NUMBER 2003-05 May 19th , 2015 POLICY: HIPAA MARKETING COMPLIANCE (PRIVACY & SECURITY of marketing and when written patient authorization is required. SCOPE: Applies to all UConn Health workforce and contracted staff Credentialed staff Members of the Board of Directors DEFINITIONS: Marketing - means

  20. USF System USF USFSP USFSM Number: 5-014

    E-Print Network [OSTI]

    Meyers, Steven D.

    POLICY USF System USF USFSP USFSM Number: 5-014 Subject: Asset/Property Management Responsible, excluding real property. II. STATEMENT OF POLICY A. Asset Management Services is delegated the authority, fabrication or gift, which is practicable to identify by marking will be visibly marked by Asset Management

  1. NUMBER: BUSF 6.00 SECTION: Business and Finance

    E-Print Network [OSTI]

    Almor, Amit

    NUMBER: BUSF 6.00 SECTION: Business and Finance SUBJECT: Payroll Authorizations DATE: November 1 The language used in the Business and Finance policies does not create an employment contract between of the Business and Finance policies, in whole or in part, with or without notice. In all cases, the Business

  2. NUMBER: BUSF 8.01 SECTION: Business and Finance

    E-Print Network [OSTI]

    Almor, Amit

    NUMBER: BUSF 8.01 SECTION: Business and Finance SUBJECT: Payroll Authorizations DATE: December 4 The language used in the Business and Finance policies does not create an employment contract between of the Business and Finance policies, in whole or in part, with or without notice. In all cases, the Business

  3. NUMBER: BUSF 6.09 SECTION: Business and Finance

    E-Print Network [OSTI]

    Almor, Amit

    NUMBER: BUSF 6.09 SECTION: Business and Finance SUBJECT: Distribution of Payroll Statements Campuses Authorized by: Rick Kelly Issued by: Payroll The language used in the Business and Finance. The University reserves the right to revise the content of the Business and Finance policies, in whole or in part

  4. POLICY NUMBER 2009-03 October 16, 2009

    E-Print Network [OSTI]

    administration, research funding or those officials in any other type of position with authority, direct to all types of research at UCHC, one essential goal is to protect the rights and safety of humanPOLICY NUMBER 2009-03 October 16, 2009 POLICY: Institutional Conflicts of Interest in Research

  5. Los Alamos science, Number 14

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    Nine authored articles are included covering: natural heat engine, photoconductivity, the Caribbean Basin, energy in Central America, peat, geothermal energy, and the MANIAC computer. Separate abstracts were prepared for the articles. (DLC)

  6. Disposal R&D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration

    SciTech Connect (OSTI)

    Birkholzer, J.T.

    2011-06-01

    For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

  7. Disposition of transuranic residues from plutonium isentropic compression experiment (Pu-ice) conducted at Z machine

    SciTech Connect (OSTI)

    Goyal, Kapil K [Los Alamos National Laboratory; French, David M [Los Alamos National Laboratory; Humphrey, Betty J [WESTON SOLUTIONS INC.; Gluth, Jeffry [SNL

    2010-01-01

    In 1992, the U.S. Congress passed legislation to discontinue above- and below-ground testing of nuclear weapons. Because of this, the U.S. Department of Energy (DOE) must rely on laboratory experiments and computer-based calculations to verify the reliability of the nation's nuclear stockpile. The Sandia National Laboratories/New Mexico (SNL/NM) Z machine was developed by the DOE to support its science-based approach to stockpile stewardship. SNL/NM researchers also use the Z machine to test radiation effects on various materials in experiments designed to mimic nuclear explosions. Numerous components, parts, and materials have been tested. These experiments use a variety of radionuclides; however, plutonium (Pu) isotopes with greater than ninety-eight percent enrichment are the primary radionuclides used in the experiments designed for stockpile stewardship. In May 2006, SNL/NM received authority that the Z Machine Isentropic Compression Experiments could commence. Los Alamos National Laboratory (LANL) provided the plutonium targets and loaded the target assemblies, which were fabricated by SNL/NM. LANL shipped the loaded assemblies to SNL/NM for Z machine experiments. Three experiments were conducted from May through July 2006. The residues from each experiment, which weighed up to 913 pounds, were metallic and packaged into a respective 55-gallon drum each. Based on a memorandum of understanding between the two laboratories, LANL provides the plutonium samples and the respective radio-isotopic information. SNL/NM conducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste certification for disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a comprehensive approach for documenting generator knowledge for characterization of waste in cooperation with scientists at the two laboratories and addresses a variety of topics such as material control and accountability, safeguards of material, termination of safeguards for eventual shipment from SNL/NM to LANL, associated approvals from DOE-Carlsbad Field Office, which governs WIPP and various notifications. It portrays a comprehensive approach needed for successful completion of a complex project between two national laboratories.

  8. Compendium of Experimental Cetane Numbers

    SciTech Connect (OSTI)

    Yanowitz, J.; Ratcliff, M. A.; McCormick, R. L.; Taylor, J. D.; Murphy, M. J.

    2014-08-01

    This report is an updated version of the 2004 Compendium of Experimental Cetane Number Data and presents a compilation of measured cetane numbers for pure chemical compounds. It includes all available single compound cetane number data found in the scientific literature up until March 2014 as well as a number of unpublished values, most measured over the past decade at the National Renewable Energy Laboratory. This Compendium contains cetane values for 389 pure compounds, including 189 hydrocarbons and 201 oxygenates. More than 250 individual measurements are new to this version of the Compendium. For many compounds, numerous measurements are included, often collected by different researchers using different methods. Cetane number is a relative ranking of a fuel's autoignition characteristics for use in compression ignition engines; it is based on the amount of time between fuel injection and ignition, also known as ignition delay. The cetane number is typically measured either in a single-cylinder engine or a constant volume combustion chamber. Values in the previous Compendium derived from octane numbers have been removed, and replaced with a brief analysis of the correlation between cetane numbers and octane numbers. The discussion on the accuracy and precision of the most commonly used methods for measuring cetane has been expanded and the data has been annotated extensively to provide additional information that will help the reader judge the relative reliability of individual results.

  9. 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.

  10. Number

    Office of Legacy Management (LM)

    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 Gas &SCE-SessionsSouthReport for the Weldon Spring,7=cr5rnP 7694 i+lJNew York,' , /v-i 2

  11. Standing Delegations of Authority as at 1 December 2014 1 STANDING DELEGATIONS OF AUTHORITY

    E-Print Network [OSTI]

    University of Technology, Sydney

    Standing Delegations of Authority as at 1 December 2014 1 STANDING DELEGATIONS OF AUTHORITY 1 the Delegation Principles outlined on pages 5 and 6. Any questions about the interpretation of the Standing Delegations of Authority, suggestions for amendment of the Standing Delegations of Authority and requests

  12. Pipeline MT Instructions Identification Number

    E-Print Network [OSTI]

    Hong, Don

    Pipeline MT Instructions Identification Number For identification purposes, you will be assigned a special identification number. M# You can activate your MT email, login to PipelineMT to register for classes or pay tuition and fees. Activating the MTSU Email and PipelineMT accounts: Visit the website

  13. National Training and Education Resource Advanced Authoring Training

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

    Advanced Authoring Training Participant Guide NTER Advanced Authoring Training Participant Guide (032012 pw) 2 Contents OBJECTIVES ......

  14. USF System USF USFSP USFSM Number: USF12.003

    E-Print Network [OSTI]

    Meyers, Steven D.

    this regulation: (a) A "work" includes any copyrightable material such as printed material, computer software, computer programs, computer assisted instructional coursework, programmed instructional materials, three is the property of the employee, who has the right to determine the disposition of such work and the revenue

  15. Types of random numbers and Monte Carlo Methods Pseudorandom number generation

    E-Print Network [OSTI]

    Mascagni, Michael

    Types of random numbers and Monte Carlo Methods Pseudorandom number generation Quasirandom number generation Conclusions WE246: Random Number Generation A Practitioner's Overview Prof. Michael Mascagni #12;Types of random numbers and Monte Carlo Methods Pseudorandom number generation Quasirandom number

  16. Montana Water Quality Permit Application, Nondegradation Authorization...

    Open Energy Info (EERE)

    Montana Water Quality Permit Application, Nondegradation Authorization, and Permit Fees Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory...

  17. Authorization basis for the 209-E Building

    SciTech Connect (OSTI)

    TIFFANY, M.S.

    1999-02-23

    This Authorization Basis document is one of three documents that constitute the Authorization Basis for the 209-E Building. Per the U.S. Department of Energy, Richland Operations Office (RL) letter 98-WSD-074, this document, the 209-E Building Preliminary Hazards Analysis (WHC-SD-WM-TI-789), and the 209-E Building Safety Evaluation Report (97-WSD-074) constitute the Authorization Basis for the 209-E Building. This Authorization Basis and the associated controls and safety programs will remain in place until safety documentation addressing deactivation of the 209-E Building is developed by the contractor and approved by RL.

  18. Oregon Underground Injection Control Program Authorized Injection...

    Open Energy Info (EERE)

    Systems Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Oregon Underground Injection Control Program Authorized Injection Systems Webpage...

  19. Coordination of Federal Authorizations for Electric Transmission...

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

    rulemaking and opportunity for comment on the coordination of federal authorizations for electric transmission facilities, September 19, 2008 Coordination of Federal...

  20. Disposal Authorization Statement | Department of Energy

    Office of Environmental Management (EM)

    DAS requirements ensure the facility does not pose a threat to human health and the environment, defines the authorization for the design, construction, operation,...

  1. Stockroom Authorization Department of Chemistry & Biochemistry

    E-Print Network [OSTI]

    Morgan, Stephen L.

    Stockroom Authorization Department of Chemistry & Biochemistry University of South Carolina, GSRC supplies from the Dept. of Chemistry & Biochemistry Stockroom must bring with them this completed pre

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

    SciTech Connect (OSTI)

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

    1993-06-01

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

  3. 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.

  4. Motion at low Reynolds number

    E-Print Network [OSTI]

    Tam, Daniel See Wai, 1980-

    2008-01-01

    The work described in this thesis centers on inertialess motion at low Reynolds numbers at the crossroad between biofluids and microfluids. Here we address questions regarding locomotion of micro-swimmers, transport of ...

  5. Departmental Business Instrument Numbering System

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

    2005-01-27

    The Order prescribes the procedures for assigning identifying numbers to all Department of Energy (DOE) and National Nuclear Security Administration (NNSA) business instruments. Cancels DOE O 540.1. Canceled by DOE O 540.1B.

  6. Departmental Business Instrument Numbering System

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

    2000-12-05

    To prescribe procedures for assigning identifying numbers to all Department of Energy (DOE), including the National Nuclear Security Administration, business instruments. Cancels DOE 1331.2B. Canceled by DOE O 540.1A.

