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Sample records for mox gold supplier

  1. MOX

    National Nuclear Security Administration (NNSA)

    as MOX fuel will be significantly more expensive than anticipated. Given a lifecycle cost estimate for the program of approximately 30 billion or more and a challenging budget...

  2. All About MOX

    ScienceCinema (OSTI)

    None

    2014-08-06

    In 1999, the Nuclear Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

  3. Strong Support for MOX Continues

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

    When completed, the MOX facility will convert weapons- grade plutonium to nuclear reactor fuel assemblies. These assemblies will then be used as fuel in commercial nuclear power ...

  4. Environmental Excellence Program Recognizes MOX Services | National...

    National Nuclear Security Administration (NNSA)

    of NNSA's Mixed Oxide (MOX) Fuel Fabrication Facility at the Savannah River Site. ... The MOX Fuel Fabrication Facility, currently under construction at the Savannah River Site ...

  5. PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX

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

    . ,-) ')7 73?¥i5": )~"'f"YC-:;'~dt?f(~"'f9'FrrZ , . PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX Services Unclassified Information System Template - January 30, 2009, Version 2 Department of Energy Privacy Impact Assessment (pIA) Guidance is provided in the template. See DOE Order 206.1, Department of Energy Privacy Program, Appendix A, Privacy Impact Assessments, for requirements and additional guidance for conducting a PIA:

  6. MOX | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    MOX Mixed Oxide (MOX) Fuel Fabrication Facility Documents related to the project: Plutonium Disposition Study Options Independent Assessment Phase 1 Report, April 13, 2015 Plutonium Disposition Study Options Independent Assessment Phase 2 Report, August 20, 2015 Final Report of the Plutonium Disposition Red Team, August 13, 2015 Commentary on... Analysis of Surplus Weapons-Grade Plutonium Disposition Options The Administration remains firmly committed to disposing of surplus weapon-grade

  7. Over 9600 Small Business Subcontracts Critical to the Success...

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

    Wise was recognized as a 2012 MOX Gold Supplier during a special presentation in Dayton. Bottom: Byers Precision Fabricators was recognized as a 2012 MOX Gold Supplier during a ...

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

    Office of Environmental Management (EM)

    ... Wise was recognized as a 2012 MOX Gold Supplier during a special presentation in Dayton. Bottom: Byers Precision Fabricators was recognized as a 2012 MOX Gold Supplier during a ...

  9. Adequate NQA-1 Suppliers

    Office of Environmental Management (EM)

    Issuance of the Office of Environmental Management Nuclear Supplier Alert System The Office of ... Distribution includes the DOE Ofl'lce of Health, Safety and Security (HSS) with ...

  10. Guidelines for Supplier, Vendor Shows

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

    Guidelines for Supplier, Vendor Shows Guidelines for SupplierVendor or Professional Local Trade FairsShows As a premier national research and development laboratory, LANL seeks...

  11. Adequate NQA-1 Suppliers

    Broader source: Energy.gov [DOE]

    Scope of Project Milestone Task 2.6: Request the procedures used for qualifying nuclear grade suppliers from each major EM contractor and evaluate the procedures to determine the level of...

  12. MOX Reprocessing at Tokai Reprocessing Plant

    SciTech Connect (OSTI)

    Taguchi, Katsuya; Nagaoka, Shinichi; Yamanaka, Atsushi; Nakamura, Yoshinobu; Omori, Eiichi; SATO, Takehiko; MIURA, Nobuyuki

    2007-07-01

    In March 2007, the first reprocessing of the 'Type B' MOX spent fuels of the Prototype Advanced Thermal Reactor FUGEN was initiated at Tokai Reprocessing Plant as a plant-scale demonstration of MOX fuel reprocessing. The operation was advanced satisfactorily and it has been confirmed that the MOX fuels as well as UO{sub 2} fuels can be reprocessed safely. Some characteristics of MOX fuels on reprocessing, such as properties of undissolved residue affecting the clarification process, are becoming visible. Reprocessing of the 'Type B' MOX fuels will be continued for several more years from now on, further investigations on solubility of fuels, characteristics of undissolved residues, progress of solvent degradation and so on will be continued. (authors)

  13. Actual Scale MOX Powder Mixing Test for MOX Fuel Fabrication Plant in Japan

    SciTech Connect (OSTI)

    Osaka, Shuichi; Kurita, Ichiro; Deguchi, Morimoto; Ito, Masanori; Goto, Masakazu

    2007-07-01

    Japan Nuclear Fuel Ltd. (hereafter, JNFL) promotes a program of constructing a MOX fuel fabrication plant (hereafter, J-MOX) to fabricate MOX fuels to be loaded in domestic light water reactors. Since Japanese fiscal year (hereafter, JFY) 1999, JNFL, to establish the technology for a smooth start-up and the stable operation of J-MOX, has executed an evaluation test for technology to be adopted at J-MOX. JNFL, based on a consideration that J-MOX fuel fabrication comes commercial scale production, decided an introduction of MIMAS technology into J-MOX main process, from powder mixing through pellet sintering, well recognized as mostly important to achieve good quality product of MOX fuel, since it achieves good results in both fuel production and actual reactor irradiation in Europe, but there is one difference that JNFL is going to use Japanese typical plutonium and uranium mixed oxide powder converted with the micro-wave heating direct de-nitration technology (hereafter, MH-MOX) but normal PuO{sub 2} of European MOX fuel fabricators. Therefore, in order to evaluate the suitability of the MH-MOX powder for the MIMAS process, JNFL manufactured small scale test equipment, and implemented a powder mixing evaluation test up until JFY 2003. As a result, the suitability of the MH-MOX powder for the MIMAS process was positively evaluated and confirmed It was followed by a five-years test named an 'actual test' from JFY 2003 to JFY 2007, which aims at demonstrating good operation and maintenance of process equipment as well as obtaining good quality of MOX fuel pellets. (authors)

  14. MOX Services Unclassified Information System PIA, National Nuclear Services

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

    Administration | Department of Energy MOX Services Unclassified Information System PIA, National Nuclear Services Administration MOX Services Unclassified Information System PIA, National Nuclear Services Administration MOX Services Unclassified Information System PIA, National Nuclear Services Administration MOX Services Unclassified Information System PIA, National Nuclear Services Administration (378.48 KB) More Documents & Publications TRAIN-PIA.pdf Occupational Medicine - Assistant

  15. NNSA B-Roll: MOX Facility

    SciTech Connect (OSTI)

    2010-05-21

    In 1999, the National Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

  16. NNSA B-Roll: MOX Facility

    ScienceCinema (OSTI)

    None

    2010-09-01

    In 1999, the National Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

  17. Supplier Toolbox | The Ames Laboratory

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

    Terms and Conditions Contractor Travel Policy Supplier Representations and Certifications Intellectual Property Clauses Bonds Cost Reimbursement Invoice Example Cost Share- Cost...

  18. Supplier Information Form Date: New Revision

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

    Supplier Information Form Date: New Revision Interested suppliers may complete and submit a Supplier Information Form to be included into LANS' vendor database. Suppliers are advised that there is no guarantee any solicitations or awards will be sent to Supplier by submitting a Supplier Information Form; however, in the event a solicitation is sent to the Supplier from an LANS Procurement Official, then a more formal quotation/offer may be required. Legal Business Name: D/B/A: (if applicable)

  19. Quality Procedure - Supplier Qualification | Department of Energy

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

    Supplier Qualification Quality Procedure - Supplier Qualification This procedure establishes the responsibilities and process for supplier qualification activities conducted by Environmental Management (EM) Headquarters (HQ) Office of Standards and Quality Assurance in accordance with EM-QA-001, Environmental Management Quality Assurance Program. Quality Procedure - Supplier Qualification (2.03 MB) More Documents & Publications Quality Procedure - Approved Suppliers List Quality Procedure -

  20. Tag: Suppliers | Y-12 National Security Complex

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

    Tag: Suppliers Displaying 1 - 10 of 38... Category: Suppliers Container Technologies Industries, LLC receives small business award CNS recently honored Container Technologies...

  1. MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR

    SciTech Connect (OSTI)

    G. S. Chang; M. Robel; W. J. Carmack; D. J. Utterbeck

    2006-06-01

    The treatment of spent fuel produced in nuclear power generation is one of the most important issues to both the nuclear community and the general public. One of the viable options to long-term geological disposal of spent fuel is to extract plutonium, minor actinides (MA), and potentially long-lived fission products from the spent fuel and transmute them into short-lived or stable radionuclides in currently operating light-water reactors (LWR), thus reducing the radiological toxicity of the nuclear waste stream. One of the challenges is to demonstrate that the burnup-dependent characteristic differences between Reactor-Grade Mixed Oxide (RG-MOX) fuel and RG-MOX fuel with MA Np-237 and Am 241 are minimal, particularly, the inert gas generation rate, such that the commercial MOX fuel experience base is applicable. Under the Advanced Fuel Cycle Initiative (AFCI), developmental fuel specimens in experimental assembly LWR-2 are being tested in the northwest (NW) I-24 irradiation position of the Advanced Test Reactor (ATR). The experiment uses MOX fuel test hardware, and contains capsules with MOX fuel consisting of mixed oxide manufactured fuel using reactor grade plutonium (RG-Pu) and mixed oxide manufactured fuel using RG-Pu with added Np/Am. This study will compare the fuel neutronics depletion characteristics of Case-1 RG-MOX and Case-2 RG-MOX with Np/Am.

  2. MOX Two-Year Construction Anniversary | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Two-Year Construction Anniversary MOX Two-Year Construction Anniversary MOX Two-Year Construction Anniversary In 1999, the National Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus

  3. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    2001-07-17

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

  4. Mox fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    2001-05-15

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

  5. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, Mark L.; Rosenstein, Richard G.

    1998-01-01

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

  6. MOX fuel arrangement for nuclear core

    DOE Patents [OSTI]

    Kantrowitz, M.L.; Rosenstein, R.G.

    1998-10-13

    In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

  7. Supplier Information Form | Argonne National Laboratory

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

    Supplier Information Form PDF icon SB_SIF_form_Rev_0110

  8. MOX recycling in GEN 3 + EPR Reactor homogeneous and stable full MOX core

    SciTech Connect (OSTI)

    Arslan, M.; Villele, E. de; Gauthier, J.C.; Marincic, A.

    2013-07-01

    In the case of the EPR (European Pressurized Reactor) reactor, 100% MOX core management is possible with simple design adaptations which are not significantly costly. 100% MOX core management offers several highly attractive advantages. First, it is possible to have the same plutonium content in all the rods of a fuel assembly instead of having rods with 3 different plutonium contents, as in MOX assemblies in current PWRs. Secondly, the full MOX core is more homogeneous. Thirdly, the stability of the core is significantly increased due to a large reduction in the Xe effect. Fourthly, there is a potential for the performance of the MOX fuel to match that of new high performance UO{sub 2} fuel (enrichment up to 4.95 %) in terms of increased burn up and cycle length. Fifthly, since there is only one plutonium content, the manufacturing costs are reduced. Sixthly, there is an increase in the operating margins of the reactor, and in the safety margins in accident conditions. The use of 100% MOX core will improve both utilisation of natural uranium resources and reductions in high level radioactive waste inventory.

  9. MOX Three-Year Construction Anniversary | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Three-Year Construction Anniversary August 1, 2010 marks the third year of successful construction at the Mixed Oxide (MOX) Fuel Fabrication Facility at the Savannah River Site near Aiken, SC. Shaw AREVA MOX Services, LLC is under contract with the National Nuclear Security Administration (NNSA) to design, build, and operate MOX Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium.

  10. Microsoft PowerPoint - MOX Adventure_Reactor Subcommittee_Tamara...

    National Nuclear Security Administration (NNSA)

    3 MOX Fuel - General MOX fuel pellets from former weapons plutonium Blend of 5% PuO 2 with 95% depleted UO 2 Like LEU fuel pellets, MOX fuel pellets are primarily ...

  11. NNSA Holds Groundbreaking at MOX Facility | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA's plutonium disposition program moved another step forward with the start of site preparation for its Mixed Oxide (MOX) Fuel Fabrication Facility at the Savannah River Site. ...

  12. Suppliers | Y-12 National Security Complex

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

    Suppliers Suppliers The Consolidated Nuclear Security Supply Chain Management department wants to alert suppliers to an active email scam involving request for quotations and issuance of purchase orders that purport to originate from CNS but are in fact fraudulent. Please see this important notice to our suppliers. We are committed to obtaining the best value in the products and services we purchase. We purchase environmentally friendly products, including those with reduced packaging and those

  13. Microsoft PowerPoint - MOX Adventure_Reactor Subcommittee_Tamara Reavis

    National Nuclear Security Administration (NNSA)

    MOX Adventure Tamara Reavis May 2015 Page 2 Overview of Presentation > Characteristics of MOX Fuel  MOX Fuel at Duke Energy  MOX Fuel and NMMSS Page 3 MOX Fuel - General  MOX fuel pellets from former weapons plutonium  Blend of ~5% PuO 2 with ~95% depleted UO 2  Like LEU fuel pellets, MOX fuel pellets are primarily uranium  Fission power comes primarily from plutonium (Pu 239 ) instead of uranium (U 235 )  Other than the material of the fuel pellets, MOX and uranium fuel

  14. The manufacture and performance of homogeneous microstructure SBR MOX fuel

    SciTech Connect (OSTI)

    Barker, Matthew A.; Stephenson, Keith; Weston, Rebecca

    2007-07-01

    In the early 1980's, British experience in the manufacture of mixed-oxide fast reactor fuel was used to develop a new thermal MOX manufacturing route called the Short Binder-less Route (SBR). Laboratory- scale development led to the manufacture of commercial PWR fuel in a small pilot plant, and the construction of the full-scale dual-line Sellafield MOX Plant (SMP). SMP's first MOX assemblies are now under irradiation. SBR MOX is manufactured with 100% co-milled feedstock, leading to a microstructure dominated by a solid solution of (U,Pu)O{sub 2} at the nominal enrichment. A comprehensive fuel performance research programme has demonstrated the benign performance of SBR MOX up to 54 MWd/kgHM. In particular, the homogeneous microstructure is believed to be instrumental in the favourable fission gas retention and PCI resistance properties. (authors)

  15. Feasibility Study of MOX Fuel Online Burnup Analysis

    SciTech Connect (OSTI)

    Dennis, M.L.; Usman, S.

    2006-07-01

    This research is an extension of well established Non-Destructive Analysis of UO fuel using gamma spectroscopy of Cs-137 and other related isotopes. Given the performance similarities between UO fuel and MOX fuel, investigations are underway to develop similar correlation for MOX. MOX fuel burnup and decay simulations are being performed using ORIGEN-ARP (Oak Ridge Isotope Generation and Depletion Code - Automatic Rapid Processing). Simulation results are being analyzed and will be used to determine performance specifications of a detection system for field applications. Analysis of isotopic activity from irradiated fuel will be used to develop correlations to determine burn-up and Plutonium content of MOX fuel. These results will be particularly useful in view of the recent interest in MOX fuel. (authors)

  16. UK mining invests, suppliers profit

    SciTech Connect (OSTI)

    2009-04-15

    In the midst of a major economic crisis in the United Kingdom, equipment suppliers have been reporting a number of considerable purchases by British coal mining companies. In December 2008, Liebherr-Great Britain delivered the first two of four Rq350 Litronic hydraulic excavators for use at the Broken Cross opencast coal site in Lanarkshire, Scotland. Ten Terex TR100 rigid haulers were delivered to the site in late 2008. Hatfield Colliery at Stainforth, South Yorkshire, has been reopened by PowerFuel. The main equipment for two longwall faces was supplied by Joy Mining Machinery UK Ltd. 2 photos.

  17. MOX Cross-Section Libraries for ORIGEN-ARP

    SciTech Connect (OSTI)

    Gauld, I.C.

    2003-07-01

    The use of mixed-oxide (MOX) fuel in commercial nuclear power reactors operated in Europe has expanded rapidly over the past decade. The predicted characteristics of MOX fuel such as the nuclide inventories, thermal power from decay heat, and radiation sources are required for design and safety evaluations, and can provide valuable information for non-destructive safeguards verification activities. This report describes the development of computational methods and cross-section libraries suitable for the analysis of irradiated MOX fuel with the widely-used and recognized ORIGEN-ARP isotope generation and depletion code of the SCALE (Standardized Computer Analyses for Licensing Evaluation) code system. The MOX libraries are designed to be used with the Automatic Rapid Processing (ARP) module of SCALE that interpolates appropriate values of the cross sections from a database of parameterized cross-section libraries to create a problem-dependent library for the burnup analysis. The methods in ORIGEN-ARP, originally designed for uranium-based fuels only, have been significantly upgraded to handle the larger number of interpolation parameters associated with MOX fuels. The new methods have been incorporated in a new version of the ARP code that can generate libraries for low-enriched uranium (LEU) and MOX fuel types. The MOX data libraries and interpolation algorithms in ORIGEN-ARP have been verified using a database of declared isotopic concentrations for 1042 European MOX fuel assemblies. The methods and data are validated using a numerical MOX fuel benchmark established by the Organization for Economic Cooperation and Development (OECD) Working Group on burnup credit and nuclide assay measurements for irradiated MOX fuel performed as part of the Belgonucleaire ARIANE International Program.