  7. Danish Energy Authority Poland -Electricity and gas

    E-Print Network [OSTI]

    Danish Energy Authority Poland - Electricity and gas market development study and practical guidelines for using EU Funds Electricity sector analyses December 2004 #12;Danish Energy Authority Poland - Electricity and gas market development study and practical guidelines for using EU Funds Electricity sector

  8. Financial Policy Manual 2107 ACCOUNTING AUTHORITY & RESPONSIBILITY

    E-Print Network [OSTI]

    George, Edward I.

    Financial Policy Manual Page 1 2107 ACCOUNTING AUTHORITY & RESPONSIBILITY Effective: December 1986: Research Services PURPOSE To assign authority and responsibility for the accounting for sponsored projects must be separately accounted for per the terms of the award An advance account may be established prior

  9. Policy-Based Authorization William R. Cook

    E-Print Network [OSTI]

    Cook, William R.

    Page 1 Policy-Based Authorization William R. Cook Department of Computer Sciences University of Texas at Austin Abstract This paper discusses policy-based authorization, an effective intermediate point between MAC and DAC that promises to combine the best features of both models. Policy

  10. Using the Web for Name Authority Work

    E-Print Network [OSTI]

    Whittaker, Beth M.; Spillane, Jodi Lynn

    2001-01-01

    While many catalogers are using the Web to find the information they need to perform authority work quickly and accurately, the full potential of the Web to assist catalogers in name authority work has yet to be realized. The ever-growing nature...

  11. Kentucky Natural Gas Number of Residential Consumers (Number of Elements)

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (Billion Cubic Feet) Wyoming963Residential Consumers (Number of Elements) Kentucky Natural Gas Number

  12. A. Name: Information Systems Security Incident Response Policy B. Number: 20070103-secincidentresp

    E-Print Network [OSTI]

    George, Edward I.

    Page 1 I. Title A. Name: Information Systems Security Incident Response Policy B. Number: 20070103 and Responsibility Information Systems and Computing is responsible for the operation of Penn's data networks (Penn-secincidentresp C. Author(s): David Millar (ISC Information Security) and Lauren Steinfeld (Chief Privacy Officer

  13. TRANSPORT NUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION

    E-Print Network [OSTI]

    De Jonghe, Lutgard C.

    2014-01-01

    NUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION LutgardNUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION LutgardNUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION Lutgard

  14. TRANSPORT NUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION

    E-Print Network [OSTI]

    De Jonghe, Lutgard C.

    2012-01-01

    NUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION LutgardNUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION LutgardNUMBER GRADIENTS AND SOLID ELECTROLYTE DEGRADATION Lutgard

  15. PP-22 British Columbia Hydro and Power Authority, Amendment 1967...

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

    PP-22 British Columbia Hydro and Power Authority, Amendment 1967 PP-22 British Columbia Hydro and Power Authority, Amendment 1967 Presidential permit authorizing British Columbia...

  16. The Lichens of Aton Forest, Connecticut Author(s): Mason E. Hale, Jr.

    E-Print Network [OSTI]

    LeTourneau, Peter M.

    The Lichens of Aton Forest, Connecticut Author(s): Mason E. Hale, Jr. Source: The Bryologist, Vol OF ATON FOREST THE LICHENS OF ATON FOREST, CONNECTICUT MASONE. HALE, JR. INTRODUCTION During the summer, CONNECTICUT MASONE. HALE, JR. INTRODUCTION During the summer of 1949 the author studied the lichens of Aton

  17. Experimental determination of Ramsey numbers

    E-Print Network [OSTI]

    Zhengbing Bian; Fabian Chudak; William G. Macready; Lane Clark; Frank Gaitan

    2013-08-14

    Ramsey theory is a highly active research area in mathematics that studies the emergence of order in large disordered structures. Ramsey numbers mark the threshold at which order first appears and are extremely difficult to calculate due to their explosive rate of growth. Recently, an algorithm that can be implemented using adiabatic quantum evolution has been proposed that calculates the two-color Ramsey numbers $R(m,n)$. Here we present results of an experimental implementation of this algorithm and show that it correctly determines the Ramsey numbers R(3,3) and $R(m,2)$ for $4\\leq m\\leq 8$. The R(8,2) computation used 84 qubits of which 28 were computational qubits. This computation is the largest experimental implementation of a scientifically meaningful adiabatic evolution algorithm that has been done to date.

  18. Nuclear Material Disposition

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

    2015-12-18

    This Guide describes acceptable, but not mandatory means for complying with requirements. Guides are not requirements documents and are not to be construed as requirements in any audit or appraisal for compliance with associated rule or directives.

  19. Facility Disposition Projects

    Office of Environmental Management (EM)

    5 37.5 A4 Independent Cost EstimateSchedule Review P 3.0 NA 0.0 5 15.0 5 15.0 A5 Life Cycle Cost P 3.0 1 3.0 4 12.0 5 15.0 A6 Forecast of Cost at Completion P 3.0 NA 0.0 3 9.0 5...

  20. Integrated Facilities Disposition Program

    Office of Environmental Management (EM)

    Hole 8 Plume 6 Managed by UT-Battelle for the U.S. Department of Energy Remediating aging waste treatment and collection systems is an integral part of the Central Campus...

  1. Delegation as Officially Designated Federal Security Authority...

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

    Status: Current Effective Date: Sep 27, 2012 Re-delegation Allowed: No Authorities: DOE O 473.3 Related History Related to: DOE O 473.3, Protection Program Operations There...

  2. Safety Management Functions, Responsibilities, and Authorities Manual

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

    2003-12-31

    This Manual defines safety management functions, responsibilities, and authorities for DOE senior management with responsibilities for line, support, oversight, and enforcement actions. Cancels DOE M 411.1-1B. Canceled by DOE O 450.2.

  3. Safety Management Functions, Responsibilities, and Authorities Manual

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

    1997-10-08

    This Manual defines safety management functions, responsibilities, and authorities for DOE senior management with responsibilities for line, support, oversight, and enforcement actions. Canceled by DOE M 411.1-1A. Does not cancel other directives.

  4. Shared Authority Concerns in Automated Driving Applications

    E-Print Network [OSTI]

    Cummings, M.L.

    2014-05-13

    Given the move toward driverless cars, which includes the more short-term goal of driving assistance, what the appropriate shared authority and interaction paradigms should be between human drivers and the automation remains ...

  5. Safety Management Functions, Responsibilities, and Authorities

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

    2001-05-22

    This Manual provides the responsibilities of Headquarters and field element offices required by DOE P 411.1, Safety Management Functions, Responsibilities and Authorities Policy, dated 1-28-97. It also contains detailed requirements to supplement the policy's direction for each DOE organization having safety management functions to establish and maintain separate documentation of their responsibilities and authorities. Cancels DOE M 411.1-1A. Canceled by DOE M 411.1-1C.

  6. Constrained Ramsey Numbers of Graphs

    E-Print Network [OSTI]

    Jiang, Tao

    Constrained Ramsey Numbers of Graphs Robert E. Jamison,1 Tao Jiang,2* and Alan C. H. Ling3 1-like trees. � 2002 Wiley Periodicals, Inc. J Graph Theory 42: 1­16, 2003 Keywords: Ramsey; monochromatic edges have the same color and rainbow iff all of its edges have different colors. In classical Ramsey

  7. Swimming by numbers QUANTUM CONTROL

    E-Print Network [OSTI]

    Mahadevan, L.

    flow, providing key qualitative insight in fluid mechanics. For example, the so-called Reynolds number be described by a universal mechanical principle seems optimistic -- if not entirely unrealistic. Now, however and pressure forces relevant for net propulsion. A measure of the thrust force is given by the mass

  8. A Design and Implementation of Immersive Virtual Space Authoring System Jeongdan Choi, Chansu Lee, Kwangman Oh, Chanjong Park

    E-Print Network [OSTI]

    Lee, Chan-Su

    software modules, 3D authoring software modules and VR I/O devices such as CyberGlove and HMD. We also house. Also, many authors who want to create the virtual space need more and more convenient interface of a number of commands for object loading, object placement, property specification and animation

  9. Louisiana Natural Gas Number of Residential Consumers (Number of Elements)

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (Billion Cubic Feet) Wyoming963Residential Consumers (Number of33Cubic Foot)Year Jan

  10. California Natural Gas Number of Residential Consumers (Number of Elements)

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (Billion Cubic Feet) Wyoming963 1.969 1.979Coal4 ArizonaResidential Consumers (Number of Elements)

  11. Nebraska Natural Gas Number of Industrial Consumers (Number of Elements)

    U.S. Energy Information Administration (EIA) 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 PageMonthly","10/2015"4,"Ames5 Tables July 1996 Energy Information Administration Office of Coal, Nuclear,Decade Year-03.823,172 3,009165,360Industrial Consumers (Number of

  12. Nebraska Natural Gas Number of Residential Consumers (Number of Elements)

    U.S. Energy Information Administration (EIA) 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 PageMonthly","10/2015"4,"Ames5 Tables July 1996 Energy Information Administration Office of Coal, Nuclear,Decade Year-03.823,172 3,009165,360Industrial Consumers (Number

  13. North Dakota Natural Gas Number of Industrial Consumers (Number of

    U.S. Energy Information Administration (EIA) 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 PageMonthly","10/2015"4,"Ames5 Tables July 1996 Energy Information Administration Office of Coal, Nuclear,DecadeYear Jan FebElements) Industrial Consumers (Number of

  14. North Dakota Natural Gas Number of Residential Consumers (Number of

    U.S. Energy Information Administration (EIA) 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 PageMonthly","10/2015"4,"Ames5 Tables July 1996 Energy Information Administration Office of Coal, Nuclear,DecadeYear Jan FebElements) Industrial Consumers (Number

  15. State authority in an expanded territorial sea 

    E-Print Network [OSTI]

    Fulbright, Michael Gene

    1977-01-01

    . , University of West Florida Chairman of Advisory Committee: John L. Seymour The purpose of this thesis was to examine what types of state authority would extend to an expanded area of the territorial sea. This thesis first exa- mines the historical... miles ioso 82 facto for any Gulf State. State boundaries were to be determined by the historic action taken with respect to them jointly by Congress and the state itself. The authors of the SLA intended that such joint action wou~M fix the states...

  16. EFFECTIVENESS OF LEAD-LAG PHASING ON PROGRESSION BANDWIDTH Zong Tian (Corresponding Author)

    E-Print Network [OSTI]

    Tian, Zong Z.