  18. Sandia National Laboratories: Working with Sandia: Current Suppliers

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

    Current Suppliers Construction Supplier Resources iSupplier iSupplier Account Manage your company profile within our iSupplier Portal How to manage your iSupplier Account Accounts Payable Accounts Payable Invoicing Process Contract Information Contract Information Construction/Facilities Construction/Facilities Contract Audit Contract Audit Economic Impact Economic Impact Current and Past News Scam Notice, July 2015 Suspect/Counterfeit Help Management iSupplier Account supreg@sandia.gov

  19. Energy Secretary Bodman Commends Key Milestone In MOX Program | Department

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

    of Energy Commends Key Milestone In MOX Program Energy Secretary Bodman Commends Key Milestone In MOX Program April 1, 2005 - 11:28am Addthis WASHINGTON, DC - In response to the Nuclear Regulatory Commission's (NRC) authorization of the construction of a U.S. Mixed-Oxide (MOX) Fuel Fabrication Facility at the Department of Energy's Savannah River Site in South Carolina, Secretary of Energy Samuel W. Bodman today released the following statement: "Issuing the permit for construction of a

  20. MOX Fuel Presentation to Duke Board of Directors

    National Nuclear Security Administration (NNSA)

    PuO 2 with 95% depleted UO 2 - Like LEU fuel pellets, MOX fuel pellets are primarily uranium * Fission power comes primarily from plutonium (Pu 239 ) instead of uranium (U 235 )...

  1. Oversight Scheduling and Operational Awareness at the Savannah River Site, March 2013

    Office of Environmental Management (EM)

    MOX Fuel Fabrication Facility | Department of Energy Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility January 3, 2013 - 10:38am Addthis Top: MOX Services President Kelly Trice, left, presents a certificate to Wise President and Owner David Abney and Wise Marketing Director Renee Abney. Wise was recognized as a 2012 MOX Gold Supplier during

  2. Over 9600 Small Business Subcontracts Critical to the Success of NNSA's

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

    MOX Fuel Fabrication Facility | Department of Energy Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility Over 9600 Small Business Subcontracts Critical to the Success of NNSA's MOX Fuel Fabrication Facility January 3, 2013 - 10:38am Addthis Top: MOX Services President Kelly Trice, left, presents a certificate to Wise President and Owner David Abney and Wise Marketing Director Renee Abney. Wise was recognized as a 2012 MOX Gold Supplier during

  3. An integrated approach for the verification of fresh mixed oxide fuel (MOX) assemblies at light water reactor MOX recycle reactors

    SciTech Connect (OSTI)

    Menlove, Howard O; Lee, Sang - Yoon

    2009-01-01

    This paper presents an integrated approach for the verification of mixed oxide (MOX) fuel assemblies prior to their being loaded into the reactor. There is a coupling of the verification approach that starts at the fuel fabrication plant and stops with the transfer of the assemblies into the thermal reactor. The key measurement points are at the output of the fuel fabrication plant, the receipt at the reactor site, and the storage in the water pool as fresh fuel. The IAEA currently has the capability to measure the MOX fuel assemblies at the output of the fuel fabrication plants using a passive neutron coincidence counting systems of the passive neutron collar (PNCL) type. Also. at the MOX reactor pool, the underwater coincidence counter (UWCC) has been developed to measure the MOX assemblies in the water. The UWCC measurement requires that the fuel assembly be lifted about two meters up in the storage rack to avoid interference from the fuel that is stored in the rack. This paper presents a new method to verify the MOX fuel assemblies that are in the storage rack without the necessity of moving the fuel. The detector system is called the Underwater MOX Verification System (UMVS). The integration and relationship of the three measurements systems is described.

  4. Important notice to suppliers | Y-12 National Security Complex

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

    notice to ... Important notice to suppliers The Consolidated Nuclear Security Supply Chain Management department wants to alert suppliers to an active email scam involving...

  5. Supplier Performance Evaluation and Rating System (SPEARS)

    SciTech Connect (OSTI)

    Oged, M.; Warner, D.; Gurbuz, E.

    1993-03-01

    The SSCL Magnet Quality Assurance Department has implemented a Supplier Performance Evaluation and Rating System (SPEARS) to assess supplier performance throughout the development and production stages of the SSCL program. The main objectives of SPEARS are to promote teamwork and recognize performance. This paper examines the current implementation of SPEARS. MSD QA supports the development and production of SSCsuperconducting magnets while implementing the requirements of DOE Order 5700.6C. The MSD QA program is based on the concept of continuous improvement in quality and productivity. The QA program requires that procurement of items and services be controlled to assure conformance to specification. SPEARS has been implemented to meet DOE requirements and to enhance overall confidence in supplier performance. Key elements of SPEARS include supplier evaluation and selection as well as evaluation of furnished quality through source inspection, audit, and receipt inspection. These elements are described in this paper.

  6. Supplier's Quick Guide to Sandia Electronic Invoicing

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

    ... 4 - Purchase Orders: Enter PO number only in search box and press 'Go', DO NOT enter any other fields. ... Invoice Payment Terms Section 8. Available Invoice Terms (Optional) Suppliers ...

  7. Quality Procedure - Approved Suppliers List | Department of Energy

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

    Approved Suppliers List Quality Procedure - Approved Suppliers List This procedure establishes the responsibilities, process, and records for developing and maintaining the Approved Suppliers List (ASL) for EM Headquarters Office of Standards and Quality Assurance in accordance with EM-QA-001, Environmental Management Quality Assurance Program. Quality Procedure - Approved Suppliers List (2.06 MB) More Documents & Publications Quality Procedure - Supplier Qualification Quality Procedure -

  8. ANALYSIS AND EXAMINATION OF MOX FUEL FROM NONPROLIFERATION PROGRAMS

    SciTech Connect (OSTI)

    McCoy, Kevin; Machut, Dr McLean; Morris, Robert Noel; Blanpain, Patrick; Hemrick, James Gordon

    2013-01-01

    The U.S. Department of Energy has decided to dispose of a portion of the nation s surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. Four lead assemblies were manufactured and irradiated to a maximum fuel rod burnup of 47.3 MWd/kg heavy metal. This was the first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio of less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. The performance of the rods was analyzed with AREVA s next-generation GALILEO code. The results of the analysis confirmed that the fuel rods had performed safely and predictably, and that GALILEO is applicable to MOX fuel with a low 240Pu/239Pu ratio as well as to standard MOX. The results are presented and compared to the GALILEO database. In addition, the fuel cladding was tested to confirm that traces of gallium in the fuel pellets had not affected the mechanical properties of the cladding. The irradiated cladding was found to remain ductile at both room temperature and 350 C for both the axial and circumferential directions.

  9. Supplier's Quick Guide to Sandia Electronic Invoicing

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

    Supplier's Quick Guide to Sandia Electronic Invoicing Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. 2 Table of Contents ACCESS TO ISUPPLIER & OTHER INFORMATION:

  10. How to select a water treatment supplier

    SciTech Connect (OSTI)

    Keister, T.E.

    1995-06-01

    This paper is a continuation of one first presented in 1984 at the International Water Conference. Since that time many things have changed, not the least of which is my means of earning a living. While my prospective upon the world has changed due to conversion from user to supplier, the industrial world today is also much different than that of ten years ago. Major factors driving change are the explosion in computer technology, new environmental realities and restrictions, and a radically different world from both the political and economic standpoints. All of these areas directly impact upon water treatment and the selection of a supplier. Your attention is called to the sponsor of this paper, the Association of Water Technologies (AWT). The AWT is the trade association representing {open_quotes}small{close_quotes} water treatment companies, which presently control at least 21% of the US market in water treatment services. This 21% plus market share is greater than that of any single water treatment supplier. Growth of the AWT has been quite remarkable since its founding nine short years ago, membership now stands at approximately 370 companies. The growth of the Association is a good indication that the individual small water treatment suppliers, making up 74% of the membership, are also growing. Given the huge marketing budgets of the six major water treatment companies, it is sometimes difficult to realize that there are approximately 800 other water treatment companies in the market. Many of these smaller companies can oftentimes provide a better water treatment program than a major company can due to better service, closer customer contact, superior technology, and lower overhead costs. Selection of a water treatment supplier, be it a major or one of the smaller companies, should be made upon a firm foundation of facts, not marketing {open_quotes}hype{close_quotes}.

  11. Sandia National Laboratories: What Sandia Looks For In Our Suppliers

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

    Prospective Suppliers What Sandia Looks For In Our Suppliers What Does Sandia Buy? Business Opportunities Website Small Business Working with Sandia What Sandia Looks For In Our Suppliers Suppliers must have the ability to demonstrate sustained high performance in cost, quality, safety, and on-time delivery. In addition: Innovation and responsiveness Customer focused Financially healthy and lean Product and service leadership within their industry Share commitment to mission success Able to

  12. Sandia National Laboratories: Working with Sandia: Supplier Registration

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

    Prospective Suppliers What Sandia Looks For In Our Suppliers What Does Sandia Buy? Business Opportunities Website Small Business Working with Sandia Supplier Registration Step 1. SAM Registration In order to do business with Sandia National Laboratories, businesses will be required to be registered in the System for Award Management (SAM). SAM is a government portal that enables secure registration as a potential supplier of products or services to Sandia National Laboratories and other

  13. Mixed Oxide (MOX) Fuel Fabrication Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) fieldoffices / Savannah River Field Office Mixed Oxide (MOX) Fuel Fabrication Facility Documents related to the project: Plutonium Disposition Study Options Independent Assessment Phase 1 Report, April 13, 2015 Plutonium Disposition Study Options Independent Assessment Phase 2 Report, August 20, 2015 Final Report of the Plutonium Disposition Red Team, August 13, 2015 Commentary on Report by High Bridge Associates, Inc., Feb. 12, 2016 Related Topics Mixed Oxide Fuel

  14. MOX Lead Assembly Fabrication at the Savannah River Site

    SciTech Connect (OSTI)

    Geddes, R.L.; Spiker, D.L.; Poon, A.P.

    1997-12-01

    The U. S. Department of Energy (DOE) announced its intent to prepare an Environmental Impact Statement (EIS) under the National Environmental Policy Act (NEPA) on the disposition of the nations weapon-usable surplus plutonium.This EIS is tiered from the Storage and Disposition of Weapons-Usable Fissile Material Programmatic Environmental Impact Statement issued in December 1996,and the associated Record of Decision issued on January, 1997. The EIS will examine reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. The three types of facilities are: a pit disassembly and conversion facility, a facility to immobilize surplus plutonium in a glass or ceramic form for disposition, and a facility to fabricate plutonium oxide into mixed oxide (MOX) fuel.As an integral part of the surplus plutonium program, Oak Ridge National Laboratory (ORNL) was tasked by the DOE Office of Fissile Material Disposition(MD) as the technical lead to organize and evaluate existing facilities in the DOE complex which may meet MD`s need for a domestic MOX fuel fabrication demonstration facility. The Lead Assembly (LA) facility is to produce 1 MT of usable test fuel per year for three years. The Savannah River Site (SRS) as the only operating plutonium processing site in the DOE complex, proposes two options to carry out the fabrication of MOX fuel lead test assemblies: an all Category I facility option and a combined Category I and non-Category I facilities option.

  15. Isotopic Details of the Spent Catawba-1 MOX Fuel Rods at ORNL

    SciTech Connect (OSTI)

    Ellis, Ronald James

    2015-04-01

    The United States Department of Energy funded Shaw/AREVA MOX Services LLC to fabricate four MOX Lead Test Assemblies (LTA) from weapons-grade plutonium. A total of four MOX LTAs (including MX03) were irradiated in the Catawba Nuclear Station (Unit 1) Catawba-1 PWR which operated at a total thermal power of 3411 MWt and had a core with 193 total fuel assemblies. The MOX LTAs were irradiated along with Duke Energy s irradiation of eight Westinghouse Next Generation Fuel (NGF) LEU LTAs (ref.1) and the remaining 181 LEU fuel assemblies. The MX03 LTA was irradiated in the Catawba-1 PWR core (refs.2,3) during cycles C-16 and C-17. C-16 began on June 5, 2005, and ended on November 11, 2006, after 499 effective full power days (EFPDs). C-17 started on December 29, 2006, (after a shutdown of 48 days) and continued for 485 EFPDs. The MX03 and three other MOX LTAs (and other fuel assemblies) were discharged at the end of C-17 on May 3, 2008. The design of the MOX LTAs was based on the (Framatome ANP, Inc.) Mark-BW/MOX1 17 17 fuel assembly design (refs. 4,5,6) for use in Westinghouse PWRs, but with MOX fuel rods with three Pu loading ranges: the nominal Pu loadings are 4.94 wt%, 3.30 wt%, and 2.40 wt%, respectively, for high, medium, and low Pu content. The Mark-BW/MOX1 (MOX LTA) fuel assembly design is the same as the Advanced Mark-BW fuel assembly design but with the LEU fuel rods replaced by MOX fuel rods (ref. 5). The fabrication of the fuel pellets and fuel rods for the MOX LTAs was performed at the Cadarache facility in France, with the fabrication of the LTAs performed at the MELOX facility, also in France.

  16. Final assessment of MOX fuel performance experiment with Japanese PWR specification fuel in the HBWR

    SciTech Connect (OSTI)

    Fujii, Hajime; Teshima, Hideyuki; Kanasugi, Katsumasa; Kosaka, Yuji; Arakawa, Yasushi

    2007-07-01

    In order to obtain high burn-up MOX fuel irradiation performance data, SBR and MIMAS MOX fuel rods with Pu-fissile enrichment of about 6 wt% had been irradiated in the HBWR from 1995 to 2006. The peak burn-up of MOX pellet achieved 72 GWd/tM. In this test, fuel centerline temperature, rod internal pressure, stack length and cladding length were measured for MOX fuel and UO{sub 2} fuel as reference. MOX fuel temperature is confirmed to have no significant difference in comparison with UO{sub 2}, taking into account of adequate thermal conductivity degradation due to PuO{sub 2} addition and burn-up development. And the measured fuel temperature agrees well with FINE code calculation up to high burn-up region. Fission gas release of MOX is possibly greater than UO{sub 2} based on temperature and pressure assessment. No significant difference is confirmed between SBR and MIMAS MOX on FGR behavior. MOX fuel swelling rate agrees well with solid swelling rate in the literature. Cladding elongation data shows onset of PCMI in high power region. (authors)

  17. Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels

    SciTech Connect (OSTI)

    Carbajo, J.J.

    2005-05-27

    The purpose of this report is to quantify the differences between mixed oxide (MOX) and low-enriched uranium (LEU) fuels and to assess in reasonable detail the potential impacts of MOX fuel use in VVER-1000 nuclear power plants in Russia. This report is a generic tool to assist in the identification of plant modifications that may be required to accommodate receiving, storing, handling, irradiating, and disposing of MOX fuel in VVER-1000 reactors. The report is based on information from work performed by Russian and U.S. institutions. The report quantifies each issue, and the differences between LEU and MOX fuels are described as accurately as possible, given the current sources of data.

  18. A Neutronic Analysis of TRU Recycling in PWRs Loaded with MOX-UE Fuel (MOX with U-235 Enriched U Support)

    SciTech Connect (OSTI)

    G. Youinou; S. Bays

    2009-05-01

    This report presents the results of a study dealing with the homogeneous recycling of either Pu or Pu+Np or Pu+Np+Am or Pu+Np+Am+Cm in PWRs using MOX-UE fuel, i.e. standard MOX fuel with a U235 enriched uranium support instead of the standard tail uranium (0.25%) for standard MOX fuel. This approach allows to multirecycle Pu or TRU (Pu+MA) as long as U235 is available, by keeping the Pu or TRU content in the fuel constant and at a value ensuring a negative moderator void coefficient (i.e. the loss of the coolant brings imperatively the reactor to a subcritical state). Once this value is determined, the U235 enrichment of the MOX-UE fuel is adjusted in order to reach the target burnup (51 GWd/t in this study).

  19. 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.

  20. Prime Supplier Sales Volumes of Distillate Fuel Oils and Kerosene...

    Gasoline and Diesel Fuel Update (EIA)

    Marketing Annual 1997 401 Table 50. Prime Supplier Sales Volumes of Distillate Fuel Oils and Kerosene by PAD District and State (Thousand Gallons per Day) - Continued...

  1. Table 50. Prime Supplier Sales Volumes of Distillate Fuel Oils...

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

    Marketing Annual 1999 359 Table 50. Prime Supplier Sales Volumes of Distillate Fuel Oils and Kerosene by PAD District and State (Thousand Gallons per Day) - Continued...

  2. Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane...

    Gasoline and Diesel Fuel Update (EIA)

    See footnotes at end of table. 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane, and Residual Fuel Oil by PAD District and State 386 Energy Information...

  3. Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane...

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

    Marketing Annual 1998 Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane, and Residual Fuel Oil by PAD District and State (Thousand Gallons per Day) -...