    EFFECTIVENESS OF LEAD-LAG PHASING ON PROGRESSION BANDWIDTH Zong Tian (Corresponding Author) Varun of using lead-lag phasing, and 2) the effect of number of signals on progression bandwidth. A computer that lead-lag phasing had a significant advantage over the leading left-turn and lagging left-turn phasing

  17. Author's personal copy A note on the scope of the journal

    E-Print Network [OSTI]

    Lee, Xuhui

    Author's personal copy Editorial A note on the scope of the journal Agricultural and Forest Meteorology is an international journal for the publication of original articles and reviews on the inter experimental data. In recent years, the journal has seen a rapid increase in submission numbers. This growth

  18. The Fermat and Mersenne Numbers 

    E-Print Network [OSTI]

    Nowlin, W. D.

    1960-01-01

    . (Throughout this thesis, F will always denote a Feraat nmaber and M a Mersenne nuuber. ) The problea of deternining p which of the Fernat and Mersenne nmabers are prius has concerned uany matheuaticians during the last two centuries. This research has... or a Fermat, number. Next? Froth~a theorem, of which Pepin's test is a special case, is stated and proved. In the last section the theory of recurring series is used to establish primality tests of the Lucas type for both the Fermat and Mersenne...

  19. Risk Management for Distributed Authorization Christian Skalka

    E-Print Network [OSTI]

    Wang, Xiaoyang "Sean"

    Risk Management for Distributed Authorization Christian Skalka University of Vermont X. Sean Wang assess risk, but risk in trust management is usually an informal consideration. In this paper, we de trust management systems treat all assertions as equally valid up to certificate authentication

  20. Energy Resources and Convening Lead Author (CLA)

    E-Print Network [OSTI]

    Power S.p.A., Italy) S.C. Bhattacharya (International Energy Initiative, India) Maurice B. Dusseault (University of Waterloo, Canada) Luc Gagnon (HydroQuébec, Canada) Helmut Haberl (Klagenfurt University Leoben,Austria) Vladimir Yakushev (Gazprom, Russia) Contributing Authors (CA) Doug J. Arent (National

  1. WEAPONS ON CAMPUS Authority: Chief of Police

    E-Print Network [OSTI]

    Scharf, Fred

    05.501 WEAPONS ON CAMPUS Authority: Chief of Police History: Established September 14, 2006 Source of weapons on UNCW property. II. Policy A. The University of North Carolina system of campuses is classified be unlawful for any person to possess the following weapons on UNCW property: 1. Dynamite cartridge, bomb

  2. Guide to Authors About the Journal

    E-Print Network [OSTI]

    Loss, Daniel

    nature physics Guide to Authors About the Journal Aims and scope of the journal Nature Physics. The journal content reflects core physics disciplines, but is also open to a broad range of topics whose to experiment, also features. Research areas covered in the journal include: · Quantum physics · Atomic

  3. Page 1 of 1 Author Query Form

    E-Print Network [OSTI]

    Utsunomiya, Satoshi

    ;A/Author phone: C;A/Title C;A/Department Department of Nuclear Engineering and Radiological Sciences C 48109-2104 C;A/Country U.S.A. C;A/Title C;A/Department Department of Nuclear Engineering, and Nuclear Engineering and Radiological Science C;A/Institution University of Michigan C;A/Street Address

  4. COMPARING THE VANCOUVER INTERNATIONAL AIRPORT AUTHORITY'S

    E-Print Network [OSTI]

    prescribed authorities to conduct environmental impact assessments (EIAs) of projects carried out on federal environmental management. The International Association for Impact Assessment's (IAIA) Principles for EIA Best if the proposed CEAA regulations come into force. Keywords: Environmental impact assessment; best practice

  5. Web Information Retrieval Author Preprint for Web

    E-Print Network [OSTI]

    Hawking, David

    indexes is often called `the hidden web', `the deep web', or `web dark matter' (Bailey et al., 2000). 2Web Information Retrieval Author Preprint for Web Nick Craswell and David Hawking 18 April 2009 1 Introduction This chapter outlines some distinctive characteristics of web information re- trieval, starting

  6. Authorization in Trust Management: Features and Foundations

    E-Print Network [OSTI]

    Wang, Xiaoyang "Sean"

    Authorization in Trust Management: Features and Foundations Peter C. Chapin University of Vermont and Christian Skalka University of Vermont and X. Sean Wang University of Vermont Trust management systems' addresses: Peter Chapin, University of Vermont, Department of Computer Science, Burlington, VT 05405

  7. Intuitive Ontology Authoring using Controlled Natural Language

    E-Print Network [OSTI]

    Dimitrova, Vania

    in accordance with the requirements for the degree of Doctor of Philosophy University of Leeds School. 246-264. This paper was mostly written by me, and reviewed and improved by the other authors. ©2013 University of Leeds and Ronald Denaux #12;to... domain experts, I suppose. #12;Acknowledgements My

  8. Reconsidering Authority Scientific Expertise, Bounded Rationality,

    E-Print Network [OSTI]

    Strevens, Michael

    , perhaps, but disastrous for us, living in this world in which almost all information about anything sources; rather, we should give it special treatment, keeping track of it even after we have extracted of that authority. I will search for a semiformal model of epistemic backtracking, a model formal enough

  9. Paper Preview Paper Number 63180-MS

    E-Print Network [OSTI]

    Abu-Khamsin, Sidqi

    Preconditioning Authors M.A. Aggour, King Fahd University of Petroleum & Minerals; M.A. Al-Muhareb, Saudi Aramco

  10. DRAFT CRUISE REPORT Cruise Number: DY0807

    E-Print Network [OSTI]

    Neuston (Neu) 68 Deployment of satellite buoy (SatBuoy) 3 Samples Collected Tows Number Number of larvae of buoy or mooring (Deploy) 3 3 Stimulated fluorescence collected during CTD casts (Fluor) 18 Number

  11. The Evolution of Science Museums Author(s): Silvio A. Bedini

    E-Print Network [OSTI]

    Short, Daniel

    University Press on behalf of the Society for the History of Technology Stable URL: http@jstor.org. . Society for the History of Technology and The Johns Hopkins University Press are collaborating with JSTORThe Evolution of Science Museums Author(s): Silvio A. Bedini Reviewed work(s): Source: Technology

  12. Storage Operators and Directed Lambda-Calculus Author(s): Rene David and Karim Nour

    E-Print Network [OSTI]

    Nour, Karim

    Storage Operators and Directed Lambda-Calculus Author(s): Rene David and Karim Nour Source, December 1995 STORAGE OPERATORS AND DIRECTED LAMBDA-CALCULUS RENE DAVID AND KARIM NOUR Abstract. Storage. With this calculus we get an equivalent-and simple-definition of the storage operators that allows to show some

  13. Deriving Morality from Politics: Rethinking the Formula of Humanity Author(s): Japa Pallikkathayil

    E-Print Network [OSTI]

    Machery, Edouard

    Deriving Morality from Politics: Rethinking the Formula of Humanity Author(s): Japa Pallikkathayil-1704/2010/12101-0001$10.00 116 Deriving Morality from Politics: Rethinking the Formula of Humanity* Japa Pallikkathayil Kant's Formula of Humanity famously forbids treating others merely as a means. It is unclear, however, what

  14. Rainbow Trout Production in Dystrophic Lakes Author(s): Waldo E. Johnson and Arthur D. Hasler

    E-Print Network [OSTI]

    Notre Dame, University of

    Rainbow Trout Production in Dystrophic Lakes Author(s): Waldo E. Johnson and Arthur D. Hasler://www.jstor.org #12;RAINBOW TROUT PRODUCTION IN DYSTROPHIC LAKES1 Waldo E. Johnson and Arthur D. Hasler Department, and it is well known that these small lakes contribute very little to the sport fishery of this area

  15. Carbon Dioxide Evolution from the Floor of Three Minnesota Forests Author(s): W. A. Reiners

    E-Print Network [OSTI]

    Thomas, David D.

    Carbon Dioxide Evolution from the Floor of Three Minnesota Forests Author(s): W. A. Reiners and extend access to Ecology. http://www.jstor.org #12;Late Spring 1968 CARBON DIOXIDE EVOLUTION RATES 471. Germination behavior of some halc- phytes. Bull. Res. Council Israel (D) 6: 187-188. CARBON DIOXIDE EVOLUTION

  16. Buy Coal! A Case for Supply-Side Environmental Policy Author(s): Brd Harstad

    E-Print Network [OSTI]

    Stølen, Ketil

    Buy Coal! A Case for Supply-Side Environmental Policy Author(s): Bård Harstad Reviewed work by The University of Chicago. All rights reserved. 0022-3808/2012/12001-0003$10.00 Buy Coal! A Case for Supply, world prices change and nonpartici- pants typically emit more; they may also extract the dirtiest type

  17. Journal of Philosophy, Inc. Author(s): Alan Ross Anderson and Nuel D. Belnap, Jr.

    E-Print Network [OSTI]

    Belnap, Nuel

    Journal of Philosophy, Inc. Enthymemes Author(s): Alan Ross Anderson and Nuel D. Belnap, Jr. Source: The Journal of Philosophy, Vol. 58, No. 23, American Philosophical Association Eastern Division Fifty: Journal of Philosophy, Inc. Stable URL: http://www.jstor.org/stable/2023169 Accessed: 28/05/2009 15

  18. Natural and Experimental Boudinage and Pinch-and-Swell Structures Author(s): Hans Ramberg

    E-Print Network [OSTI]

    Lee, Cin-Ty Aeolus

    Natural and Experimental Boudinage and Pinch-and-Swell Structures Author(s): Hans Ramberg Source, and build upon a wide range of content in a trusted digital archive. We use information technology and tools BOUDINAGE AND PINCH-AND-SWELL STRUCTURES1 HANS RAMBERG University of Chicago ABSTRACT Examples of boudinage

  19. Multivariate Analysis of Drosophila Courtship Author(s): Therese A. Markow and Stephen J. Hanson

    E-Print Network [OSTI]

    Markow, Therese

    Multivariate Analysis of Drosophila Courtship Author(s): Therese A. Markow and Stephen J. Hanson.Natl.Acad.Sci.USA Vol. 78, No. 1, pp. 430-434, January1981 Genetics Multivariate analysis of Drosophila (sequential%). Potential ap- plications of this multivariate analysis to investigations of neuro- biological

  20. Natural Selection and Culture Author(s): Peter J. Richerson and Robert Boyd

    E-Print Network [OSTI]

    Richerson, Peter J.

    Natural Selection and Culture Author(s): Peter J. Richerson and Robert Boyd Source: BioScience, Vol indicates your acceptance of JSTOR's Terms and Conditions of Use, available at http://www.jstor.org/page/info the discovery and use of these resources. For more information about JSTOR, please contact support

  1. On Stress and Linguistic Rhythm Author(s): Mark Liberman and Alan Prince

    E-Print Network [OSTI]

    Pennsylvania, University of

    On Stress and Linguistic Rhythm Author(s): Mark Liberman and Alan Prince Source: Linguistic Inquiry-336. Mark Liberman, On Stress and Linguistic Alan Prince Rhythm* 0. Prospectus In this essay a new theory to JSTOR Terms and Conditions #12;250 MARK LIBERMAN AND ALAN PRINCE patternsof stress in termsof

  2. Date Revised: 2015-02-10 FIN-FRM-008R Signing Authority & Research Reports Access Research Funds Page 1 of 2 This form will serve to delegate or remove Signing Authority and/or Research Reports Access for the Project identified

    E-Print Network [OSTI]

    Fletcher, Robin

    Date Revised: 2015-02-10 FIN-FRM-008R Signing Authority & Research Reports Access ­ Research Funds Page 1 of 2 This form will serve to delegate or remove Signing Authority and/or Research Reports Access. There is no limit on the number of individuals to whom Signing Authority and/or Research Reports access may

  3. Author Index Abezgauz, Ludmila P1

    E-Print Network [OSTI]

    Martin, Jan M.L.

    Author Index Abezgauz, Ludmila P1 Abu-Reziq, Raed S1b3 Abutbul, Inbal P130 Adadi, Racheli P2 Addadi, Lia S2c5, P67, P123, P129, P159, P182 Adler, Michal P69 Afri, Michal P3, P26, P38 Agmon, Noam P131 Aharoni, Anna P4 Aharonov, Yakir P106 Akiva, Udi S4c1 Albeck, Amnon S1c5, P5 Albu-Yaron, Ana P210

  4. Evaluating the Web Hubs and Authorities

    E-Print Network [OSTI]

    Ullman, Jeffrey D.

    1 Evaluating the Web PageRank Hubs and Authorities #12;2 PageRank Intuition: solve the recursive = the principal eigenvector of the stochastic matrix of the Web. A few fixups needed. #12;3 Stochastic Matrix of the Web Enumerate pages. Page i corresponds to row and column i. M [i,j ] = 1/n if page j links to n pages

  5. Ramsey numbers of sparse hypergraphs David Conlon

    E-Print Network [OSTI]

    Fox, Jacob

    Ramsey numbers of sparse hypergraphs David Conlon Jacob Fox Benny Sudakov Abstract We give a short proof that any k-uniform hypergraph H on n vertices with bounded degree has Ramsey number at most c(, k on the Ramsey number of hypergraphs with at most m edges. 1 Introduction For a graph H, the Ramsey number r

  6. Contact-Handled Transuranic Waste Authorized Methods for Payload...

    Office of Environmental Management (EM)

    Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH TRAMPAC) Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH TRAMPAC) This...

  7. Energy Department Authorizes Dominion Cove Point LNG to Export...

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

    Energy Department Authorizes Dominion Cove Point LNG to Export Liquefied Natural Gas Energy Department Authorizes Dominion Cove Point LNG to Export Liquefied Natural Gas May 7,...

  8. Energy Department Authorizes Freeport LNG to Export Liquefied...

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

    Department Authorizes Freeport LNG to Export Liquefied Natural Gas Energy Department Authorizes Freeport LNG to Export Liquefied Natural Gas November 14, 2014 - 2:00pm Addthis News...

  9. Energy Department Authorizes Second Proposed Facility to Export...

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

    Energy Department Authorizes Second Proposed Facility to Export Liquefied Natural Gas Energy Department Authorizes Second Proposed Facility to Export Liquefied Natural Gas May 17,...

  10. Energy Department Authorizes Emera CNG, LLC's Application to...

    Office of Environmental Management (EM)

    Authorizes Emera CNG, LLC's Application to Export Compressed Natural Gas Energy Department Authorizes Emera CNG, LLC's Application to Export Compressed Natural Gas October 19, 2015...

  11. Orders Granting Natural Gas, LNG & CNG Authorizations Issued...

    Office of Environmental Management (EM)

    Orders Granting Natural Gas, LNG & CNG Authorizations Issued in 2014 Orders Granting Natural Gas, LNG & CNG Authorizations Issued in 2014 Order 3378 - Encana Natural Gas Inc. Order...

  12. Project Reports for Peoria Tribe: Housing Authority- 2010 Project

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Housing Authority of the Peoria Tribe of Indians of Oklahoma (Peoria Housing Authority or PHA) will conduct the "PHA Weatherization Training Project."

  13. Presidential Permits and Export Authorizations - About the Program...

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

    transmission lines which cross the U.S. international border; and 2.Authorizing exports of electric energy to foreign countries. The authority to grant Presidential permits...

  14. POLICY GUIDANCE MEMORANDUM #09A Direct Hire Authority for Acquisition...

    Office of Environmental Management (EM)

    09A Direct Hire Authority for Acquisition Positions (Expired) POLICY GUIDANCE MEMORANDUM 09A Direct Hire Authority for Acquisition Positions (Expired) THIS GUIDANCE HAS EXPIRED...

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    02 Using Schedule A Hiring Authority for ARRA Positions (Expired) POLICY GUIDANCE MEMORANDUM 02 Using Schedule A Hiring Authority for ARRA Positions (Expired) THIS GUIDANCE HAS...

  16. Santa Clara Valley Transportation Authority and San Mateo County...

    Energy Savers [EERE]

    Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results Santa Clara Valley Transportation Authority and San...

  17. Cooperation Among Balancing Authorities Offers Greater Use of...

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    Cooperation Among Balancing Authorities Offers Greater Use of Renewable Energy with Lower Integration Costs Cooperation Among Balancing Authorities Offers Greater Use of Renewable...

  18. Department for Analysis and Computational Number Theory Additive functions and number systems

    E-Print Network [OSTI]

    Department for Analysis and Computational Number Theory Additive functions and number systems systems April 7, 2010 1 / 35 #12;Department for Analysis and Computational Number Theory Outline Number and Computational Number Theory Number systems Let R be an integral domain, b R, and N = {n1, . . . , nm} R

  19. Express Card Department Administrator Authorization Form

    E-Print Network [OSTI]

    California at San Diego, University of

    office has a commitment to the Express Card program and approves participation We are ready to design' number review of individual purchases for procurement policy compliance prompt submission of receipts administrator will receive email notification of all purchases made by cardholders in the department or unit

  20. The number of genome duplications uncovered in the evolutionary history of land plants seems to be steadily

    E-Print Network [OSTI]

    Gent, Universiteit

    .vandepeer@psb.vib-ugent.be 1 Department of Plant Systems Biology, VIB, Technologiepark 927, Ghent, Belgium Full list of authorThe number of genome duplications uncovered in the evolutionary history of land plants seems, previously unnoticed ancient whole genome duplications (WGDs) in seed plants. More precisely, the authors

  1. Long Island Power Authority | Open Energy Information

    Open Energy Info (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 QA:QAsource History View NewTexas:Montezuma, Arizona:Oregon: EnergyLloyd, NewBranch Capital Jump to:Authority Jump to:

  2. Lower Colorado River Authority | Open Energy Information

    Open Energy Info (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 QA:QAsource History View NewTexas:Montezuma, Arizona:Oregon:Lowell Point, Alaska: Energy ResourcesAuthority Jump to:

  3. Municipal Electric Authority | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION J APPENDIX ECoop Inc Jump to: navigation,Mereg GmbHMontebalitoMt Princeton HotMultilagosAuthority

  4. Tennessee Valley Authority (Kentucky) | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION J APPENDIX ECoop Inc JumpHeter BatterySolarfinMarketMemberI PLLCsourceValley Authority (Kentucky)

  5. Bolivar Energy Authority | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION JEnvironmental JumpInformationBio-GasIllinois:Energy Authority Jump to: navigation, search

  6. Property:Author | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION J APPENDIXsourceII JumpQuarterly SmartDB-2,Information PromotingProperty EditAuthor Jump to:

  7. Property:Authority | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION J APPENDIXsourceII JumpQuarterly SmartDB-2,Information PromotingProperty EditAuthor Jump

  8. Property:File/Author | Open Energy Information

    Open Energy Info (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 QA:QA J-E-1 SECTION JEnvironmental Jump to: navigation,Property Edit withExplorationTimePerMetricProperty EditAuthor

  9. Technology Partnership Ombudsman - Roles, Responsibilities, Authorities and

    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 QA:QA J-E-1 SECTION J APPENDIX E LIST OF APPLICABLEStatutory Authority J-I- 1May 20062012

  10. NercEnergy, Author at Nercenergy

    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 NewsInformationJessework usesofPublications TheScience4.21 4.43EnergyAuthor: NercEnergy

  11. Volume 60, Numbers 3&4 (Complete) 

    E-Print Network [OSTI]

    Dickson, Donald

    2002-01-01

    , intends ?to re-establish the notion that books are written by people who lived in particular times and places?; each volume ?will include substantial critical discussion? of the author?s works. Barbara K. Lewalski?s The Life of John Milton: A Critical... SUBMISSIONS: Though primarily a review journal, SCN also publishes shorter articles and scholarly notes. Manuscripts should be submitted in duplicate (with the author?s name and institutional affiliation on the cover page only) accompanied by a stamped, self...

  12. Prime number generation and factor elimination

    E-Print Network [OSTI]

    Vineet Kumar

    2014-10-06

    We have presented a multivariate polynomial function termed as factor elimination function,by which, we can generate prime numbers. This function's mapping behavior can explain the irregularities in the occurrence of prime numbers on the number line. Generally the different categories of prime numbers found till date, satisfy the form of this function. We present some absolute and probabilistic conditions for the primality of the number generated by this method. This function is capable of leading to highly efficient algorithms for generating prime numbers.

  13. MULTIPLE AUTHORIZATION A Model and Architecture for Increased, Practical Security

    E-Print Network [OSTI]

    ]. Contraction-Minimal triangulations are called minimal or irreducible triangu- lations by various authors. 1

  14. Logical Attestation: An Authorization Architecture for Trustworthy Computing

    E-Print Network [OSTI]

    Sirer, Emin Gun

    system. Key words: simulation, interactive storytelling, story authoring 1 Introduction Storytelling

  15. Motor Fleet Request/Authorization Page 1 UNCW Travel System

    E-Print Network [OSTI]

    Olszewski Jr., Edward A.