  4. Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane...

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

    Marketing Annual 1995 Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane, and Residual Fuel Oil by PAD District and State (Thousand Gallons per Day) -...

  5. Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane...

    Gasoline and Diesel Fuel Update (EIA)

    Marketing Annual 1999 Table 49. Prime Supplier Sales Volumes of Aviation Fuels, Propane, and Residual Fuel Oil by PAD District and State (Thousand Gallons per Day) -...

  6. Sandia National Laboratories: Working with Sandia: Become a Supplier

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

    attempts to procure goods from existing laboratory suppliers. View Notice Step 1. SAM Registration Government Registration within the System for Award Management (SAM) The...

  7. Energy Supplier Obligations and White Certificate Schemes: Comparative...

    Open Energy Info (EERE)

    ways different European Union (EU) member states, including the United Kingdom, Italy, France, Denmark and Belgium, have implemented energy supplier obligations and white...

  8. Table 48. Prime Supplier Sales Volumes of Motor Gasoline by...

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

    Petroleum Marketing Annual 1998 Table 48. Prime Supplier Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State (Thousand Gallons per Day) -...

  9. Table 48. Prime Supplier Sales Volumes of Motor Gasoline by...

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

    Petroleum Marketing Annual 1999 Table 48. Prime Supplier Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State (Thousand Gallons per Day) -...

  10. Table 48. Prime Supplier Sales Volumes of Motor Gasoline by...

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

    Petroleum Marketing Annual 1995 Table 48. Prime Supplier Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State (Thousand Gallons per Day) -...

  11. Gold Nanoparticles

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

    Kornberg Research Science Perspective Chemistry World 16 December 2007 Structure of a Coated Gold Nanoparticle summary written by Amber Dance, SLAC Communication Office A team of scientists, working in part at SSRL's crystallography beam lines and led by Stanford Professor Roger Kornberg, has determined for the first time the atomic structure (at 1.1 Å resolution) of a thiol-covered gold nanoparticle, a discovery with potential for a range of applications from biosensors to nanotransistors. The

  12. Development of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Mertyurek, Ugur; Gauld, Ian C.

    2015-12-24

    In this research, ORIGEN cross section libraries for reactor-grade mixed oxide (MOX) fuel assembly designs have been developed to provide fast and accurate depletion calculations to predict nuclide inventories, radiation sources and thermal decay heat information needed in safety evaluations and safeguards verification measurements of spent nuclear fuel. These ORIGEN libraries are generated using two-dimensional lattice physics assembly models that include enrichment zoning and cross section data based on ENDF/B-VII.0 evaluations. Using the SCALE depletion sequence, burnup-dependent cross sections are created for selected commercial reactor assembly designs and a representative range of reactor operating conditions, fuel enrichments, and fuel burnup.more » The burnup dependent cross sections are then interpolated to provide problem-dependent cross sections for ORIGEN, avoiding the need for time-consuming lattice physics calculations. The ORIGEN libraries for MOX assembly designs are validated against destructive radiochemical assay measurements of MOX fuel from the MALIBU international experimental program. This program included measurements of MOX fuel from a 15 × 15 pressurized water reactor assembly and a 9 × 9 boiling water reactor assembly. The ORIGEN MOX libraries are also compared against detailed assembly calculations from the Phase IV-B numerical MOX fuel burnup credit benchmark coordinated by the Nuclear Energy Agency within the Organization for Economic Cooperation and Development. Finally, the nuclide compositions calculated by ORIGEN using the MOX libraries are shown to be in good agreement with other physics codes and with experimental data.« less

  13. Development of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs

    SciTech Connect (OSTI)

    Mertyurek, Ugur; Gauld, Ian C.

    2015-12-24

    In this research, ORIGEN cross section libraries for reactor-grade mixed oxide (MOX) fuel assembly designs have been developed to provide fast and accurate depletion calculations to predict nuclide inventories, radiation sources and thermal decay heat information needed in safety evaluations and safeguards verification measurements of spent nuclear fuel. These ORIGEN libraries are generated using two-dimensional lattice physics assembly models that include enrichment zoning and cross section data based on ENDF/B-VII.0 evaluations. Using the SCALE depletion sequence, burnup-dependent cross sections are created for selected commercial reactor assembly designs and a representative range of reactor operating conditions, fuel enrichments, and fuel burnup. The burnup dependent cross sections are then interpolated to provide problem-dependent cross sections for ORIGEN, avoiding the need for time-consuming lattice physics calculations. The ORIGEN libraries for MOX assembly designs are validated against destructive radiochemical assay measurements of MOX fuel from the MALIBU international experimental program. This program included measurements of MOX fuel from a 15 × 15 pressurized water reactor assembly and a 9 × 9 boiling water reactor assembly. The ORIGEN MOX libraries are also compared against detailed assembly calculations from the Phase IV-B numerical MOX fuel burnup credit benchmark coordinated by the Nuclear Energy Agency within the Organization for Economic Cooperation and Development. Finally, the nuclide compositions calculated by ORIGEN using the MOX libraries are shown to be in good agreement with other physics codes and with experimental data.

  14. Melting temperatures of the ZrO{sub 2}-MOX system

    SciTech Connect (OSTI)

    Uchida, T.; Hirooka, S.; Kato, M.; Morimoto, K.; Sugata, H.; Shibata, K.; Sato, D.

    2013-07-01

    Severe accidents occurred at the Fukushima Daiichi Nuclear Power Plant Units 1-3 on March 11, 2011. MOX fuels were loaded in the Unit 3. For the thermal analysis of the severe accident, melting temperature and phase state of MOX corium were investigated. The simulated coriums were prepared from 4%Pu-containing MOX, 8%Pu-containing MOX and ZrO{sub 2}. Then X-ray diffraction, density and melting temperature measurements were carried out as a function of zirconium and plutonium contents. The cubic phase was observed in the 25%Zr-containing corium and the tetragonal phase was observed in the 50% and 75%Zr-containing coria. The lattice parameter and density monotonically changed with Pu content. Melting temperature increased with increasing Pu content; melting temperature were estimated to be 2932 K for 4%Pu MOX corium and 3012 K for 8%Pu MOX corium in the 25%ZrO{sub 2}-MOX system. The lowest melting temperature was observed for 50%Zr-containing corium. (authors)

  15. Suppliers and Environmental Innovation: The Automotive Paint Process

    SciTech Connect (OSTI)

    Geffen, Charlette A.; Rothenberg, Sandra

    2000-01-01

    Automobile assembly plants worldwide face increasing pressures in the environmental arena. How a plant responds to these issues has significant implications for the cost and quality of plant operations. This paper uses three case studies of U.S. assembly plants to examine the role of partnerships between original equipment manufacturers (OEMs) and their suppliers in improving the environmental performance of manufacturing operations. We find that strong partnerships with suppliers, supported by appropriate incentive systems, were a significant element of the successful application of innovative environmental technologies. Supplier staff members were an important part of achieving environmental performance improvements while maintaining production quality and cost goals. The management factors influencing the extent and nature of supplier involvement are identified. The results of this work point to the importance of suppliers in addressing the manufacturing challenges of the future.

  16. Examination of Risk Analysis Methods for MOX Land Transport in Japan

    SciTech Connect (OSTI)

    HOHNSTREITER, GLENN FREDRICK; PIERCE, JIM D.

    2003-04-01

    This report presents background information and methodology for a risk assessment of mixed oxide (MOX) reactor fuel transport in the nation of Japan to support their nuclear energy program. This work includes an extensive literature review, a review of other MOX activities worldwide, a survey of the statutory requirements for transporting nuclear materials, a discussion of risk assessment methodology, and calculation results for specific examples. Typical risk evaluations are given to provide guidance for later risk analyses specific to MOX fuel transport in Japan. This report also includes specific information that will be required for routes, cask types, accident-rate statistics, and population densities along specified routes, along with other detailed information needed for risk analysis studies pertinent to MOX transport in Japan. This information will be used in future specific risk studies.

  17. Japanese suppliers in transition from domestic nuclear reactor vendors to international suppliers

    SciTech Connect (OSTI)

    Forsberg, C.W.; Reich, W.J.; Rowan, W.J.

    1994-06-27

    Japan is emerging as a major leader and exporter of nuclear power technology. In the 1990s, Japan has the largest and strongest nuclear power supply industry worldwide as a result of the largest domestic nuclear power plant construction program. The Japanese nuclear power supply industry has moved from dependence on foreign technology to developing, design, building, and operating its own power plants. This report describes the Japanese nuclear power supply industry and examines one supplier--the Mitsubishi group--to develop an understanding of the supply industry and its relationship to the utilities, government, and other organizations.

  18. ORNL Supplier Database - Stay in Touch! | Department of Energy

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

    ORNL Supplier Database - Stay in Touch! ORNL Supplier Database - Stay in Touch! December 5, 2014 - 4:19pm Addthis Small business owners seeking to do business with the U.S. Department of Energy may already be aware of the Oak Ridge Supplier Database. The Small Business Programs Office at Oak Ridge National Laboratory (ORNL) would like to keep in touch with you periodically about pertinent, small business-related information. This may include updates from ORNL, the Department of Energy (DOE), the

  19. NNSA Marks Two-Year Construction Milestone at MOX Facility in South

    National Nuclear Security Administration (NNSA)

    Carolina | National Nuclear Security Administration | (NNSA) Marks Two-Year Construction Milestone at MOX Facility in South Carolina July 31, 2009 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) today marked the second full year of successful construction of the Mixed Oxide (MOX) Fuel Fabrication Facility at the Savannah River Site (SRS) near Aiken, South Carolina, by launching a new online multimedia kit on NNSA's website. The kit, which includes a photo gallery that

  20. Microsoft Word - Managing Your iSupplier Profile Job Aid R12 05092012.docx

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

    Managing Your iSupplier Profile Table of Contents Summary of Your iSupplier Profile...........................................................................................................................2 Accessing Your Account for the First Time.............................................................................................................2 Navigating to Your

  1. Programmatic and technical requirements for the FMDP fresh MOX fuel transport package

    SciTech Connect (OSTI)

    Ludwig, S. B.; Michelhaugh, R. D.; Pope, R. B.; Shappert, L. B.; Singletary, B. H.; Chae, S. M.; Parks, C. V.; Broadhead, B. L.; Schmid, S. P.; Cowart, C. G.

    1997-12-01

    This document is intended to guide the designers of the package to all pertinent regulatory and other design requirements to help ensure the safe and efficient transport of the weapons-grade (WG) fresh MOX fuel under the Fissile Materials Disposition Program. To accomplish the disposition mission using MOX fuel, the unirradiated MOX fuel must be transported from the MOX fabrication facility to one or more commercial reactors. Because the unirradiated fuel contains large quantities of plutonium and is not sufficient radioactive to create a self-protecting barrier to deter the material from theft, DOE intends to use its fleet of safe secure trailers (SSTs) to provide the necessary safeguards and security for the material in transit. In addition to these requirements, transport of radioactive materials must comply with regulations of the Department of Transportation and the Nuclear Regulatory Commission (NRC). In particular, NRC requires that the packages must meet strict performance requirements. The requirements for shipment of MOX fuel (i.e., radioactive fissile materials) specify that the package design is certified by NRC to ensure the materials contained in the packages are not released and remain subcritical after undergoing a series of hypothetical accident condition tests. Packages that pass these tests are certified by NRC as a Type B fissile (BF) package. This document specifies the programmatic and technical design requirements a package must satisfy to transport the fresh MOX fuel assemblies.

  2. Gold Nanoantennas

    SciTech Connect (OSTI)

    2012-01-01

    An array of gold nanoantennas laced into an artificial membrane enhances the fluorescence intensity of three different molecules when they pass through plasmonic hot spots in the array. Watch for the blue, green and red flashes. The photobleaching at the end of each fluorescence event (white flashes) is indicative of single molecule observations.

  3. The Nuclear Suppliers Group: A multilateral arrangement devoted to supplier coordination

    SciTech Connect (OSTI)

    Dedik, T.; Thorne, C.E.; Goorevich, R.S.

    1995-12-31

    When the then-26 adherents to the Nuclear Suppliers Group (NSG) Guidelines met for the first time in more than 13 years in The Hague in April 1991 it began a new and dynamic process for coordinating the full range of nuclear supplier issues. In less than four years the NSG has expanded its membership to 31 countries and has implemented major changes to its Guidelines and commodity control lists. Enhancements to the Regime agreed to by the Group since its reinvigoration include the adoption of controls on nuclear-related-dual-use equipment, materials and technology; the requirements for a recipient country to have an agreement with the International Atomic Energy Agency calling for safeguards on its entire nuclear program, both now and in the future; a major expansion of the Trigger List (the list of commodities which ``trigger`` safeguards as a condition of supply) to clarify and add detail to the controlled commodities; comparable controls on technologies associated with Trigger List items; and ``fixes`` to the Guidelines to control retransfers and exports to countries with suspect nonproliferation credentials. This paper provides a comprehensive overview of the NSG and discusses in detail the past, present and future work of the Group.

  4. Table 48. Prime Supplier Sales Volumes of Motor Gasoline by...

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

    - - 466.1 466.1 See footnotes at end of table. 48. Prime Supplier Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State 356 Energy Information...

  5. Table 48. Prime Supplier Sales Volumes of Motor Gasoline by...

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

    - - 532.1 532.1 See footnotes at end of table. 48. Prime Supplier Sales Volumes of Motor Gasoline by Grade, Formulation, PAD District, and State 356 Energy Information...

  6. Comment to NOI re Retrospective Risk Pooling Program For Suppliers

    Broader source: Energy.gov [DOE]

    Comment by Cameco Resources On Retrospective Risk Pooling Program For Suppliers, 75 Fed. Reg. 43945 (July 27, 2010), Section 934 Rule Making. As discussed below, Cameco believes that producers and...

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

    SciTech Connect (OSTI)

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

    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.

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

    SciTech Connect (OSTI)

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

    1998-03-01

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

  9. Critical Experiments that Simulated Damp MOX Powders - Do They Meet the Need?

    SciTech Connect (OSTI)

    J. Blair Briggs; Dr. Ali Nouri; Dr. Claes Nordborg

    2005-09-01

    The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified the MOX fuel manufacturing process as an area in which there is a need for additional integral benchmark data. The specific need focused on damp MOX powders. The WPNCS was ultimately asked by the NEA Nuclear Science Committee (NSC) to provide the framework for the selection and performance of new experiments that fill the identified need. A set of criteria was established to enable uniform comparison of experimental proposals with generic MOX application data. Criteria were established for five general characteristics: (1) neutronic parameters, (2) type of experiments, (3) financial aspects, (4) schedule, and (5) other considerations. Proposals were judged most importantly on their ability to match the neutronic parameters of predetermined MOX applications. The neutronic parameters that formed the basis for comparison included core average values (not local values) for flux, fission and capture rate; detailed balance data (fission and capture) for the main isotopes (Actinides, H and O); sensitivity coefficients to important nuclear reactions (fission, capture, elastic and inelastic scatter, nu-bar, mu-bar) for all uranium and plutonium isotopes, hydrogen, and oxygen; sensitivity profiles to the main nuclear reactions for uranium and plutonium isotopes; energy of average lethargy causing fission; and the average fission group energy. The focus of this paper is on the definition of the need; the neutronics criteria established to assess which, if any, of three proposed MOX experimental programs best meet the need; and the actual assessment of the proposed experimental programs.

  10. Modeling of the performance of weapons MOX fuel in light water reactors

    SciTech Connect (OSTI)

    Alvis, J.; Bellanger, P.; Medvedev, P.G.; Peddicord, K.L.; Gellene, G.I.

    1999-05-01

    Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light water reactors (LWRs) for the disposition of excess plutonium from disassembled nuclear warheads. Fuel performance models are used which describe the behavior of MOX fuel during irradiation under typical power reactor conditions. The objective of this project is to perform the analysis of the thermal, mechanical, and chemical behavior of weapons MOX fuel pins under LWR conditions. If fuel performance analysis indicates potential questions, it then becomes imperative to assess the fuel pin design and the proposed operating strategies to reduce the probability of clad failure and the associated release of radioactive fission products into the primary coolant system. Applying the updated code to anticipated fuel and reactor designs, which would be used for weapons MOX fuel in the US, and analyzing the performance of the WWER-100 fuel for Russian weapons plutonium disposition are addressed in this report. The COMETHE code was found to do an excellent job in predicting fuel central temperatures. Also, despite minor predicted differences in thermo-mechanical behavior of MOX and UO{sub 2} fuels, the preliminary estimate indicated that, during normal reactor operations, these deviations remained within limits foreseen by fuel pin design.

  11. Greenhouse Gases into Gold

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

    Turning Greenhouse Gases into Gold Greenhouse Gases into Gold NERSC simulations reveal reaction mechanism behind CO conversion into carbon-neutral fuels and chemicals November ...