    Motor Fleet Request/Authorization Page 1 UNCW Travel System Motor Fleet Request/Travel Authorization ENTER THE MOTOR FLEET REQUEST IN THE TRANSPORTATION SECTION OF THE TRAVEL AUTHORIZATION. PRESS CLICK TO ADD AND SELECT MOTOR FLEET FROM THE DROP-DOWN BOX. #12;Motor Fleet Request/Authorization Page 2

  16. 168 Hinweise fr die Autoren Instructions to Authors

    E-Print Network [OSTI]

    Wien, Universität

    in SMALL CAPITALS: SINGER (1964), KÜHNER & ROMAGNESI (1975), when more than two authors: SMITH & al. (1982

  17. Turing's normal numbers: towards randomness Veronica Becher

    E-Print Network [OSTI]

    presumably in 1938 Alan Turing gave an algorithm that produces real numbers normal to every integer base- putable normal numbers, and this result should be attributed to Alan Turing. His manuscript entitled "A

  18. A thermodynamic classification of pairs of real numbers via the Triangle Multi-dimensional continued fraction

    E-Print Network [OSTI]

    Thomas Garrity

    2012-05-25

    A new classification scheme for pairs of real numbers is given, generalizing earlier work of the author that used continued fraction, which in turn was motivated by ideas from statistical mechanics in general and work of Knauf and Fiala and Kleban in particular. Critical for this classification are the number theoretic and geometric properties of the triangle map, a type of multi-dimensional continued fraction.

  19. Small Ramsey Numbers Stanislaw P. Radziszowski

    E-Print Network [OSTI]

    Radziszowski, Stanislaw P.

    Small Ramsey Numbers Stanislaw P. Radziszowski Department of Computer Science Rochester Institute Ramsey numbers, where the avoided graphs are complete or complete without one edge. Many results per behavior of Ramsey numbers, but rather we concentrate on their specific values. Mathematical Reviews

  20. SHARP THRESHOLDS FOR HYPERGRAPH REGRESSIVE RAMSEY NUMBERS

    E-Print Network [OSTI]

    Lee, Gyesik

    SHARP THRESHOLDS FOR HYPERGRAPH REGRESSIVE RAMSEY NUMBERS LORENZO CARLUCCI, GYESIK LEE, AND ANDREAS WEIERMANN Abstract. The f-regressive Ramsey number Rreg f (d, n) is the minimum N such that every colouring regressive Ramsey numbers as defined by Kanamori and McAloon. In this paper we classifiy the growth

  1. Motivation Examples Star Avoiding Ramsey Numbers

    E-Print Network [OSTI]

    Isaak, Garth

    Motivation Examples Star Avoiding Ramsey Numbers Jonelle Hook, Garth Isaak Department and Cryptography Jonelle Hook, Garth Isaak Star Avoiding Ramsey Numbers #12;Motivation Examples Graph Ramsey-coloring of K13 has a red C5 or a blue K4. Jonelle Hook, Garth Isaak Star Avoiding Ramsey Numbers #12

  2. Diagonal Ramsey Numbers in Multipartite Graphs

    E-Print Network [OSTI]

    van Vuuren, Jan H.

    Diagonal Ramsey Numbers in Multipartite Graphs AP Burger , PJP Grobler , EH Stipp & JH van Vuuren September 17, 2003 Abstract The notion of a graph theoretic Ramsey number is generalised by assuming definition. Some small multipartite Ramsey numbers are found, while upper and lower bounds are established

  3. Diagonal Ramsey Numbers in Multipartite Graphs

    E-Print Network [OSTI]

    van Vuuren, Jan H.

    Diagonal Ramsey Numbers in Multipartite Graphs AP Burger + , PJP Grobler # , EH Stipp # & JH van Vuuren # September 17, 2003 Abstract The notion of a graph theoretic Ramsey number is generalised as in the classical definition. Some small multipartite Ramsey numbers are found, while upper and lower bounds

  4. Number of peer-reviewed publications

    E-Print Network [OSTI]

    ·Number of peer- reviewed publications produced per year ·Data accurate as of 02 April 2012 · Number of publications produced per institution (top 10) ·Collaborations counted multiple times · Non-cumulative number of citations received by OER publications per year ·Data accurate as of 02 April 2012 · The work

  5. Company number 5857955 Wellcome Trust Finance plc

    E-Print Network [OSTI]

    Rambaut, Andrew

    Company number 5857955 Wellcome Trust Finance plc Annual Report and Financial Statements Year ended 30 September 2014 #12;Company number 5857955 Wellcome Trust Finance plc Contents Page Strategic number 58579551 Wellcome Trust Finance plc Strategic Report For the year ended 30 September 2014

  6. KIAS SEOUL, February 2004 Transcendental Number Theory

    E-Print Network [OSTI]

    Waldschmidt, Michel

    ) ­ Introductio in Analysin Infinitorum. Suggests the transcendence of log 1/ log 2 when this number is irrational in Analysin Infinitorum. Suggests the transcendence of log 1/ log 2 when this number is irrational (for this number is irrational (for algebraic 1 and 2). http://www.math.jussieu.fr/miw/ 14 #12;Euler (1748

  7. Clar number of catacondensed benzenoid hydrocarbons

    E-Print Network [OSTI]

    Klavzar, Sandi

    Clar number of catacondensed benzenoid hydrocarbons Sandi KlavŸzar a,# , Petra Ÿ Zigert a , Ivan hydrocarbon: CL is equal to the minimum number of straight lines required to intersect all hexagons theory; Clar formula; Clar number; Resonance graph; Benzenoid hydrocarbons 1. Introduction Within

  8. Authorized limits for Fernald copper ingots

    SciTech Connect (OSTI)

    Frink, N.; Kamboj, S.; Hensley, J.; Chen, S. Y.

    1997-09-01

    This development document contains data and analysis to support the approval of authorized limits for the unrestricted release of 59 t of copper ingots containing residual radioactive material from the U.S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP). The analysis presented in this document comply with the requirements of DOE Order 5400.5, {open_quotes}Radiation Protection of the Public and the Environment,{close_quotes} as well as the requirements of the proposed promulgation of this order as 10 CFR Part 834. The document was developed following the step-by-step process described in the Draft Handbook for Controlling Release for Reuse or Recycle Property Containing Residual Radioactive Material.

  9. TITLE: AUTHOR(S) SUBMITTED TO: Mm EVOLUTIO:l C: S!LICIC

    Office of Scientific and Technical Information (OSTI)

    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 MunicipalTechnicalInformation FederatedInformationTITLE: AUTHOR(S) SUBMITTED TO: Mm EVOLUTIO:l

  10. A. E. K. Ris Ris-M-GHZ Title and authors)

    E-Print Network [OSTI]

    A. E. K. Risø Risø-M-GHZ r» I Gto Title and authors) Users Manual for the PWR-PLASIM Model by P. la of the PWR power plant model PWR-PLASIM described in Risø Report No. 318. It should serve as a users guide Reactor Technology Group's own registration numbers) PWR-1-7 5 Copies to Abstract to #12;ISBN 87 550 0302

  11. Telemetry as a Technique in the Study of Predation Author(s): L. David Mech

    E-Print Network [OSTI]

    Thomas, David D.

    in this regard by Marshall and Kupa (1963). These authors were able to locate four predator- killed grouse (Bonasa umbellus) and deter- mine the type of predation in three cases. Recently McEwen and Brown (1966 in a collar of dental acrylic (Mech et al. 1965). They were re- leased where captured. Movements

  12. Tip sheet: Expanded Library of Congress Call Number Classification system Call Number Subject Matter

    E-Print Network [OSTI]

    Kambhampati, Patanjali

    Tip sheet: Expanded Library of Congress Call Number Classification system Call Number Subject R: Medicine T: Technology U: Military Science Z: Bibliography. Library Science. Information

  13. Neutronic evaluation of a non-fertile fuel for the disposition of weapons-grade plutonium in a boiling water reactor

    SciTech Connect (OSTI)

    Sterbentz, J.W.

    1994-10-01

    A new non-fertile, weapons-grade plutonium oxide fuel concept is developed and evaluated for deep burn applications in a boiling water reactor environment using the General Electric 8x8 Advanced Boiling Water Reactor (ABWR) fuel assembly dimensions and pitch. Detailed infinite lattice fuel burnup results and neutronic performance characteristics are given and although preliminary in nature, clearly demonstrate the fuel`s potential as an effective means to expedite the disposition of plutonium in existing light water reactors. The new non-fertile fuel concept is an all oxide composition containing plutonia, zirconia, calcia, and erbia having the following design weight percentages: 8.3; 80.4; 9.7; and 1.6. This fuel composition in an infinite fuel lattice operating at linear heat generation rates of 6.0 or 12.0 kW/ft per rod can remain critical for up to 1,200 and 600 Effective Full Power Days (EFPD), respectively, and achieve a burnup of 7.45 {times} 10{sup 20} f/cc. These burnups correspond to a 71--73% total plutonium isotope destruction and a 91--94% destruction of the {sup 239}Pu isotope for the 0--40% moderator steam void condition. Total plutonium destruction greater than 73% is possible with a fuel management scheme that allows subcritical fuel assemblies to be driven by adjacent high reactivity assemblies. The fuel exhibits very favorable neutron characteristics from beginning-of-life (BOL) to end-of-life (EOL). Prompt fuel Doppler coefficient of reactivity are negative, with values ranging between {minus}0.4 to {minus}2.0 pcm/K over the temperature range of 900 to 2,200 K. The ABWR fuel lattice remains in an undermoderated condition for both hot operational and cold startup conditions over the entire fuel burnup lifetime.

  14. A True Measure of Exposure 238 Los Alamos Science Number 23 1995

    E-Print Network [OSTI]

    Massey, Thomas N.

    A True Measure of Exposure 238 Los Alamos Science Number 23 1995 Authorization and Collection Alamos tissue analysis program obtained samples for study. During the first twelve years of the program at the Los Alamos Medical Center. As described in the main text, the first case was Cecil Kelley, who had

  15. PHYSICAL REVIEW C VOLUME 46, NUMBER 1 JULY 1992 Nuclear fission with diffusive dynamics

    E-Print Network [OSTI]

    Bertsch George F.

    PHYSICAL REVIEW C VOLUME 46, NUMBER 1 JULY 1992 Nuclear fission with diffusive dynamics D. Cha investigate the dynamics of nuclear fission, assuming purely diffusive motion up to the saddle point/BP=(Bp/BE' )(BE*/BP). Several authors have applied the Smoluchowski equation to nuclear fission processes

  16. Regulatory and technical reports (abstract index journal): Annual compilation for 1997. Volume 22, Number 4

    SciTech Connect (OSTI)

    1998-04-01

    This journal includes all formal reports in the NUREG series prepared by the NRC staff and contractors; proceedings of conferences and workshops; as well as international agreement reports. The entries in this compilation are indexed for access by title and abstract, secondary report number, personal author, subject, NRC organization for staff and international agreements, contractor, international organization, and licensed facility.

  17. Paper Number 15736-PA Title Reaction Kinetics of Fuel Formation for In-Situ Combustion

    E-Print Network [OSTI]

    Abu-Khamsin, Sidqi

    Paper Number 15736-PA Title Reaction Kinetics of Fuel Formation for In-Situ Combustion Authors Abu believed to cause fuel formation for in-situ combustion have been studied and modeled. A thin, packed bed the approach of a combustion front. Analysis of gases produced from the reaction cell revealed that pyrolysis

  18. Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

    SciTech Connect (OSTI)

    Stickney, R.G.