  12. Performance of Cladding on MOX Fuel with Low 240Pu/239Pu Ratio

    SciTech Connect (OSTI)

    McCoy, Kevin; Blanpain, Patrick; Morris, Robert Noel

    2014-01-01

    The U.S. Department of Energy has decided to dispose of a portion of its surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. As part of fuel qualification, four lead assemblies were manufactured and irradiated to a maximum fuel rod average burnup of 47.3 MWd/kg heavy metal. This was the world s first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This paper discusses the results of those examinations with emphasis on cladding performance. Exams relevant to the cladding included visual and eddy current exams, profilometry, microscopy, hydrogen analysis, gallium analysis, and mechanical testing. There was no discernible effect of the type of MOX fuel on the performance of the cladding.

  13. Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

    SciTech Connect (OSTI)

    Kudinov, K. G.; Tretyakov, A. A.; Sorokin, Yu. P.; Bondin, V. V.; Manakova, L. F.; Jardine, L. J.

    2002-02-26

    In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on a production capacity of 2.75 tons of weapons plutonium per year to produce the resulting fuel assemblies: 1.25 tons for the BN-600 reactor FAs and the remaining 1.5 tons for VVER-1000 FAs. It is likely the quantity of BN-600 FAs will be reduced in actual practice. The process of nuclear disarmament frees a significant amount of weapons plutonium for other uses, which, if unutilized, represents a constant general threat. In France, Great Britain, Belgium, Russia, and Japan, reactor-grade plutonium is used in MOX-fuel production. Making MOX-fuel for CANDU (Canada) and pressurized water reactors (PWR) (Europe) is under consideration in Russia. If this latter production is added, as many as 5 tons of Pu per year might be processed into new FAs in Russia. Many years of work and experience are represented in the estimates of MOX fuel production wastes derived in this report. Prior engineering studies and sludge treatment investigations and comparisons have determined how best to treat Pu sludges and MOX fuel wastes. Based upon analyses of the production processes established by these efforts, we can estimate that there will be approximately 1200 kg of residual wastes subject to immobilization per MT of plutonium processed, of which approximately 6 to 7 kg is Pu in the residuals per MT of Pu processed. The wastes are various and complicated in composition. Because organic wastes constitute both the major portion of total waste and of the Pu to be immobilized, the recommended treatment of MOX-fuel production waste is

  14. Multirecycling of Plutonium from LMFBR Blanket in Standard PWRs Loaded with MOX Fuel

    SciTech Connect (OSTI)

    Sonat Sen; Gilles Youinou

    2013-02-01

    It is now well-known that, from a physics standpoint, Pu, or even TRU (i.e. Pu+M.A.), originating from LEU fuel irradiated in PWRs can be multirecycled also in PWRs using MOX fuel. However, the degradation of the isotopic composition during irradiation necessitates using enriched U in conjunction with the MOX fuel either homogeneously or heterogeneously to maintain the Pu (or TRU) content at a level allowing safe operation of the reactor, i.e. below about 10%. The study is related to another possible utilization of the excess Pu produced in the blanket of a LMFBR, namely in a PWR(MOX). In this case the more Pu is bred in the LMFBR, the more PWR(MOX) it can sustain. The important difference between the Pu coming from the blanket of a LMFBR and that coming from a PWR(LEU) is its isotopic composition. The first one contains about 95% of fissile isotopes whereas the second one contains only about 65% of fissile isotopes. As it will be shown later, this difference allows the PWR fed by Pu from the LMFBR blanket to operate with natural U instead of enriched U when it is fed by Pu from PWR(LEU)

  15. A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments

    SciTech Connect (OSTI)

    Phillippe, Aaron M; Clarno, Kevin T; Banfield, James E; Ott, Larry J; Philip, Bobby; Berrill, Mark A; Sampath, Rahul S; Allu, Srikanth; Hamilton, Steven P

    2014-01-01

    Abstract The IFA-597 (Integrated Fuel Assessment) experiments from the International Fuel Performance Experiments (IFPE) database were designed to study the thermal behavior of mixed oxide (MOX) fuel and the effects of an annulus on fission gas release in light-water-reactor fuel. An evaluation of nuclear fuel pin heat transfer in the FRAPCON-3.4 and Exnihilo codes for MOX fuel systems was performed, with a focus on the first 20 time steps ( 6 GWd/MT(iHM)) for explicit comparison between the codes. In addition, sensitivity studies were performed to evaluate the effect of the radial power shape and approximations to the geometry to account for the thermocouple hole, dish, and chamfer. The analysis demonstrated relative agreement for both solid (rod 1) and annular (rod 2) fuel in the experiment, demonstrating the accuracy of the codes and their underlying material models for MOX fuel, while also revealing a small energy loss artifact in how gap conductance is currently handled in Exnihilo for chamfered fuel pellets. The within-pellet power shape was shown to significantly impact the predicted centerline temperatures. This has provided an initial benchmarking of the pin heat transfer capability of Exnihilo for MOX fuel with respect to a well-validated nuclear fuel performance code.

  16. Benchmark of SCALE (SAS2H) isotopic predictions of depletion analyses for San Onofre PWR MOX fuel

    SciTech Connect (OSTI)

    Hermann, O.W.

    2000-02-01

    The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, after discharge from reactors is of significant interest to the Fissile Materials Disposition Program. The validation of the SCALE (SAS2H) depletion code for use in the prediction of isotopic compositions of MOX fuel, similar to previous validation studies on uranium-only fueled reactors, has corresponding significance. The EEI-Westinghouse Plutonium Recycle Demonstration Program examined the use of MOX fuel in the San Onofre PWR, Unit 1, during cycles 2 and 3. Isotopic analyses of the MOX spent fuel were conducted on 13 actinides and {sup 148}Nd by either mass or alpha spectrometry. Six fuel pellet samples were taken from four different fuel pins of an irradiated MOX assembly. The measured actinide inventories from those samples has been used to benchmark SAS2H for MOX fuel applications. The average percentage differences in the code results compared with the measurement were {minus}0.9% for {sup 235}U and 5.2% for {sup 239}Pu. The differences for most of the isotopes were significantly larger than in the cases for uranium-only fueled reactors. In general, comparisons of code results with alpha spectrometer data had extreme differences, although the differences in the calculations compared with mass spectrometer analyses were not extremely larger than that of uranium-only fueled reactors. This benchmark study should be useful in estimating uncertainties of inventory, criticality and dose calculations of MOX spent fuel.

  17. Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

    SciTech Connect (OSTI)

    Kudinov, K.G.; Tretyakov, A.A.; Sorokin, Y.P.; Bondin, V.V.; Manakova, L.F.; Jardine, L.J.

    2001-12-01

    In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on production capacity of 2.75 tons of weapons plutonium per year to produce the resulting fuel assemblies: 1.25 tons for the BN-600 reactor FAs and the remaining 1.5 tons for VVER-1000 FAs. It is likely the quantity of BN-600 FAs will be reduced in actual practice. The process of nuclear disarmament frees a significant amount of weapons plutonium for other uses, which, if unutilized, represents a constant general threat. In France, Great Britain, Belgium, Russia, and Japan, reactor-grade plutonium is used in MOX-fuel production. Making MOX-fuel for CANDU (Canada) and pressurized water reactors (PWR) (Europe) is under consideration Russia. If this latter production is added, as many as 5 tons of Pu per year might be processed into new FAs in Russia. Many years of work and experience are represented in the estimates of MOX fuel production wastes derived in this report. Prior engineering studies and sludge treatment investigations and comparisons have determined how best to treat Pu sludges and MOX fuel wastes. Based upon analyses of the production processes established by these efforts, we can estimate that there will be approximately 1200 kg of residual wastes subject to immobilization per MT of plutonium processed, of which approximately 6 to 7 kg is Pu in the residuals per MT of Pu processed. The wastes are various and complicated in composition. Because organic wastes constitute both the major portion of total waste and of the Pu to be immobilized, the recommended treatment of MOX-fuel production waste is incineration

  18. Your're Invited: Join Our Supplier Outreach Event on August 19th

    Broader source: Energy.gov [DOE]

    On August 19, 2011, the Department of Energy will be co-sponsoring a suppliers outreach event for suppliers who wish to provide services to Service Disabled Veteran Owned Businesses. This event,...

  19. Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    SciTech Connect (OSTI)

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

    1998-08-01

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

  20. Sandia National Laboratories: Working with Sandia: Prospective Suppliers

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

    Prospective Suppliers Doing Business with Sandia Sandia is dedicated to purchasing quality products and services required to meet our national security mission Sandia spends about $1 billion each year on purchases of quality products and services to meet its national security missions. The Labs are committed to buying from small businesses and partnering with companies that share its values of conducting business in an ethical and safe manner while providing products and services on time and

  1. Evaluation of Internal Criticality of the Plutonium Dispostion MOX SNF Waste Form

    SciTech Connect (OSTI)

    A.A. Alsaed

    1999-09-28

    The purpose of this calculation is to perform a parametric study to determine the effects of fission product leaching, assembly collapse, and iron oxide loss ({Delta}Fe{sub 2}O{sub 3}) on the reactivity of a waste package (WP) containing mixed oxide (MOX) spent nuclear fuel (SNF). Previous calculations (CRWMS M&O 1998a) have shown that the criticality control features of the WP are adequate to prevent criticality of a flooded WP for all the enrichment/burnup pairs expected for the MOX SNF. Therefore, the objective of this calculation is to determine the increase in reactivity that might result from possible degradation of the WP criticality control features. Specifically, this calculation tests the sensitivity of effective neutron multiplication factor (k{sub eff}) to loss (from the WP) of the following: (1) fission product neutron absorbers, or (2) moderator displacement material (principally, the iron oxide that results from the corrosion of carbon steel).

  2. Weapons-Grade MOX Fuel Burnup Characteristics in Advanced Test Reactor Irradiation

    SciTech Connect (OSTI)

    G. S. Chang

    2006-07-01

    Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a burnup of 50 GWd/t. The MOX fuel was fabricated at Los Alamos National Laboratory (LANL) by a master-mix process and has been irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). Previous withdrawals of the same fuel have occurred at 9, 21, 30, 40, and 50 GWd/t. Oak Ridge National Laboratory (ORNL) manages this test series for the Department of Energys Fissile Materials Disposition Program (FMDP). A UNIX BASH (Bourne Again SHell) script CMO has been written and validated at the Idaho National Laboratory (INL) to couple the Monte Carlo transport code MCNP with the depletion and buildup code ORIGEN-2 (CMO). The new Monte Carlo burnup analysis methodology in this paper consists of MCNP coupling through CMO with ORIGEN-2(MCWO). MCWO is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code ORIGEN-2. The fuel burnup analyses presented in this study were performed using MCWO. MCWO analysis yields time-dependent and neutron-spectrum-dependent minor actinide and Pu concentrations for the ATR small I-irradiation test position. The purpose of this report is to validate both the Weapons-Grade Mixed Oxide (WG-MOX) test assembly model and the new fuel burnup analysis methodology by comparing the computed results against the neutron monitor measurements and the irradiated WG-MOX post irradiation examination (PIE) data.

  3. 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.

    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.

  4. Application of wavelet scaling function expansion continuous-energy resonance calculation method to MOX fuel problem

    SciTech Connect (OSTI)

    Yang, W.; Wu, H.; Cao, L.

    2012-07-01

    More and more MOX fuels are used in all over the world in the past several decades. Compared with UO{sub 2} fuel, it contains some new features. For example, the neutron spectrum is harder and more resonance interference effects within the resonance energy range are introduced because of more resonant nuclides contained in the MOX fuel. In this paper, the wavelets scaling function expansion method is applied to study the resonance behavior of plutonium isotopes within MOX fuel. Wavelets scaling function expansion continuous-energy self-shielding method is developed recently. It has been validated and verified by comparison to Monte Carlo calculations. In this method, the continuous-energy cross-sections are utilized within resonance energy, which means that it's capable to solve problems with serious resonance interference effects without iteration calculations. Therefore, this method adapts to treat the MOX fuel resonance calculation problem natively. Furthermore, plutonium isotopes have fierce oscillations of total cross-section within thermal energy range, especially for {sup 240}Pu and {sup 242}Pu. To take thermal resonance effect of plutonium isotopes into consideration the wavelet scaling function expansion continuous-energy resonance calculation code WAVERESON is enhanced by applying the free gas scattering kernel to obtain the continuous-energy scattering source within thermal energy range (2.1 eV to 4.0 eV) contrasting against the resonance energy range in which the elastic scattering kernel is utilized. Finally, all of the calculation results of WAVERESON are compared with MCNP calculation. (authors)

  5. Sandia National Laboratories Supplier Quality Requirements for Build to

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

    Supplier Quality Requirements for Build to Print Hardware Purchases Subject: First Release:SNL-5-2002, Issue A, 05/16/02 Revised this 18th day'ofNovember, 2004 as F-42(QP-28)04* . Revised By: 11)' I(.~ 't:t' AntOnIO J. ~ora, 14133 14133 Manager ~ c-. m I ~~ <.:-, lL 10252 Manager? \"\\_- - II - 2.3 - 0 'i ~e~7 1 025 8 Manager$::~ R (/.tff7 J Frank A. Villareal Approved By: * The revision of the document in effect at tlte tinre of award of Purchase Order of Subcontract unless otherwise

  6. GOLD PLATING PROCESS

    DOE Patents [OSTI]

    Seegmiller, R.

    1957-08-01

    An improved bath is reported for plating gold on other metals. The composition of the plating bath is as follows: Gold cyanide from about 15 to about 50 grams, potassium cyanide from about 70 to about 125 grams, and sulfonated castor oil from about 0.1 to about 10 cc. The gold plate produced from this bath is smooth, semi-hard, and nonporous.

  7. Gold Awards - Hanford Site

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

    Hanford Site Wide Programs DOE Human Resources Management Recognition and Awards Program Gold Awards About Us DOE Human Resources Management Division DOE Employment Recognition and Awards Program Gold Awards Silver Award Federal Employees Union (AFGE Local 788) Work Schedules / Pay and Leave Benefits and Services EEO & Diversity Gold Awards Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size Recognition is provided through monetary, non-monetary, and honorary

  8. Suspect/Counterfeit Items Information Guide for Subcontractors/Suppliers

    SciTech Connect (OSTI)

    Tessmar, Nancy D.; Salazar, Michael J.

    2012-09-18

    Counterfeiting of industrial and commercial grade items is an international problem that places worker safety, program objectives, expensive equipment, and security at risk. In order to prevent the introduction of Suspect/Counterfeit Items (S/CI), this information sheet is being made available as a guide to assist in the implementation of S/CI awareness and controls, in conjunction with subcontractor's/supplier's quality assurance programs. When it comes to counterfeit goods, including industrial materials, items, and equipment, no market is immune. Some manufactures have been known to misrepresent their products and intentionally use inferior materials and processes to manufacture substandard items, whose properties can significantly cart from established standards and specifications. These substandard items termed by the Department of Energy (DOE) as S/CI, pose immediate and potential threats to the safety of DOE and contractor workers, the public, and the environment. Failure of certain systems and processes caused by an S/CI could also have national security implications at Los Alamos National Laboratory (LANL). Nuclear Safety Rules (federal Laws), DOE Orders, and other regulations set forth requirements for DOE contractors to implement effective controls to assure that items and services meet specified requirements. This includes techniques to implement and thereby minimizing the potential threat of entry of S/CI to LANL. As a qualified supplier of goods or services to the LANL, your company will be required to establish and maintain effective controls to prevent the introduction of S/CI to LANL. This will require that your company warrant that all items (including their subassemblies, components, and parts) sold to LANL are genuine (i.e. not counterfeit), new, and unused, and conform to the requirements of the LANL purchase orders/contracts unless otherwise approved in writing to the Los Alamos National Security (LANS) contract administrator

  9. Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 1 -- Intact mode calculations

    SciTech Connect (OSTI)

    Goluoglu, S.; Davis, J.W.; Montierth, L.M.

    1999-07-01

    The authors provide the intact criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test Facility (FFTF) in the potential Monitored Geologic Repository at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the DOE SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is representative of the mixed-oxide fuel (MOX) group.

  10. 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.

    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

  11. Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium

    SciTech Connect (OSTI)

    Biswas, D.; Rathbun, R.; Lee, Si Young; Rosenthal, P.

    1993-12-31

    Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

  12. Going green earns Laboratory gold

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

    Going green earns Laboratory gold Going green earns Laboratory gold The Laboratory's newest facility is its first to achieve both the Leadership in Energy and Environmental Design...

  13. Noah Golding | Department of Energy

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

    Noah Golding About Us Noah Golding - Communications Specialist, Wind and Water Power Technologies Office Most Recent Winning with Wind: Electric Co-ops Providing Clean Energy to ...

  14. Going green earns Laboratory gold

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

    Going green earns Laboratory gold Going green earns Laboratory gold The Laboratory's newest facility is its first to achieve both the Leadership in Energy and Environmental Design ...

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

    SciTech Connect (OSTI)

    Bronson, M.C.

    1997-10-01

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

  16. Strength Loss in MA-MOX Green Pellets from Radiation Damage to Binders

    SciTech Connect (OSTI)

    Paul A. Lessing; W.R. Cannon; Gerald W. Egeland; Larry D. Zuck; James K. Jewell; Douglas W. Akers; Gary S. Groenewold

    2013-06-01

    The fracture strength of green Minor Actinides (MA)-MOX pellets containing 75 wt.% DUO2, 20 wt. % PuO2, 3 wt. % AmO2 and 2 wt. % NpO2 was studied as a function of storage time, after mixing in the binder and before sintering, to test the effect of radiation damage on binders. Fracture strength degraded continuously over the 10 days of the study for all three binders studied: PEG binder (Carbowax 8000), microcrystalline wax (Mobilcer X) and Styrene-acrylic copolymer (Duramax B1022) but the fracture strength of Duramax B1022 degraded the least. For instance, for several hours after mixing Carbowax 8000 with MA MOX, the fracture strength of a pellet was reasonably high and pellets were easily handled without breaking but the pellets were too weak to handle after 10 days. Strength measured using diametral compression test showed strength degradation was more rapid in pellets containing 1.0 wt. % Carbowax PEG 8000 compared to those containing only 0.2 wt. %, suggesting that irradiation not only left the binder less effective but also reduced the pellet strength. In contrast the strength of pellets containing Duramax B1022 degraded very little over the 10 day period. It was suggested that the styrene portion of the Duramax B1022 copolymer provided the radiation resistance.

  17. 100% MOX BWR experimental program design using multi-parameter representative

    SciTech Connect (OSTI)

    Blaise, P.; Fougeras, P.; Cathalau, S.

    2012-07-01

    A new multiparameter representative approach for the design of Advanced full MOX BWR core physics experimental programs is developed. The approach is based on sensitivity analysis of integral parameters to nuclear data, and correlations among different integral parameters. The representativeness method is here used to extract a quantitative relationship between a particular integral response of an experimental mock-up and the same response in a reference project to be designed. The study is applied to the design of the 100% MOX BASALA ABWR experimental program in the EOLE facility. The adopted scheme proposes an original approach to the problem, going from the initial 'microscopic' pin-cells integral parameters to the whole 'macroscopic' assembly integral parameters. This approach enables to collect complementary information necessary to optimize the initial design and to meet target accuracy on the integral parameters to be measured. The study has demonstrated the necessity of new fuel pins fabrication, fulfilling minimal costs requirements, to meet acceptable representativeness on local power distribution. (authors)

  18. Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups

    SciTech Connect (OSTI)

    Tomoyuki Uwaba; Masahiro Ito; Kozo Katsuyama; Bruce J. Makenas; David W. Wootan; Jon Carmack

    2011-05-01

    The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39 × 1026 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

  19. Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups

    SciTech Connect (OSTI)

    Uwaba, Tomoyuki; Ito, Masahiro; Mizuno, Tomoyasu; Katsuyama, Kozo; Makenas, Bruce J.; Wootan, David W.; Carmack, Jon

    2011-06-16

    The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39E26 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

  20. 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.

    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.

  1. Greenhouse Gases into Gold

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

    Turning Greenhouse Gases into Gold Greenhouse Gases into Gold NERSC simulations reveal reaction mechanism behind CO₂ conversion into carbon-neutral fuels and chemicals November 6, 2013 Contact: Kathy Kincade, +1 510 495 2124, kkincade@lbl.gov Environmentalists have long lamented the destructive effects of greenhouse gases, with carbon dioxide (CO2) often accused of being the primary instigator of global climate change. As a result, numerous efforts are under way to find ways to prevent,

  2. THERMAL EVALUATION OF THE USE OF BWR MOX SNF IN THE WASTE PACKAGE DESIGN (SCPB: N/A)

    SciTech Connect (OSTI)

    H. Wang

    1997-01-23

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24, 5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR and 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. (2) Characterize the conceptual 44 BWR and 24 BWR Uncanistered Fuel (UCF) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the WP Design, if used with SNF designed for a MOX fuel cycle, do not preclude WP compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the conceptual WP design with disposal container which is loaded with BWR MOX SNF under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation, and to provide the required guidance to determining the major design issues for future design efforts, and to show that the BWR MOX SNF loaded WP performance is similar to an WP loaded with commercial BWR SNF.

  3. IMPACT OF FISSION PRODUCTS IMPURITY ON THE PLUTONIUM CONTENT IN PWR MOX FUELS

    SciTech Connect (OSTI)

    Gilles Youinou; Andrea Alfonsi

    2012-03-01

    This report presents the results of a neutronics analysis done in response to the charter IFCA-SAT-2 entitled 'Fuel impurity physics calculations'. This charter specifies that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies (UOX SNF) is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate PWR MOX fuel assemblies. Only non-gaseous FP have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1). This mixture of Pu and FP is called PuFP. Note that, in this preliminary analysis, the FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.

  4. Development of an integrated, unattended assay system for LWR-MOX fuel pellet trays

    SciTech Connect (OSTI)

    Stewart, J.E.; Hatcher, C.R.; Pollat, L.L.

    1994-08-01

    Four identical unattended plutonium assay systems have been developed for use at the new light-water-reactor mixed oxide (LWR-MOX) fuel fabrication facility at Hanau, Germany. The systems provide quantitative plutonium verification for all MOX pellet trays entering or leaving a large, intermediate store. Pellet-tray transport and storage systems are highly automated. Data from the ``I-Point`` (information point) assay systems will be shared by the Euratom and International Atomic Energy Agency (IAEA) Inspectorates. The I-Point system integrates, for the first time, passive neutron coincidence counting (NCC) with electro-mechanical sensing (EMS) in unattended mode. Also, provisions have been made for adding high-resolution gamma spectroscopy. The system accumulates data for every tray entering or leaving the store between inspector visits. During an inspection, data are analyzed and compared with operator declarations for the previous inspection period, nominally one month. Specification of the I-point system resulted from a collaboration between the IAEA, Euratom, Siemens, and Los Alamos. Hardware was developed by Siemens and Los Alamos through a bilateral agreement between the German Federal Ministry of Research and Technology (BMFT) and the US DOE. Siemens also provided the EMS subsystem, including software. Through the USSupport Program to the IAEA, Los Alamos developed the NCC software (NCC COLLECT) and also the software for merging and reviewing the EMS and NCC data (MERGE/REVIEW). This paper describes the overall I-Point system, but emphasizes the NCC subsystem, along with the NCC COLLECT and MERGE/REVIEW codes. We also summarize comprehensive testing results that define the quality of assay performance.

  5. NREL Named Corporation of Year by the Rocky Mountain Minority Supplier

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

    Development Council - News Releases | NREL Named Corporation of Year by the Rocky Mountain Minority Supplier Development Council March 26, 2010 A minority business advocacy group has named the U.S. Department of Energy's National Renewable Energy Laboratory as its corporation of the year, citing NREL's contracts with minority-owned businesses and its outreach to them. The award was determined by heads of minority-owned businesses who are members of the Rocky Mountain Minority Supplier

  6. Derivatized gold clusters and antibody-gold cluster conjugates

    DOE Patents [OSTI]

    Hainfeld, J.F.; Furuya, F.R.

    1994-11-01

    Antibody- or antibody fragment-gold cluster conjugates are shown wherein the conjugate size can be as small as 5.0 nm. Methods and reagents are disclosed in which antibodies, Fab' or F(ab')[sub 2] fragments are covalently bound to a stable cluster of gold atoms. The gold clusters may contain 6, 8, 9, 11, 13, 55 or 67 gold atoms in their inner core. The clusters may also contain radioactive gold. The antibody-cluster conjugates are useful in electron microscopy applications as well as in clinical applications that include imaging, diagnosis and therapy. 7 figs.

  7. Derivatized gold clusters and antibody-gold cluster conjugates

    DOE Patents [OSTI]

    Hainfeld, James F.; Furuya, Frederic R.

    1994-11-01

    Antibody- or antibody fragment-gold cluster conjugates are shown wherein the conjugate size can be as small as 5.0 nm. Methods and reagents are disclosed in which antibodies, Fab' or F(ab').sub.2 fragments thereof are covalently bound to a stable cluster of gold atoms. The gold clusters may contain 6, 8, 9, 11, 13, 55 or 67 gold atoms in their inner core. The clusters may also contain radioactive gold. The antibody-cluster conjugates are useful in electron microscopy applications as well as in clinical applications that include imaging, diagnosis and therapy.

  8. Remote-controlled NDA (nondestructive assay) systems for feed and product storage at an automated MOX (mixed oxide) facility

    SciTech Connect (OSTI)

    Menlove, H.O.; Augustson, R.H.; Ohtani, T.; Seya, M.; Takahashi, S.; Abedin-Zadeh, R.; Hassan, B.; Napoli, S.

    1989-01-01

    Nondestructive assay (NDA) systems have been developed for use in an automated mixed oxide (MOX) fabrication facility. Unique features have been developed for the NDA systems to accommodate robotic sample handling and remote operation. In addition, the systems have been designed to obtain International Atomic Energy Agency inspection data without the need for an inspector at the facility at the time of the measurements. The equipment is being designed to operate continuously in an unattended mode with data storage for periods of up to one month. The two systems described in this paper include a canister counter for the assay of MOX powder at the input to the facility and a capsule counter for the assay of complete liquid-metal fast breeder reactor fuel assemblies at the output of the plant. The design, performance characteristics, and authentication of the two systems will be described. The data related to reliability, precision, and stability will be presented. 5 refs., 10 figs., 4 tabs.

  9. GOLD PRESSURE VESSEL SEAL

    DOE Patents [OSTI]

    Smith, A.E.

    1963-11-26

    An improved seal between the piston and die member of a piston-cylinder type pressure vessel is presented. A layer of gold, of sufficient thickness to provide an interference fit between the piston and die member, is plated on the contacting surface of at least one of the members. (AEC)

  10. Monte-Carlo Code (MCNP) Modeling of the Advanced Test Reactor Applicable to the Mixed Oxide (MOX) Test Irradiation

    SciTech Connect (OSTI)

    G. S. Chang; R. C. Pederson

    2005-07-01

    Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a burnup of 50 GWd/t. The MOX fuel was fabricated at Los Alamos National Laboratory by a master-mix process and has been irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). Previous withdrawals of the same fuel have occurred at 9, 21, 30, and 40 GWd/t. Oak Ridge National Laboratory (ORNL) manages this test series for the Department of Energys Fissile Materials Disposition Program (FMDP). The fuel burnup analyses presented in this study were performed using MCWO, a welldeveloped tool that couples the Monte Carlo transport code MCNP with the isotope depletion and buildup code ORIGEN-2. MCWO analysis yields time-dependent and neutron-spectrum-dependent minor actinide and Pu concentrations for the ATR small I-irradiation test position. The purpose of this report is to validate both the Weapons-Grade Mixed Oxide (WG-MOX) test assembly model and the new fuel burnup analysis methodology by comparing the computed results against the neutron monitor measurements.

  11. Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 2 -- Degraded mode calculations

    SciTech Connect (OSTI)

    Goluoglu, S.; Angers, L.; Davis, J.W.; Stockman, H.; Gottlieb, P.; Montierth, L.M.

    1999-07-01

    The authors provide the degraded criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test facility (FFTF) in the potential Monitored Geologic Repository (MGR) at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is a mixture of uranium and plutonium oxides and is representative of the mixed-oxide fuel (MOX) group. The analyses were performed according to the disposal criticality analysis methodology that was documented in the topical report submitted to the US nuclear Regulatory Commission (YMP/TR-004Q). The methodology includes analyzing the geochemical and physical processes that can breach the waste package and degrade the waste forms. This paper summarizes the results of geochemistry degradation analysis and the criticality calculations using the degradation products.

  12. Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

    SciTech Connect (OSTI)

    Koenig, Werner; Baumann, Roland

    2007-07-01

    In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

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

    SciTech Connect (OSTI)

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

    2012-07-26

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

  14. Options for converting excess plutonium to feed for the MOX fuel fabrication facility

    SciTech Connect (OSTI)

    Watts, Joe A; Smith, Paul H; Psaras, John D; Jarvinen, Gordon D; Costa, David A; Joyce, Jr., Edward L

    2009-01-01

    The storage and safekeeping of excess plutonium in the United States represents a multibillion-dollar lifecycle cost to the taxpayers and poses challenges to National Security and Nuclear Non-Proliferation. Los Alamos National Laboratory is considering options for converting some portion of the 13 metric tons of excess plutonium that was previously destined for long-term waste disposition into feed for the MOX Fuel Fabrication Facility (MFFF). This approach could reduce storage costs and security ri sks, and produce fuel for nuclear energy at the same time. Over the course of 30 years of weapons related plutonium production, Los Alamos has developed a number of flow sheets aimed at separation and purification of plutonium. Flow sheets for converting metal to oxide and for removing chloride and fluoride from plutonium residues have been developed and withstood the test oftime. This presentation will address some potential options for utilizing processes and infrastructure developed by Defense Programs to transform a large variety of highly impure plutonium into feedstock for the MFFF.

  15. Time cycle analysis and simulation of material flow in MOX process layout

    SciTech Connect (OSTI)

    Chakraborty, S.; Saraswat, A.; Danny, K.M.; Somayajulu, P.S.; Kumar, A.

    2013-07-01

    The (U,Pu)O{sub 2} MOX fuel is the driver fuel for the upcoming PFBR (Prototype Fast Breeder Reactor). The fuel has around 30% PuO{sub 2}. The presence of high percentages of reprocessed PuO{sub 2} necessitates the design of optimized fuel fabrication process line which will address both production need as well as meet regulatory norms regarding radiological safety criteria. The powder pellet route has highly unbalanced time cycle. This difficulty can be overcome by optimizing process layout in terms of equipment redundancy and scheduling of input powder batches. Different schemes are tested before implementing in the process line with the help of a software. This software simulates the material movement through the optimized process layout. The different material processing schemes have been devised and validity of the schemes are tested with the software. Schemes in which production batches are meeting at any glove box location are considered invalid. A valid scheme ensures adequate spacing between the production batches and at the same time it meets the production target. This software can be further improved by accurately calculating material movement time through glove box train. One important factor is considering material handling time with automation systems in place.

  16. The New Gold Standard: Environmental Management Introduces the...

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

    The New Gold Standard: Environmental Management Introduces the First LEED Gold Industrial Facility The New Gold Standard: Environmental Management Introduces the First LEED Gold ...

  17. Two stroke homogenous charge compression ignition engine with pulsed air supplier

    DOE Patents [OSTI]

    Clarke, John M.

    2003-08-05

    A two stroke homogenous charge compression ignition engine includes a volume pulsed air supplier, such as a piston driven pump, for efficient scavenging. The usage of a homogenous charge tends to decrease emissions. The use of a volume pulsed air supplier in conjunction with conventional poppet type intake and exhaust valves results in a relatively efficient scavenging mode for the engine. The engine preferably includes features that permit valving event timing, air pulse event timing and injection event timing to be varied relative to engine crankshaft angle. The principle use of the invention lies in improving diesel engines.

  18. Surface-stabilized gold nanocatalysts

    DOE Patents [OSTI]

    Dai, Sheng [Knoxville, TN; Yan, Wenfu [Oak Ridge, TN

    2009-12-08

    A surface-stabilized gold nanocatalyst includes a solid support having stabilizing surfaces for supporting gold nanoparticles, and a plurality of gold nanoparticles having an average particle size of less than 8 nm disposed on the stabilizing surfaces. The surface-stabilized gold nanocatalyst provides enhanced stability, such as at high temperature under oxygen containing environments. In one embodiment, the solid support is a multi-layer support comprising at least a first layer having a second layer providing the stabilizing surfaces disposed thereon, the first and second layer being chemically distinct.

  19. Gold Nanoparticles by Alfalfa Plants

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

    Jorge Gardea-Torresdey, University of Texas at El Paso In the well-known Greek legend the touch of King Midas would convert anything to metallic gold. Recently, a team working at SSRL lead by Professor Jorge Gardea-Torresdey from the University of Texas at El Paso have shown that ordinary alfalfa plants can accumulate very small particles (nanoparticles) of metallic gold (1). The best-known materials that contain nanoparticles of metallic gold are gold colloids. These lack the familiar metallic

  20. HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX

    SciTech Connect (OSTI)

    Kyser, E. A.; King, W. D.

    2012-07-31

    Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after ~4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

  1. HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX

    SciTech Connect (OSTI)

    Kyser, E.; King, W.

    2012-04-25

    Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after {approx}4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

  2. BlackGold Biofuels | Open Energy Information

    Open Energy Info (EERE)

    BlackGold Biofuels Jump to: navigation, search Name: BlackGold Biofuels Place: Philadelphia, Pennsylvania Zip: 19107 Product: Philadelphia-based developer of a waste...

  3. Tracking Individual Gold Nanoparticles | The Ames Laboratory

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

    Tracking Individual Gold Nanoparticles Researchers have developed a new way to track gold nanorods as they move around and re-orient themselves on metal surfaces, with ...

  4. Gold Standard Program Model | Open Energy Information

    Open Energy Info (EERE)

    Standard Program Model Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Gold Standard Program Model AgencyCompany Organization: The Gold Standard Foundation Sector:...

  5. Antibody-gold cluster conjugates

    DOE Patents [OSTI]

    Hainfeld, J.F.