    1998-04-29

    This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

  19. National Defense Authorization Act for Fiscal Year 1993 (PL 102...

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

    National Defense Authorization Act for Fiscal Year 1993 (PL 102-484) National Defense Authorization Act for Fiscal Year 1993 (PL 102-484) Section 3162 of the National Defense...

  20. Authoring Large and Complex Hypertext with Reusable Components 

    E-Print Network [OSTI]

    Park, Yung Ah

    2011-10-21

    from Petri net theory to select, categorize, and modify existing net fragments as building blocks for composing larger networks. Authors may switch modes between visual and textual authoring at will, thus combining the strengths of expressing large nets...

  1. Children’s story authoring with Propp’s morphology 

    E-Print Network [OSTI]

    Hammond, Sean Paul

    2011-06-30

    This thesis applies concepts from Vladimir Propp’s model of the narrative structure of fairy tales (Propp’s morphology) to a story authoring tool for children. A computer story authoring application based on Propp’s ...

  2. Bounds on Some Ramsey Numbers Involving Quadrilateral +

    E-Print Network [OSTI]

    Radziszowski, Stanislaw P.

    Bounds on Some Ramsey Numbers Involving Quadrilateral + Xiaodong Xu Guangxi Academy of Sciences@cs.rit.edu Abstract. For graphs G 1 , G 2 , · · · , Gm , the Ramsey number R(G 1 , G 2 , · · · , Gm ) is defined Ramsey numbers involving quadrilateral C 4 , including R(C 4 , K 9 ) # 32, 19 # R(C 4 , C 4 , K 4 ) # 22

  3. Fort Pierce Utilities Authority- Solar Water Heating Rebate

    Office of Energy Efficiency and Renewable Energy (EERE)

    Note: Fort Pierce Utilities Authority has completed its rebate program for 2015. Check the website for updates.

  4. Author's personal copy Physica D 239 (2010) 15271541

    E-Print Network [OSTI]

    Froyland, Gary

    2010-01-01

    particles is completely determined Corresponding author. Tel.: +61 2 9385 7050; fax: +61 2 9385 7123. E

  5. Predicting landfalling hurricane numbers from basin hurricane numbers: basic statistical analysis

    E-Print Network [OSTI]

    Laepple, T; Penzer, J; Bellone, E; Nzerem, K; Laepple, Thomas; Jewson, Stephen; Penzer, Jeremy; Bellone, Enrica; Nzerem, Kechi

    2007-01-01

    One possible method for predicting landfalling hurricane numbers is to first predict the number of hurricanes in the basin and then convert that prediction to a prediction of landfalling hurricane numbers using an estimated proportion. Should this work better than just predicting landfalling hurricane numbers directly? We perform a basic statistical analysis of this question in the context of a simple abstract model.

  6. Harmonic resolution as a holographic quantum number

    E-Print Network [OSTI]

    Bousso, Raphael

    2009-01-01

    LBNL- 57239 Harmonic resolution as a holographic quantumhep-th/0310223 UCB-PTH-03/26 Harmonic resolution as aquantum number, the harmonic resolution K. The Bekenstein

  7. REFINED BOUNDS ON THE NUMBER OF CONNECTED ...

    E-Print Network [OSTI]

    2011-04-06

    Apr 6, 2011 ... Smith inequality (see Theorem 2.5) a bound on the number of semi- ... then using Smith inequality, have been used before in several different ...

  8. Call Numbers** A, B, C 3rd

    E-Print Network [OSTI]

    Saldin, Dilano

    Call Numbers** A, B, C 3rd Floor Southeast . D, E, F, G, H, J, K, L 3rd Floor West . . . . . P 3rd Floor West . Q, R

  9. Numbers, proof and 'all that jazz'.

    E-Print Network [OSTI]

    2007-01-08

    CHAPTER 1. Numbers, proof and 'all that jazz'. There is a fundamental difference between mathematics and other sciences. In most sciences, one does ...

  10. Legal Authority 1 Export Administration Regulations EARB 298 -October 2001

    E-Print Network [OSTI]

    Bernstein, Daniel

    Legal Authority 1 Export Administration Regulations EARB 298 - October 2001 Part I PRINCIPAL STATUTORY AUTHORITY FOR THE EXPORT ADMINISTRATION REGULATIONS #12;Legal Authority 2 1 The Act expired Presidential notices, continued in effect the provisions of the Export Administration Regulations. The Act

  11. A Thermodynamic Classification of Real Numbers

    E-Print Network [OSTI]

    Thomas Garrity

    2009-03-15

    A new classification scheme for real numbers is given, motivated by ideas from statistical mechanics in general and work of Knauf and of Fiala and Kleban in particular. Critical for this classification of a real number will be the Diophantine properties of its continued fraction expansion.

  12. Circular Chromatic Ramsey Number Kyle F. Jao

    E-Print Network [OSTI]

    West, Douglas B.

    Circular Chromatic Ramsey Number Kyle F. Jao , Claude Tardif , Douglas B. West , Xuding Zhu, the circular chromatic Ramsey number Rc (F, G) is the infimum of c(H) over graphs H such that every red of a Ramsey problem for the families of homomorphic images of F and G. Letting zk = 3 - 2-k, we prove that zk

  13. 2001 TRAFFIC ZONE BOUNDARIES Zone Numbers

    E-Print Network [OSTI]

    Toronto, University of

    2001 TRAFFIC ZONE BOUNDARIES Zone Numbers & Detailed Definitions #12;2001 TRAFFIC ZONE BOUNDARIES of Toronto Joint Program in Transportation January 2003 #12;PREFACE This report presents the 2001 traffic zone numbers by local municipalities in the 2001 TTS survey area. The second part presents detailed

  14. Real numbers and other completions Fred Richman

    E-Print Network [OSTI]

    Richman, Fred

    Real numbers and other completions Fred Richman Florida Atlantic University Boca Raton, FL 33431 11 March 2007 Abstract A notion of completeness and completion suitable for use in the absence of countable choice is developed. This encompasses the con- struction of the real numbers as well as the completion

  15. Company number 5857955 Wellcome Trust Finance plc

    E-Print Network [OSTI]

    Rambaut, Andrew

    Company number 5857955 Wellcome Trust Finance plc Annual Report and Financial Statements Year ended 30 September 2012 #12;Company number 5857955 Wellcome Trust Finance plc Contents Page Directors Trust Finance plc Directors' Report for the year ended 30 September 2012 Report of the Directors

  16. Company number 5857955 Wellcome Trust Finance plc

    E-Print Network [OSTI]

    Rambaut, Andrew

    Company number 5857955 Wellcome Trust Finance plc Annual Report and Financial Statements Year ended 30 September 2013 #12;Company number 5857955 Wellcome Trust Finance plc Contents Page Directors Trust Finance plc Directors' Report For the year ended 30 September 2013 Report of the Directors

  17. RNG: A Practitioner's Overview Random Number Generation

    E-Print Network [OSTI]

    Mascagni, Michael

    -Kac/path integral methods to solve partial differential equations with random walks Defense: neutronics, nuclear random numbers 1. Each calculation is a numerical experiment Subject to known and unknown sources a calculation with the same numbers Across different machines (modulo arithmetic issues) Parallel

  18. Resolution-Stationary Random Number Generators

    E-Print Network [OSTI]

    L'Ecuyer, Pierre

    of successive output values over their entire period length. For F2-linear generators, the commonly adopted efficient ways of implementing high-quality and long-period Tausworthe generators. Key words: random number un [0, 1) is the output of the generator at step n and the number of bits in this output, L

  19. enter part number BNC / RP-BNC

    E-Print Network [OSTI]

    Berns, Hans-Gerd

    enter part number Products 7/16 1.0/2.3 1.6/5.6 AFI AMC BNC / RP-BNC C FAKRA SMB FME HN MCX Mini ------- Product Search ------- Inventory Search Search Results for: 31-10152-RFX Results: 1 - 1 of 1 Part Number. All rights reserved. Copyright | Terms & Conditions | RF E-Mail Client | Contact Us | Amphenol

  20. Ramsey numbers and adiabatic quantum computing

    E-Print Network [OSTI]

    Frank Gaitan; Lane Clark

    2012-01-08

    The graph-theoretic Ramsey numbers are notoriously difficult to calculate. In fact, for the two-color Ramsey numbers $R(m,n)$ with $m,n\\geq 3$, only nine are currently known. We present a quantum algorithm for the computation of the Ramsey numbers $R(m,n)$. We show how the computation of $R(m,n)$ can be mapped to a combinatorial optimization problem whose solution can be found using adiabatic quantum evolution. We numerically simulate this adiabatic quantum algorithm and show that it correctly determines the Ramsey numbers R(3,3) and R(2,s) for $5\\leq s\\leq 7$. We then discuss the algorithm's experimental implementation, and close by showing that Ramsey number computation belongs to the quantum complexity class QMA.

  1. A. b. K.Kis Ris-M-Ll^li Titie and author(s)

    E-Print Network [OSTI]

    51 01, ezt. 334, telex: 5072. Date Department or group Reactor Phj sies Group's own registration numbers) Copies to Abstract to #12;CONTENTS Page 1. Introduction 1 2. The Physical Principles of Flux Several reactor physics problems involve three-dimensional neutron flux calculations. The classical

  2. A. E. K. Ris Ris-M-[ 1U07 Title and author(s)

    E-Print Network [OSTI]

    -+- 7 illustrations Date Department or group Reactor Physics Department Group's own registration numbers) Abstract A method for treating heterogeneities in diffusion calculations for a reactor is de- scribed.2. Principles of the Monte Carlo Calculation ... 5 2.3. The Monte Carlo Program MOVAX 8 2.3.1. Data Input 8 2

  3. On the Cofinality of Ultrapowers Author(s): Andreas Blass and Heike Mildenberger

    E-Print Network [OSTI]

    Mildenberger, Heike

    archive indicates your acceptance of JSTOR's Terms and Conditions of Use, available at http://www.jstor.org/page/info the discovery and use of these resources. For more information about JSTOR, please contact support restrictions on the possible cofinalities of ultrapowers of the natural numbers with respect to ultrafilters

  4. Position Number: (Assigned when added to Library)

    E-Print Network [OSTI]

    California at Davis, University of

    Position Number: (Assigned when added to Library) 02016240 Dept: INST OF TRANSPORTATION STUDIES distributions to social media and trade media. 20% WEBSITE, SOCIAL MEDIA AND MEDIA MONITORING Monitor trends

  5. Polygonal Numbers, Primes and Ternary Quadratic Forms

    E-Print Network [OSTI]

    Sun, Zhi-Wei

    Polygonal Numbers, Primes and Ternary Quadratic Forms Zhi-Wei Sun Nanjing University Nanjing 210093 three papers: Z. W. Sun [Acta Arith. 2007], S. Guo, H. Pan & Z. W. Sun [Integers, 2007], and B. K. Oh

  6. High speed optical quantum random number generation

    E-Print Network [OSTI]

    Weinfurter, Harald

    High speed optical quantum random number generation Martin F¨urst1,2,, Henning Weier1,2, Sebastian/publicationFile/30276/ais20 pdf.pdf (1999). 2. "Fips 140-2, security requirements for cryptographic modules

  7. Unpredictability and the transmission of numbers

    E-Print Network [OSTI]

    Myers, John M

    2015-01-01

    Curiously overlooked in physics is its dependence on the transmission of numbers. For example the transmission of numerical clock readings is implicit in the concept of a coordinate system. The transmission of numbers and other logical distinctions is often achieved over a computer-mediated communications network in the face of an unpredictable environment. By unpredictable we mean something stronger than the spread of probabilities over given possible outcomes, namely an opening to unforeseeable possibilities. Unpredictability, until now overlooked in theoretical physics, makes the transmission of numbers interesting. Based on recent proofs within quantum theory that provide a theoretical foundation to unpredictability, here we show how regularities in physics rest on a background of channels over which numbers are transmitted. As is known to engineers of digital communications, numerical transmissions depend on coordination reminiscent of the cycle of throwing and catching by players tossing a ball back and...

  8. Department.: Music Department Course number: 210W

    E-Print Network [OSTI]

    Alpay, S. Pamir

    Department.: Music Department Course number: 210W Course title: Music, History, and Ideas Credits: 3 Contact Person: Alain Frogley Catalog Copy: MUSI 210W. Music, History, and Ideas Either semester

  9. Department.: Psychology Course Number: PSYC 210W

    E-Print Network [OSTI]

    Alpay, S. Pamir

    Department.: Psychology Course Number: PSYC 210W Course Title: Lab in Cognition Credits: 3 Contact in these experiments, the writing assignments provide a richer and fuller of the nature of psychological inquiry

  10. Department.: Psychology Course Number: PSYC 244W

    E-Print Network [OSTI]

    Alpay, S. Pamir

    Department.: Psychology Course Number: PSYC 244W Course Title: Laboratory in Personality Credits: 3 Psychological Association. The total report is at least 15 pages in length. The final report is the primary

  11. Department.: Psychology Course Number: PSYC 263W

    E-Print Network [OSTI]

    Alpay, S. Pamir

    Department.: Psychology Course Number: PSYC 263W Course Title: Laboratory in Animal Learning or 253 , and consent of instructor; ENGL 105 or 110 or 111 or 250 . W Criteria: Psychology 263W is a lab

  12. Student ID (R) Number ________________________ Semester/Year______ ________________________

    E-Print Network [OSTI]

    Rock, Chris

    Student ID (R) Number ________________________ Semester/Year______ ________________________ THIRD: ______________________________________________________ CHECK ALL THAT APPLY: _____First-time Third Party Student _____TTU Campus Student _____Non sponsor and the Third Party Sponsor Agreement prior to the due date to ensure timely posting of third

  13. Computing the Betti Numbers of Arrangements

    E-Print Network [OSTI]

    2015-08-29

    To our knowledge ... on ?. Categories and Subject Descriptors ... sets defined in terms of such hypersurfaces can be topolog- ... The first bounds on the individual Betti numbers of semi- .... The idea of using filtrations for computing Betti num-.

  14. LLW Notes, Volume 12, Number 4

    SciTech Connect (OSTI)

    Norris, C.; Brown, H.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

    1997-04-01

    Contents include articles entitled: Texas Authority`s funding pending before conference committee: Auditor`s report favors authority; Revisions likely for Illinois siting law; Midwest Compact votes on Ohio fundings: Less approved than requested; Walter Sturgeon named executive director of North Carolina authority; New forum participant for Massachusetts; CRCPD holds fifth workshop for LLRW regulators; DOD generators hold annual meeting; State legislators` LLRW working group meets; NRC Chairman Jackson responds to proposal to amend the Policy Act; US Ecology uses to recover costs and lost profits and/or to compel Ward Valley land transfer; New suit against Envirocare and others alleges unlawful business practices; Federal court finds line-item veto unconstitutional; States/utilities seek to escrow nuclear waste payments; High-level waste bill passes Senate; NRC releases decommissioning rule; EPA Region VI re La Paz Agreement; EPA, NRC debate NRC`s decommissioning rule: No progress re approaches to risk harmonization; and Mousseau heads DOE`s national low-level waste management program.

  15. Dynamical real numbers and living systems

    E-Print Network [OSTI]

    Dhurjati Prasad Datta

    2010-01-11

    Recently uncovered second derivative discontinuous solutions of the simplest linear ordinary differential equation define not only an nonstandard extension of the framework of the ordinary calculus, but also provide a dynamical representation of the ordinary real number system. Every real number can be visualized as a living cell -like structure, endowed with a definite evolutionary arrow. We discuss the relevance of this extended calculus in the study of living systems. We also present an intelligent version of the Newton's first law of motion.

  16. RCRA (Resource Conservation and Recovery Act) final authorization guidance manual

    SciTech Connect (OSTI)

    Not Available

    1983-06-10

    The document provides guidance regarding final authorization of State Hazardous Waste programs for the pre-HSWA RCRA program. The manual establishes a process and schedule for State Authorization applications, and provides detailed guidance on what State programs must contain in order to qualify for final authorization. The primary audience is U.S. EPA Headquarters and Regional offices and also State agencies, but public requests have also been received so they are included in that broad audience.

  17. 16 USC 797a - Congressional Authorization for Projects Within...

    Open Energy Info (EERE)

    16 USC 797a - Congressional Authorization for Projects Within National Parks or Monuments Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document-...

  18. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    Valley Authority, Knoxville, TN (United States)","20 FOSSIL-FUELED POWER PLANTS; 32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATION; 42 ENGINEERING NOT INCLUDED IN OTHER...

  19. Control and Accountability of Nuclear Materials: Responsibilities and Authorities

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

    1992-09-23

    The order prescribes the Department of Energy (DOE) policies, responsibilities, and authorities for control and accountability of nuclear materials. Cancels DOE O 5633.2.

  20. Oklahoma Municipal Power Authority- WISE Energy Efficiency Loan Program

    Broader source: Energy.gov [DOE]

    The Oklahoma Municipal Power Authority (OMPA) offers loans for a variety of measures and equipment through its WISE Loan Program. This program encourages residential and commercial customers to...

  1. National Defense Authorization Act for Fiscal Year 2000 § 3164...

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

    Scope: Section 3164 of the National Defense Authorization Act for Fiscal Year 2000 implements a whistleblower protection program to ensure that covered individuals may...

  2. Chapter VII Appendix D FEDERAL EMERGENCY AUTHORITIES AND POLICY...

    Office of Environmental Management (EM)

    Gasoline Supply Reserve, and provides for the presidentially directed drawdown of the reserves through the Secretary of Energy. It also authorizes the Secretary of Energy to...

  3. Applications for Change or Transfer of Control of Authorizations...

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

    Applicants for authorization to import or export natural gas, including liquefied natural gas (LNG), apply on behalf of a given entity, whose corporate structure and place of...

  4. Excepted Service Authorities for EJ and EK Pay Plans

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

    2012-03-30

    The order establishes requirements and responsibilities for the employment and compensation of individuals when using DOE excepted service authorities. Admin Chg 1 dated 6-20-12.

  5. Title 10 CFR 900 Coordination of Federal Authorizations for Electric...

    Open Energy Info (EERE)

    Title 10 CFR 900 Coordination of Federal Authorizations for Electric Transmission Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document-...

  6. Kissimmee Utility Authority- Commercial Energy Efficiency Rebate Program

    Broader source: Energy.gov [DOE]

    Kissimmee Utility Authority (KUA) offers several rebates to commercial customers for energy efficiency improvements. Rebates are available for HVAC maintenance, heat pumps, duct leak repairs,...

  7. Acronyms A AAAP Accelerated Access Authorization Program ACREM...

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

    12 I IAA Interim Access Authorization ICAM Identity, Credential, and Access Management IEA Office of Independent Enterprise Assessments IG Inspector General IN Office of...

  8. Author's personal copy Large deformation and electrochemistry of polyelectrolyte gels

    E-Print Network [OSTI]

    Hong, Wei

    Author's personal copy Large deformation and electrochemistry of polyelectrolyte gels Wei Hong and electrochemistry. A specific material model is described, including the effects of stretching the network, mixing

  9. National Defense Authorization Act for Fiscal Year 2005, Information...

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

    Section 3116 from "National Defense Authorization Act for Fiscal Year 2005" (Public Law 108-375 Oct. 28 2004) Transition20082009EMAdditionalMaterialMACopy.pdf PUBLIC LAW...

  10. Oklahoma Municipal Power Authority- Commercial and Industrial Energy Efficiency Program

    Broader source: Energy.gov [DOE]

    The Oklahoma Municipal Power Authority (OMPA) offers the Demand and Energy Efficiency Program (DEEP) to eligible commercial, industrial, and municipal government customers served by OMPA. This...

  11. Energy Department Authorizes Additional Volume at Proposed Freeport...

    Energy Savers [EERE]

    Additional Volume at Proposed Freeport LNG Facility to Export Liquefied Natural Gas Energy Department Authorizes Additional Volume at Proposed Freeport LNG Facility to Export...

  12. Energy Department Authorizes Second Proposed Facility to Export...

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

    - The Energy Department announced today that it has conditionally authorized Freeport LNG Expansion, L.P. and FLNG Liquefaction, LLC (Freeport) to export domestically produced...

  13. Energy Department Authorizes American LNG Marketing LLC's Application...

    Energy Savers [EERE]

    American LNG Marketing LLC's Application to Export Liquefied Natural Gas Energy Department Authorizes American LNG Marketing LLC's Application to Export Liquefied Natural Gas...

  14. Energy Department Authorizes Alaska LNG Project, LLC to Export...

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

    Department announced today that it has issued a conditional authorization for the Alaska LNG Project, LLC (Alaska LNG) to export domestically produced liquefied natural gas (LNG)...

  15. Energy Department Authorizes Dominion's Proposed Cove Point Facility...

    Office of Environmental Management (EM)

    Department announced today that it has conditionally authorized Dominion Cove Point LNG, LP to export domestically produced liquefied natural gas (LNG) to countries that do...

  16. Energy Department Conditionally Authorizes Cameron LNG to Export...

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

    Cameron LNG to Export Liquefied Natural Gas Energy Department Conditionally Authorizes Cameron LNG to Export Liquefied Natural Gas February 11, 2014 - 11:15am Addthis WASHINGTON -...