    1988-06-28

    Antibody- or antibody fragment-gold cluster conjugates are shown wherein the conjugate size can be about 5.0 nm. Methods and reagents are disclosed in which antibodies or Fab' fragments thereof are covalently bound to a stable cluster of gold atoms. 2 figs.

  6. Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.

    SciTech Connect (OSTI)

    Salay, Michael; Gauntt, Randall O.; Lee, Richard Y.; Powers, Dana Auburn; Leonard, Mark Thomas

    2011-01-01

    Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four accident phases and for release fractions of nine chemical classes of radionuclides as calculated with the MELCOR 1.8.5 accident analysis computer code. The accident phases are those defined in the NUREG-1465 Source Term - gap release, in-vessel release, ex-vessel release, and late in-vessel release. Important differences among the accident source terms derived here and the NUREG-1465 Source Term are not attributable to either fuel burnup or use of MOX fuel. Rather, differences among the source terms are due predominantly to improved understanding of the physics of core meltdown accidents. Heat losses from the degrading reactor core prolong the process of in-vessel release of radionuclides. Improved understanding of the chemistries of tellurium and cesium under reactor accidents changes the predicted behavior characteristics of these radioactive elements relative to what was assumed in the derivation of the NUREG-1465 Source Term. An additional radionuclide chemical class has been defined to account for release of cesium as cesium molybdate which enhances molybdenum release relative to other metallic fission products.

  7. Prediction of an arc-tunable Weyl Fermion metallic state in MoxW1-xTe2

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Chang, Tay-Rong; Xu, Su-Yang; Chang, Guoqing; Lee, Chi-Cheng; Huang, Shin-Ming; Wang, BaoKai; Bian, Guang; Zheng, Hao; Sanchez, Daniel S.; Belopolski, Ilya; et al

    2016-02-15

    A Weyl semimetal is a new state of matter that hosts Weyl fermions as emergent quasiparticles. The Weyl fermions correspond to isolated points of bulk band degeneracy, Weyl nodes, which are connected only through the crystal’s boundary by exotic Fermi arcs. The length of the Fermi arc gives a measure of the topological strength, because the only way to destroy the Weyl nodes is to annihilate them in pairs in the reciprocal space. To date, Weyl semimetals are only realized in the TaAs class. Here, we propose a tunable Weyl state in MoxW1₋xTe2 where Weyl nodes are formed by touchingmore » points between metallic pockets. We show that the Fermi arc length can be changed as a function of Mo concentration, thus tuning the topological strength. Lastly,our results provide an experimentally feasible route to realizing Weyl physics in the layered compound MoxW1₋xTe2, where non-saturating magneto-resistance and pressure-driven superconductivity have been observed.« less

  8. " by Type of Supplier, Census Region, Census Division, Industry Group,"

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

    3. Average Prices of Purchased Electricity and Steam" " by Type of Supplier, Census Region, Census Division, Industry Group," " and Selected Industries, 1994" " (Estimates in Dollars per Physical Units)" ,," Electricity",," Steam" ,," (kWh)",," (million Btu)" ,,,,,,"RSE" "SIC",,"Utility","Nonutility","Utility","Nonutility","Row"

  9. GOLD: The Genomes Online Database

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Kyrpides, Nikos; Liolios, Dinos; Chen, Amy; Tavernarakis, Nektarios; Hugenholtz, Philip; Markowitz, Victor; Bernal, Alex

    Since its inception in 1997, GOLD has continuously monitored genome sequencing projects worldwide and has provided the community with a unique centralized resource that integrates diverse information related to Archaea, Bacteria, Eukaryotic and more recently Metagenomic sequencing projects. As of September 2007, GOLD recorded 639 completed genome projects. These projects have their complete sequence deposited into the public archival sequence databases such as GenBank EMBL,and DDBJ. From the total of 639 complete and published genome projects as of 9/2007, 527 were bacterial, 47 were archaeal and 65 were eukaryotic. In addition to the complete projects, there were 2158 ongoing sequencing projects. 1328 of those were bacterial, 59 archaeal and 771 eukaryotic projects. Two types of metadata are provided by GOLD: (i) project metadata and (ii) organism/environment metadata. GOLD CARD pages for every project are available from the link of every GOLD_STAMP ID. The information in every one of these pages is organized into three tables: (a) Organism information, (b) Genome project information and (c) External links. [The Genomes On Line Database (GOLD) in 2007: Status of genomic and metagenomic projects and their associated metadata, Konstantinos Liolios, Konstantinos Mavromatis, Nektarios Tavernarakis and Nikos C. Kyrpides, Nucleic Acids Research Advance Access published online on November 2, 2007, Nucleic Acids Research, doi:10.1093/nar/gkm884]

    The basic tables in the GOLD database that can be browsed or searched include the following information:

    • Gold Stamp ID
    • Organism name
    • Domain
    • Links to information sources
    • Size and link to a map, when available
    • Chromosome number, Plas number, and GC content
    • A link for downloading the actual genome data
    • Institution that did the sequencing
    • Funding source
    • Database where information resides
    • Publication status and information

    • 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.

    • DOSE RATES FOR WESTINGHOUSE 17X17 MOX PWR SNF IN A WASTE PACKAGE (SCPB: N/A)

      SciTech Connect (OSTI)

      T.L. Lotz

      1997-01-29

      This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to estimate the dose rate on and near the surface a Multi-Purpose Canister (MPC) PWR waste package (WP) which is loaded with Westinghouse 17 x 17 mixed oxide (MOX) PWR fuel. The 21 PWR MPC WP is used to provide an upper bound for waste package designs since the 12 PWR MPC WP will have a smaller source term and an equivalent amount of shielding. the objectives of this evaluation are to calculate the requested dose rate(s) and document the calculation in a fashion to allow comparisons to other waste forms and WP designs at a future time.

    • Advantages of customer/supplier involvement in the upgrade of River Bend`s IST program

      SciTech Connect (OSTI)

      Womack, R.L.; Addison, J.A.

      1996-12-01

      At River Bend Station, IST testing had problems. Operations could not perform the test with the required repeatability; engineering could not reliably trend test data to detect degradation; licensing was heavily burdened with regulatory concerns; and maintenance could not do preventative maintenance because of poor prediction of system health status. Using Energy`s Total Quality principles, it was determined that the causes were: lack of ownership, inadequate test equipment usage, lack of adequate procedures, and lack of program maintenance. After identifying the customers and suppliers of the IST program data, Energy management put together an upgrade team to address these concerns. These customers and suppliers made up the IST upgrade team. The team`s mission was to supply River Bend with a reliable, functional, industry correct and user friendly IST program. The IST program in place went through a verification process that identified and corrected over 400 individual program discrepancies. Over 200 components were identified for improved testing methods. An IST basis document was developed. The operations department was trained on ASME Section XI testing. All IST tests have been simplified and shortened, due to heavy involvement by operations in the procedure development process. This significantly reduced testing time, resulting in lower cost, less dose and greater system availability.

    • Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-MOX, R2-UO2 and MORGANE/R configurations.

      SciTech Connect (OSTI)

      Zhong, Z.; Klann, R. T.; Nuclear Engineering Division

      2007-08-03

      An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R2-UO2 and MORGANE/R core configuration were completed. The calculation model was generated using the lattice physics code DRAGON. In addition, an initial comparison of calculated values to experimental measurements was performed based on preliminary results for the R1-MOX configuration.

    • Overall Plan for Physics Outlining Steps Necessary for Insertion of the LTA and Operation Using a 1/3 MOX Loaded Core

      SciTech Connect (OSTI)

      Pavlovichev, A.M.

      2001-04-09

      Document issued according to Work Release KI-WR04RTP. P. 00-1 describes physics tasks that are included in the current version of ''Roadmap.Level 2'' concerning Reactor tasks of Weapon-grade plutonium disposition problem for VVER-1000. On this base the objective is to identify the physical tasks in FY2000 and in future as a part of global activities on weapon-grade MOX fuel introduction into VVER-1000.

    • Procedure for matching synfuel users with potential suppliers. Appendix B. Proposed and ongoing synthetic fuel production projects

      SciTech Connect (OSTI)

      1981-08-07

      To assist the Department of Energy, Office of Fuels Conversion (OFC), in implementing the synthetic fuel exemption under the Powerplant and Industrial Fuel Use Act (FUA) of 1978, Resource Consulting Group, Inc. (RCG), has developed a procedure for matching prospective users and producers of synthetic fuel. The matching procedure, which involves a hierarchical screening process, is designed to assist OFC in: locating a supplier for a firm that wishes to obtain a synthetic fuel exemption; determining whether the fuel supplier proposed by a petitioner is technically and economically capable of meeting the petitioner's needs; and assisting the Synthetic Fuels Corporation or a synthetic fuel supplier in evaluating potential markets for synthetic fuel production. A data base is provided in this appendix on proposed and ongoing synthetic fuel production projects to be used in applying the screening procedure. The data base encompasses a total of 212 projects in the seven production technologies.

    • A National Tracking Center for Monitoring Shipments of HEU, MOX, and Spent Nuclear Fuel: How do we implement?

      SciTech Connect (OSTI)

      Mark Schanfein

      2009-07-01

      Nuclear material safeguards specialists and instrument developers at US Department of Energy (USDOE) National Laboratories in the United States, sponsored by the National Nuclear Security Administration (NNSA) Office of NA-24, have been developing devices to monitor shipments of UF6 cylinders and other radioactive materials , . Tracking devices are being developed that are capable of monitoring shipments of valuable radioactive materials in real time, using the Global Positioning System (GPS). We envision that such devices will be extremely useful, if not essential, for monitoring the shipment of these important cargoes of nuclear material, including highly-enriched uranium (HEU), mixed plutonium/uranium oxide (MOX), spent nuclear fuel, and, potentially, other large radioactive sources. To ensure nuclear material security and safeguards, it is extremely important to track these materials because they contain so-called “direct-use material” which is material that if diverted and processed could potentially be used to develop clandestine nuclear weapons . Large sources could be used for a dirty bomb also known as a radioactive dispersal device (RDD). For that matter, any interdiction by an adversary regardless of intent demands a rapid response. To make the fullest use of such tracking devices, we propose a National Tracking Center. This paper describes what the attributes of such a center would be and how it could ultimately be the prototype for an International Tracking Center, possibly to be based in Vienna, at the International Atomic Energy Agency (IAEA).

    • A global approach of the representativity concept: Application on a high-conversion light water reactor MOX lattice case

      SciTech Connect (OSTI)

      Santos, N. D.; Blaise, P.; Santamarina, A.

      2013-07-01

      The development of new types of reactor and the increase in the safety specifications and requirements induce an enhancement in both nuclear data knowledge and a better understanding of the neutronic properties of the new systems. This enhancement is made possible using ad hoc critical mock-up experiments. The main difficulty is to design these experiments in order to obtain the most valuable information. Its quantification is usually made by using representativity and transposition concepts. These theories enable to extract some information about a quantity of interest (an integral parameter) on a configuration, but generally a posteriori. This paper presents a more global approach of this theory, with the idea of optimizing the representativity of a new experiment, and its transposition a priori, based on a multiparametric approach. Using a quadratic sum, we show the possibility to define a global representativity which permits to take into account several quantities of interest at the same time. The maximization of this factor gives information about all quantities of interest. An optimization method of this value in relation to technological parameters (over-clad diameter, atom concentration) is illustrated on a high-conversion light water reactor MOX lattice case. This example tackles the problematic of plutonium experiment for the plutonium aging and a solution through the optimization of both the over-clad and the plutonium content. (authors)

    • An Assessment of the Attractiveness of Material Associated with a MOX Fuel Cycle from a Safeguards Perspective

      SciTech Connect (OSTI)

      Bathke, Charles G; Wallace, Richard K; Ireland, John R; Johnson, M W; Hase, Kevin R; Jarvinen, Gordon D; Ebbinghaus, Bartley B; Sleaford, Brad W; Collins, Brian A; Robel, Martin; Bradley, Keith S; Prichard, Andrew W; Smith, Brian W

      2009-01-01

      This paper is an extension to earlier studies that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, coextraction, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant State and sub-national group capabilities. This study also considers those materials that will be recycled and burned, possibly multiple times, in LWRs [e.g., plutonium in the form of mixed oxide (MOX) fuel]. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a State and provided the highest levels of physical protection to prevent theft by sub-national groups; no 'silver bullet' has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities. The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

    • Biomolecular Assembly of Gold Nanocrystals

      SciTech Connect (OSTI)

      Micheel, Christine Marya

      2005-05-20

      Over the past ten years, methods have been developed to construct discrete nanostructures using nanocrystals and biomolecules. While these frequently consist of gold nanocrystals and DNA, semiconductor nanocrystals as well as antibodies and enzymes have also been used. One example of discrete nanostructures is dimers of gold nanocrystals linked together with complementary DNA. This type of nanostructure is also known as a nanocrystal molecule. Discrete nanostructures of this kind have a number of potential applications, from highly parallel self-assembly of electronics components and rapid read-out of DNA computations to biological imaging and a variety of bioassays. My research focused in three main areas. The first area, the refinement of electrophoresis as a purification and characterization method, included application of agarose gel electrophoresis to the purification of discrete gold nanocrystal/DNA conjugates and nanocrystal molecules, as well as development of a more detailed understanding of the hydrodynamic behavior of these materials in gels. The second area, the development of methods for quantitative analysis of transmission electron microscope data, used computer programs written to find pair correlations as well as higher order correlations. With these programs, it is possible to reliably locate and measure nanocrystal molecules in TEM images. The final area of research explored the use of DNA ligase in the formation of nanocrystal molecules. Synthesis of dimers of gold particles linked with a single strand of DNA possible through the use of DNA ligase opens the possibility for amplification of nanostructures in a manner similar to polymerase chain reaction. These three areas are discussed in the context of the work in the Alivisatos group, as well as the field as a whole.

    • Environmental Stewardship: How Semiconductor Suppliers Help toMeet Energy-Efficiency Regulations and Voluntary Specifications inChina

      SciTech Connect (OSTI)

      Aizhen, Li; Fanara, Andrew; Fridley, David; Merriman, Louise; Ju,Jeff

      2007-01-15

      Recognizing the role that semiconductor suppliers can playin meeting energy-efficiency regulations and voluntary specifications,this paper provides an overview of Chinese policies and implementingbodies; a discussion of current programs, their goals, and effectiveness;and possible steps that can be taken tomeet these energy-efficiencyrequirements while also meeting products' high performance and costgoals.

  1. Gold ink coating of thermocouple sheaths

    DOE Patents [OSTI]

    Ruhl, H. Kenneth

    1992-01-01

    A method is provided for applying a gold ink coating to a thermocouple sheath which includes the steps of electropolishing and oxidizing the surface of the thermocouple sheath, then dipping the sheath into liquid gold ink, and finally heat curing the coating. The gold coating applied in this manner is highly reflective and does not degrade when used for an extended period of time in an environment having a temperature over 1000.degree. F. Depending on the application, a portion of the gold coating covering the tip of the thermocouple sheath is removed by abrasion.

  2. Functionalized Gold Nanoparticles for Rapid, Ultra- sensitive...

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

    The new ORNL method for surface enhanced Raman spectroscopy (SERS) involves synthesizing gold metal nanoparticles that are modified with specific amine groups. The method can be ...

  3. Gold Country Energy | Open Energy Information

    Open Energy Info (EERE)

    Energy Jump to: navigation, search Name: Gold Country Energy Place: Alaska Phone Number: (907) 520-5681 Website: goldcountryenrgy.com Facebook: https:www.facebook.compages...

  4. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G; Croft, Stephen; Swinhoe, Martyn T; Tobin, S. J.; Boyer, B. D.; Menlove, H. O.; Schear, M. A.; Worrall, Andrew

    2010-11-24

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  5. An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle

    SciTech Connect (OSTI)

    Evans, Louise G; Croft, Stephen; Swinhoe, Martyn T; Tobin, S. J.; Menlove, H. O.; Schear, M. A.; Worrall, Andrew

    2011-01-13

    Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

  6. Water and Gold: A Promising Mix for Future Batteries

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

    Water and Gold: A Promising Mix for Future Batteries Water and Gold: A Promising Mix for Future Batteries Berkeley Lab Study Reveals Molecular Structure of Water at Gold Electrodes ...

  7. Maintaining safety class electrical and electronic equipment in the absence of support from original suppliers

    SciTech Connect (OSTI)

    Gantt, D.A.

    1991-05-01

    In the absence of a large market for nuclear-qualified equipment, many manufactures no longer provide the level of support necessary to maintain equipment, which they originally manufactured to nuclear qualification standards. As a result, the nuclear facility operator either must purchase commercial grade items and perform necessary conditioning and dedication, or purchase replacement equipment from a limited number of manufacturers of nuclear-qualified equipment. Westinghouse Hanford Company, in operating the Fast Flux Test Facility (FFTF), is using both of these approaches. Instrumentation power supplies and signal conditioners used in the FFTF Reactor Shutdown System of the Plant Protection System (PPS) are standard commercial devices that were qualified for PPS use through tests performed for the original system supplier. The US Department of Energy (DOE) Order 5700.6B mandates that all DOE facilities have a quality assurance program conforming to an appropriate national standard and recommends Quality Assurance Program Requirements for Nuclear Facilities, American National Standards Institute/American Society of Mechanical Engineers (ANSI/ASME) NQA-1, as the standard to implement for reactor facilities. Following the requirements of ANSI/ASME NQA-1 and the guidance in Electric Power Research Institute (EPRI) Report NP-5652, safety system parts can be purchased either as qualified items or as commercial grade items. This document discusses the process of procuring qualified replacement parts. 6 refs., 1 tab.