  17. Energy Department Conditionally Authorizes Oregon LNG to Export...

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

    WASHINGTON - The Energy Department announced today that it has conditionally authorized LNG Development Co., LLC (Oregon LNG) to export domestically produced liquefied natural gas...

  18. DOE Replies Support NRC Commissioners and Authority to Withdraw...

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

    that the arguments that it lacked authority to withdraw the pending Yucca Mountain license application are uniformly without merit. DOE's reply brief is available here. In a...

  19. Notice of Termination for Authorization under TPDES General Permit...

    Open Energy Info (EERE)

    Termination for Authorization under TPDES General Permit (TXR150000) Jump to: navigation, search OpenEI Reference LibraryAdd to library Reference: Notice of Termination for...

  20. National Training and Education Resource Authoring Course Participant...

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

    adding questions to the pool as needed. Begin a glossary and continue adding terms to the glossary as needed. NTER Authoring Participant Guide (012012 pw) 10 LOGIN To...

  1. Listing of DOE/FE Authorizations Issued in 2015 | Department...

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

    Stabilis Energy Services LLC Modification to include Agency Rights Errata 3563 14-175-NG 010815 MPower Energy LLC Modification to increase requested authority Errata 3521...

  2. NMOCD - Form G-104 - Certificate of Compliance and Authorization...

    Open Energy Info (EERE)

    Resources Author State of New Mexico Energy and Minerals Department Published New Mexico Oil Conservation Division, 1978 DOI Not Provided Check for DOI availability: http:...

  3. Santa Clara Valley Transportation Authority and San Mateo County...

    Energy Savers [EERE]

    Santa Clara Valley Transportation Authority and San Mateo County Transit District Fuel Cell Transit Buses: Preliminary Evaluation Results vtaprelimevalresults.pdf More...

  4. Presidential Permits and Export Authorizations - About the Program...

    Office of Environmental Management (EM)

    electric energy to foreign countries. The authority to grant Presidential permits is derived from the constitutional power of the President to protect the territorial integrity...

  5. Matrix Online Characteristic Number and Its applications in Goldbach Conjecture,Polignac Conjecture,the Twin Prime Conjecture

    E-Print Network [OSTI]

    Baoshan Zhang

    2013-06-11

    This article consists of three chapters.In Chapter 1, it is determined by the consecutive odd numbers, and study to the intrinsic properties of a class of matrix sequence. Through the establishment of matrix online number concept, characteristics and the online number column use mathematical induction to prove the some properties of this kind of matrix on the number of online features (Theorem 1). Finally, it is given a trial to prove the Goldbach conjecture (Theorem 6). This is the author in the years to explore prime properties in the process of research and discovery, and believe that this finding is of great significance.In Chapter 2, it is defined the concepts of matrix master characteristic number and the Matrix Master Characteristic Sequence (Definition 1). Firstly, we prove that any even number can be expressed as for the difference of two odd prime numbers at least two groups (Theorem 4). Secondly, we prove that there are infinitely many odd prime numbers separated by four (Theorem 9). Finally, we prove that if there is greater than 1 in the intersection by S(3) and s(2m+3) for any natural number m, so that there are infinitely many odd prime numbers separated by 2m(Theorem11). The results will undoubtedly promote the research for Polignac conjecture.In Chapter 3, mainly as a result of any odd natural number a, the intersection by S(a) and s(a+2) is not empty number set, and there are far more than 1 number in the set, where S(a)={k,If 2k+a be prime as k be natural number},and P is a prime number set, N is natural number set. we prove that there are an infinite number of twin prime, and then solve the problem of the twin primes in number theory.

  6. True random numbers from amplified quantum vacuum

    E-Print Network [OSTI]

    M. Jofre; M. Curty; F. Steinlechner; G. Anzolin; J. P. Torres; M. W. Mitchell; V. Pruneri

    2011-10-17

    Random numbers are essential for applications ranging from secure communications to numerical simulation and quantitative finance. Algorithms can rapidly produce pseudo-random outcomes, series of numbers that mimic most properties of true random numbers while quantum random number generators (QRNGs) exploit intrinsic quantum randomness to produce true random numbers. Single-photon QRNGs are conceptually simple but produce few random bits per detection. In contrast, vacuum fluctuations are a vast resource for QRNGs: they are broad-band and thus can encode many random bits per second. Direct recording of vacuum fluctuations is possible, but requires shot-noise-limited detectors, at the cost of bandwidth. We demonstrate efficient conversion of vacuum fluctuations to true random bits using optical amplification of vacuum and interferometry. Using commercially-available optical components we demonstrate a QRNG at a bit rate of 1.11 Gbps. The proposed scheme has the potential to be extended to 10 Gbps and even up to 100 Gbps by taking advantage of high speed modulation sources and detectors for optical fiber telecommunication devices.

  7. Unpredictability and the transmission of numbers

    E-Print Network [OSTI]

    John M. Myers; F. Hadi Madjid

    2015-08-05

    Curiously overlooked in physics is its dependence on the transmission of numbers. For example the transmission of numerical clock readings is implicit in the concept of a coordinate system. The transmission of numbers and other logical distinctions is often achieved over a computer-mediated communications network in the face of an unpredictable environment. By unpredictable we mean something stronger than the spread of probabilities over given possible outcomes, namely an opening to unforeseeable possibilities. Unpredictability, until now overlooked in theoretical physics, makes the transmission of numbers interesting. Based on recent proofs within quantum theory that provide a theoretical foundation to unpredictability, here we show how regularities in physics rest on a background of channels over which numbers are transmitted. As is known to engineers of digital communications, numerical transmissions depend on coordination reminiscent of the cycle of throwing and catching by players tossing a ball back and forth. In digital communications, the players are computers, and the required coordination involves unpredictably adjusting "live clocks" that step these computers through phases of a cycle. We show how this phasing, which we call `logical synchronization,' constrains number-carrying networks, and, if a spacetime manifold in invoked, put "stripes" on spacetime. Via its logically synchronized channels, a network of live clocks serves as a reference against which to locate events. Such a network in any case underpins a coordinate frame, and in some cases the direct use of a network can be tailored to investigate an unpredictable environment. Examples include explorations of gravitational variations near Earth.

  8. On Going TRU Waste Disposition

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  9. On Going TRU Waste Disposition

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

    The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

  10. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    that address key functional areas of project management, engineering and design, safety, environment, security, and quality assurance, grouped by each specific CD phase. This...

  11. disposition | National Nuclear Security Administration

    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 RegisterStorm1 3446 YEAR/%2A en

  12. Disposition Schedules | 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: Alternative Fuels Data Center HomeVehicleDepartment ofGraphics » DOEDisposition Schedules

  13. State Program Advisory Number 8. Directive (Final)

    SciTech Connect (OSTI)

    Not Available

    1991-03-01

    The directive discusses State and Regional Programs Branch, which has periodically issued State Programs Advisories (SPAs) to update the 'State Consolidated Authorization Manual' (SCRAM) as new RCRA program policies, regulations, and self-implementing statutory provisions come into effect. Since the SCRAM was recently replaced by the State Authorization Manual (SAM) which includes RCRA program changes through 6/30/89, current SPAs (SPA 8 and higher) will now update the SAM. SPA 8, covers RCRA program changes for the period 7/1/89 - 12/31/89. Included are 7 new revision checklists, model Attorney General's Statement language for the changes covered by the SPA, and other revised materials. A revision to the First Third Scheduled Wastes is included here. SPA 8 introduces Revision Checklist 70 which covers changes to Part 124 which were inadvertently not included as checklists in previous guidance.

  14. Power and Water Resources Pooling Authority NOTICE OF SPECIAL MEETING

    E-Print Network [OSTI]

    Power and Water Resources Pooling Authority NOTICE OF SPECIAL MEETING Notice is hereby given that a special meeting of the Board of Directors of the Power and Water Resources Pooling Authority (PWRPA or service at least 3 days before the meeting. Requests should be sent to: Power and Water Resources Pooling

  15. Export Administration Regulations EARB 298 -October 2001 LEGAL AUTHORITY

    E-Print Network [OSTI]

    Bernstein, Daniel

    omitted text. PART I Principal Statutory Authority 1. Export Administration Act of 1979, as amended (Pub) . . . . . . . . . . . . 69 PART II Executive Orders and Other Presidential Documents Relevant to Part I Statutory Authorities 1. E.O. 12002 - Administration of the Export Administration Act of 1969, as amended (42 FR 35623; 3

  16. Web authoring principles Deborah Cross, ANU Web Coordinator

    E-Print Network [OSTI]

    Web authoring principles Deborah Cross, ANU Web Coordinator ANU Marketing Office #12;Remembering today's session · All tips available in the web style guide at styles.anu.edu.au/guide/author.php · Contact your local web manager · Contact the ANU web team via webstyle@anu.edu.au 2 #12;3 Possible

  17. A Pedagogical Interface for Authoring Adaptive e-Learning Courses

    E-Print Network [OSTI]

    Lau, W. H. Nynson

    different approaches towards learning. In light of this, adaptive educational hypermedia systems (AEHSsA Pedagogical Interface for Authoring Adaptive e-Learning Courses Christopher Watson1 Frederick W to support adaptive e-learning course authoring for different types of students. They require teachers

  18. A Subject-Delegated Decryption Scheme with "Tightly" Limited Authority

    E-Print Network [OSTI]

    International Association for Cryptologic Research (IACR)

    A Subject-Delegated Decryption Scheme with "Tightly" Limited Authority Lihua Wang1 , Takeshi@cs.tsukuba.ac.jp Abstract. In this paper, we present a new proxy cryptosystem named subject-delegated decryption scheme subjects. The advantage of our scheme is that the proxy authorities are tightly limited ("Tightly" Limited

  19. A Web-based Animation Authoring Application for Quadrupedal Characters 

    E-Print Network [OSTI]

    Murphy, Krista Lea

    2014-12-03

    AUTHORING APPLICATION FOR QUADRUPEDAL CHARACTERS A Thesis by KRISTA LEA MURPHY Submitted to the Office of Graduate and Professional Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Chair... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.2 Contributions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2. BACKGROUND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.1 Methods for Authoring Animation . . . . . . . . . . . . . . . . . . . . 3 2...

  20. 2008 The Authors Journal Compilation 2008 Blackwell Publishing Ltd

    E-Print Network [OSTI]

    Troch, Peter

    © 2008 The Authors Journal Compilation © 2008 Blackwell Publishing Ltd Geography Compass 2 (2008 and Water Resources, University of Arizona Abstract Predictions of hydrologic system response to natural some threshold #12;2 Landscape heterogeneity and hydrological theory © 2008 The Authors Geography