  8. Ultra-stable Gold Nanocatalysts - Energy Innovation Portal

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

    Find More Like This Return to Search Ultra-stable Gold Nanocatalysts Oak Ridge National ... ORNL researchers successfully deposited and stabilized gold nanoparticles on surfaces of ...

  9. Abrikosov receives Ukrainian Gold Medal | Argonne National Laboratory

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

    Abrikosov receives Ukrainian Gold Medal By Lynn Tefft Hoff * July 28, 2015 Tweet ... Abrikosov has received the Gold Medal of Vernadsky of the National Academy of Sciences of ...

  10. Newest Los Alamos facility receives LEED® Gold certification

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

    Newest facility receives LEED Gold certification Newest Los Alamos facility receives LEED Gold certification The Radiological Laboratory Utility Office Building is first to ...

  11. World's largest single crystal of gold verified by Los Alamos...

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

    Los Alamos verifies largest single gold crystal World's largest single crystal of gold verified by Los Alamos instruments Using Lujan Center's HIPPO instrument, researchers probed ...

  12. Waltzer Receives NNSA Gold Medal Award | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Gold Medal Award June 26, 2014 AMARILLO, Texas--Karl Waltzer, Acting Deputy Manager of the National Nuclear Security Administration's Production Office, has received the NNSA Gold ...

  13. The Structure of Interfacial Water on Gold Electrodes Studied...

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

    The Structure of Interfacial Water on Gold Electrodes Studied by X-ray Absorption Spectroscopy Schematic representation of X-ray absorption measurements at the biased gold water ...

  14. Prediction of the thermodynamic properties of gold, arsenic,...

    Office of Scientific and Technical Information (OSTI)

    The Hydrothermal Chemistry of Gold, Arsenic, Antimony, Mercury and Silver Brad Bessinger ... The HKF equation of state parameters for gold, arsenic, antimony, mercury, and silver ...

  15. Structure of a Thiol Monolayer-Protected Gold Nanoparticle at...

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

    Thiol Monolayer-protected Gold Nanoparticle at 1.1 Resolution Nanometer-size metal ... Historically gold nanoparticles are the best studied, dating back to ancient Rome where ...

  16. For Spitzer building, green is gold | Princeton Plasma Physics...

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

    For Spitzer building, green is gold By Patti Wieser May 26, 2011 Tweet Widget Google Plus ... Laboratory (PPPL), has been certified LEED gold, one of the highest environmental ...

  17. Abraham Presents Secretary's Gold Award to Edward Teller

    Office of Scientific and Technical Information (OSTI)

    November 26, 2002 Abraham Presents Secretary's Gold Award to Edward Teller LIVERMORE, ... National Laboratory, with the Secretary's Gold Award in recognition of his outstanding ...

  18. Reactivity of the Gold/Water Interface During Selective Oxidation...

    Office of Scientific and Technical Information (OSTI)

    the GoldWater Interface During Selective Oxidation Catalysis Citation Details In-Document Search Title: Reactivity of the GoldWater Interface During Selective Oxidation Catalysis ...

  19. Gold-nickel-titanium brazing alloy

    DOE Patents [OSTI]

    Mizuhara, Howard

    1990-07-03

    A brazing alloy in accordance with this invention has the following composition, by weight: 91 to 99% gold, 0.5 to 7% nickel; 0.10 to 2% titanium. Alternatively, with palladium present, the composition is as follows, by weight: 83 to 96% gold; 3 to 10% palladium; 0.5 to 5% nickel; 0.10 to 2% titanium.

  20. Gold-nickel-titanium brazing alloy

    DOE Patents [OSTI]

    Mizuhara, Howard

    1995-01-03

    A brazing alloy in accordance with this invention has the following composition, by weight: 91 to 99 gold, 0.5 to 7% nickel; 0.10 to 2% titanium. Alternatively, with palladium present, the composition is as follows, by weight: 83 to 96% gold; 3 to 10% palladium; 0.5 to 5% nickel; 0.10 to 2% titanium.

  1. gold medal | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    gold medal NNSA Administrator honors nonproliferation research leader Last week DOE Under Secretary for Nuclear Security and NNSA Administrator Lt. Gen. Frank G. Klotz (Ret.) presented the agency's Assistant Deputy Administrator for Nonproliferation Research and Development (R&D) Dr. Rhys Williams with the Distinguished Service Gold Medal Award at a

  2. " Row: NAICS Codes;" " Column: Supplier Sources of Purchased Electricity, Natural Gas, and Steam;"

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

    8 Number of Establishments by Quantity of Purchased Electricity, Natural Gas, and Steam, 2006;" " Level: National Data; " " Row: NAICS Codes;" " Column: Supplier Sources of Purchased Electricity, Natural Gas, and Steam;" " Unit: Establishment Counts." ,,,"Electricity","Components",,,"Natural","Gas","Components",,"Steam","Components"

  3. Coal-gold agglomeration: an alternative separation process in gold recovery

    SciTech Connect (OSTI)

    Akcil, A.; Wu, X.Q.; Aksay, E.K.

    2009-07-01

    Considering the increasing environmental concerns and the potential for small gold deposits to be exploited in the future, the uses of environmentally friendly processes are essential. Recent developments point to the potential for greatly increased plant performance through a separation process that combines the cyanide and flotation processes. In addition, this kind of alternative treatment processes to the traditional gold recovery processes may reduce the environmental risks of present small-scale gold mining. Gold recovery processes that applied to different types of gold bearing ore deposits show that the type of deposits plays an important role for the selection of mineral processing technologies in the production of gold and other precious metals. In the last 25 years, different alternative processes have been investigated on gold deposits located in areas where environmental issues are a great concern. In 1988, gold particles were first recovered by successful pilot trial of coal-gold agglomeration (CGA) process in Australia. The current paper reviews the importance of CGA in the production of gold ore and identifies areas for further development work.

  4. Gel Electrophoresis of Gold-DNA Nanoconjugates

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Pellegrino, T.; Sperling, R. A.; Alivisatos, A. P.; Parak, W. J.

    2007-01-01

    Gold-DNA conjugates were investigated in detail by a comprehensive gel electrophoresis study based on 1200 gels. A controlled number of single-stranded DNA of different length was attached specifically via thiol-Au bonds to phosphine-stabilized colloidal gold nanoparticles. Alternatively, the surface of the gold particles was saturated with single stranded DNA of different length either specifically via thiol-Au bonds or by nonspecific adsorption. From the experimentally determined electrophoretic mobilities, estimates for the effective diameters of the gold-DNA conjugates were derived by applying two different data treatment approaches. The first method is based on making a calibration curve for the relation between effectivemore » diameters and mobilities with gold nanoparticles of known diameter. The second method is based on Ferguson analysis which uses gold nanoparticles of known diameter as reference database. Our study shows that effective diameters derived from gel electrophoresis measurements are affected with a high error bar as the determined values strongly depend on the method of evaluation, though relative changes in size upon binding of molecules can be detected with high precision. Furthermore, in this study, the specific attachment of DNA via gold-thiol bonds to Au nanoparticles is compared to nonspecific adsorption of DNA. Also, the maximum number of DNA molecules that can be bound per particle was determined.« less

  5. Colloidal-gold electrosensor measuring device

    DOE Patents [OSTI]

    Wegner, Steven; Harpold, Michael A.; McCaffrey, Terence M.; Morris, Susan E.; Wojciechowski, Marek; Zhao, Junguo; Henkens, Robert W.; Naser, Najih; O'Daly, John P.

    1995-01-01

    The present invention provides a new device for use in measuring lead levels in biological and environmental samples. Using square wave coulometry and colloidal gold particles impregnated on carbon electrodes, the present invention provides a rapid, reliable, portable and inexpensive means of detecting low lead levels. The colloidal gold modified electrodes have microelectrode array characteristics and produce significantly higher stripping detection signals for lead than are produced at bulk gold electrode surfaces. The method is effective in determining levels of lead down to at least 5 .mu.g/dL in blood samples as small as 10 .mu.L.

  6. Colloidal-gold electrosensor measuring device

    DOE Patents [OSTI]

    Wegner, S.; Harpold, M.A.; McCaffrey, T.M.; Morris, S.E.; Wojciechowski, M.; Zhao, J.; Henkens, R.W.; Naser, N.; O`Daly, J.P.

    1995-11-21

    The present invention provides a new device for use in measuring lead levels in biological and environmental samples. Using square wave coulometry and colloidal gold particles impregnated on carbon electrodes, the present invention provides a rapid, reliable, portable and inexpensive means of detecting low lead levels. The colloidal gold modified electrodes have microelectrode array characteristics and produce significantly higher stripping detection signals for lead than are produced at bulk gold electrode surfaces. The method is effective in determining levels of lead down to at least 5 {micro}g/dL in blood samples as small as 10 {micro}L. 9 figs.

  7. Electrochemical control of creep in nanoporous gold

    SciTech Connect (OSTI)

    Ye, Xing-Long; Jin, Hai-Jun

    2013-11-11

    We have investigated the mechanical stability of nanoporous gold (npg) in an electrochemical environment, using in situ dilatometry and compression experiments. It is demonstrated that the gold nano-ligaments creep under the action of surface stress which leads to spontaneous volume contractions in macroscopic npg samples. The creep of npg, under or without external forces, can be controlled electrochemically. The creep rate increases with increasing potential in double-layer potential region, and deceases to almost zero when the gold surface is adsorbed with oxygen. Surprisingly, we also noticed a correlation between creep and surface diffusivity, which links the deformation of nanocrystals to mobility of surface atoms.

  8. MOX Fabrication Isolation Considerations

    SciTech Connect (OSTI)

    Eric L. Shaber; Bradley J Schrader

    2005-08-01

    This document provides a technical position on the preferred level of isolation to fabricate demonstration quantities of mixed oxide transmutation fuels. The Advanced Fuel Cycle Initiative should design and construct automated glovebox fabrication lines for this purpose. This level of isolation adequately protects the health and safety of workers and the general public for all mixed oxide (and other transmutation fuel) manufacturing efforts while retaining flexibility, allowing parallel development and setup, and minimizing capital expense. The basis regulations, issues, and advantages/disadvantages of five potential forms of isolation are summarized here as justification for selection of the preferred technical position.

  9. The New Gold Standard: Environmental Management Introduces the First LEED

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

    Gold Industrial Facility | Department of Energy The New Gold Standard: Environmental Management Introduces the First LEED Gold Industrial Facility The New Gold Standard: Environmental Management Introduces the First LEED Gold Industrial Facility September 13, 2012 - 1:02pm Addthis The 200 West Groundwater Treatment Facility is shown here after completion of construction this summer. | Photo courtesy of Zachary Carter with Mission Support Alliance (MSA) at Hanford. The 200 West Groundwater

  10. Gold nanorod melting | Argonne National Laboratory

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

    Gold nanorod melting Share Topic Programs Materials science Materials simulation & theory Nanoscience Surface & interface studies Mathematics, computing, & computer science Modeling, simulation, & visualization Supercomputing & high-performance computing

  11. Interconnecting gold islands with DNA origami

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

    Interconnecting gold islands with DNA origami Authors: Ding, B., Wu, H., Xu, W., Zhao, Z., Liu, Y., Yu, H., and Yan, H. Title: Interconnecting gold islands with DNA origami Source: Nano Lett. Year: 2010 Volume: 10 Pages: 5065-5069 ABSTRACT: Scaffolded DNA origami has recently emerged as a versatile, programmable method to fold DNA into arbitrarily shaped nanostructures that are spatially addressable, with sub-10-nm resolution. Toward functional DNA nanotechnology, one of the key challenges is to

  12. ENDF/B-VII.0, ENDF/B-VI, JEFF-3.1, AND JENDL-3.3 RESULTS FOR UNREFLECTED PLUTONIUM SOLUTIONS AND MOX LATTICES (U)

    SciTech Connect (OSTI)

    MOSTELLER, RUSSELL D.

    2007-02-09

    Previous studies have indicated that ENDF/B-VII preliminary releases {beta}-2 and {beta}-3, predecessors to the recent initial release of ENDF/B-VII.0, produce significantly better overall agreement with criticality benchmarks than does ENDF/B-VI. However, one of those studies also suggests that improvements still may be needed for thermal plutonium cross sections. The current study substantiates that concern by examining criticality benchmarks for unreflected spheres of plutonium-nitrate solutions and for slightly and heavily borated mixed-oxide (MOX) lattices. Results are presented for the JEFF-3.1 and JENDL-3.3 nuclear data libraries as well as ENDF/B-VII.0 and ENDF/B-VI. It is shown that ENDF/B-VII.0 tends to overpredict reactivity for thermal plutonium benchmarks over at least a portion of the thermal range. In addition, it is found that additional benchmark data are needed for the deep thermal range.

  13. From a fuel supplier to an active participant: Shell's view of the opportunities offered by a changing power market

    SciTech Connect (OSTI)

    Nyhan, J.

    1998-07-01

    In the last 10 years, the power generation market has seen radical changes. The coming years will see yet more change. Although the pace of change may be uneven across Europe, it is clear that the old reference points for the power generation market are no longer valid. Along with other market players, Shell has re-evaluated the role it wishes to play in the power generation market. Although it has long operated large generation capacity on its own sites, Shell's role has been that of a fuel supplier to monopoly power generation and distribution organizations, which were largely state controlled . Privatization and liberalization have been followed by changing market structures tending to push risk towards the producer. This evolution presents challenges for the normal IPP structure, where market risk is transferred and offers an opportunity for the active participation of the fuel supplier in meeting these challenges. In 1996, Shell decided to embrace the changes in power generation market. Already, significant steps have been taken in markets in Asia, Latin America and in Europe. The differing requirements of each of these markets means there are no standard solutions and requires Shell to devise flexible frameworks which meet the customer's needs. Shell is bringing its significant strengths to the power generation market and looks forward to participating on a world wide scale in the industry at this exciting phase in its development.

  14. Controlling Gold Nanoclusters by Diphospine Ligands

    SciTech Connect (OSTI)

    Chen, Jing; Zhang, Qianfan; Bonaccorso, Timary A.; Williard, Paul G.; Wang, Lai S.

    2014-01-08

    We report the synthesis and structure determination of a new Au22 nanocluster coordinated by six bidentate diphosphine ligands: 1,8-bis(diphenylphosphino) octane (L8 for short). Single crystal x-ray crystallography and electrospray ionization mass spectrometry show that the cluster assembly is neutral and can be formulated as Au22(L8)6. The Au22 core consists of two Au11 units clipped together by four L8 ligands, while the additional two ligands coordinate to each Au11 unit in a bidentate fashion. Eight gold atoms at the interface of the two Au11 units are not coordinated by any ligands. Four short gold-gold distances (2.64?2.65 Å) are observed at the interface of the two Au11 clusters as a result of the clamping force of the four clipping ligands and strong electronic interactions. The eight uncoordinated surface gold atoms in the Au22(L8)6 nanocluster are unprecedented in atom-precise gold nanoparticles and can be considered as potential in-situ active sites for catalysis.

  15. Fresh Air That's as Good as Gold | Department of Energy

    Energy Savers [EERE]

    Fresh Air That's as Good as Gold Fresh Air That's as Good as Gold July 8, 2013 - 5:25pm Addthis Brookhaven Lab physicists Peter Sutter, Eli Sutter,and Xiao Tong (left to right) ...

  16. Guided Self-Assembly of Gold Thin Films

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

    Guided Self-Assembly of Gold Thin Films Print Nanoparticles-man-made atoms with unique ... films from highly ordered one--, two- and three-dimensional arrays of gold nanoparticles. ...

  17. Gold Medal Approaches for Obtaining and Using Energy Efficiency...

    Office of Environmental Management (EM)

    Gold Medal Approaches for Obtaining and Using Energy Efficiency Data (101) Gold Medal Approaches for Obtaining and Using Energy Efficiency Data (101) August 11, 2016 1:00PM to ...

  18. Scientists Can Recycle CO2 Using Gold | Department of Energy

    Office of Environmental Management (EM)

    Can Recycle CO2 Using Gold Scientists Can Recycle CO2 Using Gold May 27, 2016 - 9:57am Addthis A new chemical process has the potential to reduce atmospheric CO2 emissions by ...

  19. Going for the Gold (Computer) | Department of Energy

    Energy Savers [EERE]

    Going for the Gold (Computer) March 3, 2009 - 4:00am Addthis John Lippert Last summer I ... EPEAT products are identified as EPEAT-Bronze, EPEAT-Silver, or EPEAT-Gold depending on ...

  20. Guided Self-Assembly of Gold Thin Films

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

    Guided Self-Assembly of Gold Thin Films Guided Self-Assembly of Gold Thin Films Print Wednesday, 21 November 2012 12:18 Nanoparticles-man-made atoms with unique optical, ...

  1. Electronic Structure of Thiol-Covered Gold Nanoparticles: Au102...

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

    Structure of Thiol-Covered Gold Nanoparticles: Au102(MBA)44 Authors: Li, Y., Galli, G., ... properties of thiolate-protected gold nanoparticles Au102(MBA)44 that have ...

  2. World's largest single crystal of gold verified at Los Alamos

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

    World's largest single crystal of gold verified at Los Alamos World's largest single crystal of gold verified at Los Alamos The SCD instrument is used to determine the periodic ...

  3. Rainbows and Leprechauns: Finding Gold in Partnerships (101)...

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

    Rainbows and Leprechauns: Finding Gold in Partnerships (101) Rainbows and Leprechauns: Finding Gold in Partnerships (101) March 17, 2016 1:00PM to 2:30PM EDT

  4. Electrocatalyst Having Gold Monolayers on Platinum Nanoparticle Cores and

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

    Uses Thereof - Energy Innovation Portal Having Gold Monolayers on Platinum Nanoparticle Cores and Uses Thereof Brookhaven National Laboratory Contact BNL About This Technology Publications: PDF Document Publication Stabilization of Platinum Oxygen-Reduction Electrocatalysts Using Gold Clusters (263 KB) <p> Scanning electron micrograph of gold clusters on platinum nanoparticles</p> Scanning electron micrograph of gold clusters on platinum nanoparticles Technology Marketing Summary

  5. Gold-coated nanoparticles for use in biotechnology applications

    DOE Patents [OSTI]

    Berning, Douglas E.; Kraus, Jr., Robert H.; Atcher, Robert W.; Schmidt, Jurgen G.

    2009-07-07

    A process of preparing gold-coated magnetic nanoparticles is disclosed and includes forming a suspension of magnetic nanoparticles within a suitable liquid, adding an amount of a reducible gold compound and a reducing agent to the suspension, and, maintaining the suspension for time sufficient to form gold-coated magnetic nanoparticles.

  6. Gold-coated nanoparticles for use in biotechnology applications

    DOE Patents [OSTI]

    Berning, Douglas E.; Kraus, Jr., Robert H.; Atcher, Robert W.; Schmidt, Jurgen G.

    2007-06-05

    A process of preparing gold-coated magnetic nanoparticles is disclosed and includes forming a suspension of magnetic nanoparticles within a suitable liquid, adding an amount of a reducible gold compound and a reducing agent to the suspension, and, maintaining the suspension for time sufficient to form gold-coated magnetic nanoparticles.

  7. Waltzer Receives NNSA Gold Medal Award | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Waltzer Receives NNSA Gold Medal Award June 26, 2014 Karl Waltzer, Acting Deputy Manager of the National Nuclear Security Administration's Production Office, has received the NNSA Gold Medal Award in recognition of his distinguished achievements in support of national security programs. File Waltzer Receives NNSA Gold Medal Award

  8. High Strength Gold Wire for Microelectronics Miniaturization - Energy

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

    Innovation Portal High Strength Gold Wire for Microelectronics Miniaturization Ames Laboratory Contact AMES About This Technology Technology Marketing Summary ISU and Ames Laboratory researchers have developed a high strength gold wire for use in microelectronics that can maintain its electrical and mechanical properties while permitting miniaturization of microelectronics design. Description Gold alloy wires currently used in microelectronics have limited electrical and mechanical

  9. X-ray laser driven gold targets

    SciTech Connect (OSTI)

    Petrova, Tz. B. Whitney, K. G.; Davis, J.

    2014-03-15

    The femtosecond population dynamics of gold irradiated by a coherent high-intensity (>10{sup 17} W/cm{sup 2}) x-ray laser pulse is investigated theoretically. There are two aspects to the assembled model. One is the construction of a detailed model of platinum-like gold inclusive of all inner-shell states that are created by photoionization of atomic gold and decay either by radiative or Auger processes. Second is the computation of the population dynamics that ensues when an x-ray pulse is absorbed in gold. The hole state generation depends on the intensity and wavelength of the driving x-ray pulse. The excited state populations reached during a few femtosecond timescales are high enough to generate population inversions, whose gain coefficients are calculated. These amplified lines in the emitted x-ray spectrum provide important diagnostics of the radiation dynamics and also suggest a nonlinear way to increase the frequency of the coherent output x-ray pulses relative to the frequency of the driver input x-ray pulse.

  10. APPLICATION OF COLUMN EXTRACTION METHOD FOR IMPURITIES ANALYSIS ON HB-LINE PLUTONIUM OXIDE IN SUPPORT OF MOX FEED PRODUCT SPECIFICATIONS

    SciTech Connect (OSTI)

    Jones, M.; Diprete, D.; Wiedenman, B.

    2012-03-20

    The current mission at H-Canyon involves the dissolution of an Alternate Feedstocks 2 (AFS-2) inventory that contains plutonium metal. Once dissolved, HB-Line is tasked with purifying the plutonium solution via anion exchange, precipitating the Pu as oxalate, and calcining to form plutonium oxide (PuO{sub 2}). The PuO{sub 2} will provide feed product for the Mixed Oxide (MOX) Fuel Fabrication Facility, and the anion exchange raffinate will be transferred to H-Canyon. The results presented in this report document the potential success of the RE resin column extraction application on highly concentrated Pu samples to meet MOX feed product specifications. The original 'Hearts Cut' sample required a 10000x dilution to limit instrument drift on the ICP-MS method. The instrument dilution factors improved to 125x and 250x for the sample raffinate and sample eluent, respectively. As noted in the introduction, the significantly lower dilutions help to drop the total MRL for the analyte. Although the spike recoveries were half of expected in the eluent for several key elements, they were between 94-98% after Nd tracer correction. It is seen that the lower ICD limit requirements for the rare earths are attainable because of less dilution. Especially important is the extremely low Ga limit at 0.12 {mu}g/g Pu; an ICP-MS method is now available to accomplish this task on the sample raffinate. While B and V meet the column A limits, further development is needed to meet the column B limits. Even though V remained on the RE resin column, an analysis method is ready for investigation on the ICP-MS, but it does not mean that V cannot be measured on the ICP-ES at a low dilution to meet the column B limits. Furthermore, this column method can be applicable for ICP-ES as shown in Table 3-2, in that it trims the sample of Pu, decreasing and sometimes eliminating Pu spectral interferences.

  11. Detailed energy distributions in laser-produced plasmas of solid gold and foam gold planar targets

    SciTech Connect (OSTI)

    Dong, Yunsong; Zhang, Lu; Yang, Jiamin; Shang, Wanli

    2013-12-15

    Foam gold was proposed to increase the laser to x-ray conversion efficiency due to its important applications. To understand the mechanism of x-ray enhancement, the detailed energy distributions and plasma profiles for laser-irradiated solid gold and foam gold targets were studied comparatively by hydrodynamic simulations using the code Multi-1D. It is confirmed that the radiation heat wave is subsonic for the normal solid gold target, while supersonic for the foam gold target. The shock wave, which is behind the supersonic radiation heat wave for the foam gold target, generates a plasma temperature gradient with high temperature near the shock wave front to produce an additional net outward radiation for enhancement of the x-ray emission. Much larger inward plasma velocity is also driven by the shock wave as an initial plasma velocity for the laser deposition and electron thermal conduct zone, which decreases the expanding plasma kinetic energy loss and helps to increase the x-ray radiation.

  12. Antifungal activity of gold nanoparticles prepared by solvothermal method

    SciTech Connect (OSTI)

    Ahmad, Tokeer; Wani, Irshad A.; Lone, Irfan H.; Ganguly, Aparna; Manzoor, Nikhat; Ahmad, Aijaz; Ahmed, Jahangeer; Al-Shihri, Ayed S.

    2013-01-15

    Graphical abstract: Gold nanoparticles (7 and 15 nm) of very high surface area (329 and 269 m{sup 2}/g) have been successfully synthesized through solvothermal method by using tin chloride and sodium borohydride as reducing agents. As-prepared gold nanoparticles shows very excellent antifungal activity against Candida isolates and activity increases with decrease in the particle size. Display Omitted Highlights: ► Effect of reducing agents on the morphology of gold nanoparticles. ► Highly uniform and monodisperse gold nanoparticles (7 nm). ► Highest surface area of gold nanoparticles (329 m{sup 2/}g). ► Excellent antifungal activity of gold nanoparticles against Candida strains. -- Abstract: Gold nanoparticles have been successfully synthesized by solvothermal method using SnCl{sub 2} and NaBH{sub 4} as reducing agents. X-ray diffraction studies show highly crystalline and monophasic nature of the gold nanoparticles with face centred cubic structure. The transmission electron microscopic studies show the formation of nearly spherical gold nanoparticles of average size of 15 nm using SnCl{sub 2}, however, NaBH{sub 4} produced highly uniform, monodispersed and spherical gold nanoparticles of average grain size of 7 nm. A high surface area of 329 m{sup 2}/g for 7 nm and 269 m{sup 2}/g for 15 nm gold nanoparticles was observed. UV–vis studies assert the excitations over the visible region due to transverse and longitudinal surface plasmon modes. The gold nanoparticles exhibit excellent size dependant antifungal activity and greater biocidal action against Candida isolates for 7 nm sized gold nanoparticles restricting the transmembrane H{sup +} efflux of the Candida species than 15 nm sized gold nanoparticles.

  13. COMMISSIONING OF RHIC DEUTERON - GOLD COLLISIONS.

    SciTech Connect (OSTI)

    SATOGATA,T.AHRENS,L.BAI,M.BEEBE-WANG,J.

    2003-05-12

    Deuteron and gold beams have been accelerated to a collision energy of {radical}s = 200 GeV/u in the Relativistic Heavy Ion Collider (RHIC), providing the first asymmetric-species collisions of this complex. Necessary changes for this mode of operation include new ramping software and asymmetric crossing angle geometries. This paper reviews machine performance, problem encountered and their solutions, and accomplishments during the 16 weeks of ramp-up and operations.

  14. Update: US oil-import market. 1982 top 7 suppliers to US import market: how their shares changed since 1973

    SciTech Connect (OSTI)

    Not Available

    1983-03-09

    This issue updates the Energy Detente 7/09/82, which tracked US oil imports since the Arab Oil Embargo. Since then, the phrase oil glut became common even among cautious market analysts as many exporters, hard-pressed for petrodollars, produced much more than the market was prepared to absorb. To examine how the US import market has adjusted to this continued buyers market, the top seven suppliers of 1982 are tracked backwards through time. A graph shows the 1982 reversal of Mexico's and Saudi Arabia's positions in this market. The three main reasons for Mexico's strong present position in the US market are: crude costs and corresponding refined value; proximity to US refining centers; and strategic importance of Mexico's economic stability through oil sales. Interviews with various US refiners and other market observers confirm that these elements will persist during 1983, regardless of significant price cuts among OPEC and other producers. It is believed that the profitability of running heavy Maya crude in sophisticated plants will continue to look optimistic, and that Mexican crude sales to the Strategic Petroleum Reserve implies US government interest in Mexico's economic recovery, and in its stability in the light of civil wars being waged in Central America. This issue presents the Energy Detente (1) fuel price/tax series and (2) industrial fuel prices for March 1983 for countries of the Eastern Hemisphere. 6 figures, 8 tables.

  15. Another Gold for PPPL: Laboratory Wins 2nd Gold GreenBuy Award | Princeton

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

    Plasma Physics Lab Another Gold for PPPL: Laboratory Wins 2nd Gold GreenBuy Award By Jeanne Jackson DeVoe September 23, 2013 Tweet Widget Google Plus One Share on Facebook Teodora Todorova cleans a restroom with green products like HydroxiPro, which is 100 percent bio-based. The hand soap in PPPL's rest rooms is made mostly of vegetable-based glycerin and aloe. The paper products are made from 70 to 100 percent recycled products and the hand towels are composted at PPPL. Teodora Todorova

  16. Newest Los Alamos facility receives LEED® Gold certification

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

    Newest facility receives LEED® Gold certification Newest Los Alamos facility receives LEED® Gold certification The Radiological Laboratory Utility Office Building is first to achieve both the Leadership in Energy and Environmental Design status and LEED Gold certification. June 13, 2012 Radiological Laboratory Utility Office Building Radiological Laboratory Utility Office Building Contact Kim Powell Communications Office (505) 695-6159 Email LOS ALAMOS, New Mexico, June 13, 2012-Los Alamos

  17. Synthesis of porous gold nanoshells by controlled transmetallation reaction

    SciTech Connect (OSTI)

    Pattabi, Manjunatha M, Krishnaprabha

    2015-06-24

    Aqueous synthesis of porous gold nanoshells in one step is carried out through controlled transmetallation (TM) reaction using a naturally available egg shell membrane (ESM) as a barrier between the sacrificial silver particles (AgNPs) and the gold precursor solution (HAuCl{sub 4}). The formation of porous gold nanoshells via TM reaction is inferred from UV-Vis spectroscopy and the scanning electron microscopic (SEM) studies.

  18. Molecular Structure of Water at Gold Electrodes Revealed

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

    Molecular Structure of Water at Gold Electrodes Revealed Molecular Structure of Water at Gold Electrodes Revealed Print Wednesday, 25 March 2015 00:00 The structure of liquid water has been intensely studied, but until recently, it has not been clear what happens to it when a surface is introduced. ALS researchers have now made a first-ever observation of the molecular structure of liquid water at a gold surface under different charging conditions. This marks the first time that the scientific

  19. World's largest single crystal of gold verified at Los Alamos

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

    World's largest single crystal of gold verified at Los Alamos World's largest single crystal of gold verified at Los Alamos The SCD instrument is used to determine the periodic atomic arrangement or crystal structure of single crystals, both natural and synthetic. April 7, 2014 Neutron diffraction data collected on the single-crystal diffraction (SCD) instrument at the Lujan Center, from the Venezuelan gold sample, indicate that the sample is a single crystal. Neutron diffraction data collected

  20. Los Alamos explores hybrid ultrasmall gold nanocluster for enzymatic fuel

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

    cells Hybrid ultrasmall gold nanocluster for enzymatic fuel cells Los Alamos explores hybrid ultrasmall gold nanocluster for enzymatic fuel cells With fossil-fuel sources dwindling, better biofuel cell design is a strong candidate in the energy field. September 24, 2015 Gold nanoclusters (~1 nm) are efficient mediators of electron transfer between co-self-assembled enzymes and carbon nanotubes in an enzyme fuel cell. The efficient electron transfer from this quantized nano material minimizes

  1. Earned Value Management System Gold Card | Department of Energy

    Energy Savers [EERE]

    Gold Card Earned Value Management System Gold Card Earned Value Management (EVM) is a systematic approach to the integration and measurement of cost, schedule, and technical (scope) accomplishments on a project or task. It provides both the government and contractors the ability to examine detailed schedule information, critical program and technical milestones, and cost data. Formulas and Terminology "Gold Card" -- September 2011 (92.71 KB) Key Resources PMCDP EVMS PARS IIe FPD

  2. Rainbows and Leprechauns: Finding Gold in Partnerships (101)

    Broader source: Energy.gov [DOE]

    Better Buildings Residential Network Peer Exchange Call Series: Rainbows and Leprechauns: Finding Gold in Partnerships (101), March 17, 2016, call slides and discussion summary.

  3. Microsoft PowerPoint - Marion Gold.Providence.Infrastructure...

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

    DOE Quadrennial Energy Review Providence, Rhode Island Monday, April 21, 2014 Marion S. Gold, Ph.D. Commissioner Rhode Island Office of Energy Resources RI Office of Energy ...

  4. Rainbows and Leprechauns: Finding Gold in Partnerships (101)...

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

    Peer Exchange Call Series: Rainbows and Leprechauns: Finding Gold in Partnerships (101), March 17, 2016, call slides and discussion summary. Call Slides and Discussion Summary ...

  5. Laminin receptor specific therapeutic gold nanoparticles (198AuNP...

    Office of Scientific and Technical Information (OSTI)

    prostate cancer Citation Details In-Document Search Title: Laminin receptor specific therapeutic gold nanoparticles (198AuNP-EGCg) show efficacy in treating prostate cancer ...

  6. Los Alamos explores hybrid ultrasmall gold nanocluster for enzymatic...

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

    Los Alamos explores hybrid ultrasmall gold nanocluster for enzymatic fuel cells With fossil-fuel sources dwindling, better biofuel cell design is a strong candidate in the energy ...

  7. Understanding Interactions between Manganese Oxide and Gold That...

    Office of Scientific and Technical Information (OSTI)

    Water Oxidation Prev Next Title: Understanding Interactions between Manganese Oxide and Gold That Lead to Enhanced Activity for Electrocatalytic Water Oxidation ...

  8. Argonne APCF achieves LEED Gold rating | Argonne National Laboratory

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

    Laboratory's Advanced Protein Characterization Facility (APCF) has received the U.S. Green Building Council's Leadership in Energy and Environmental Design (LEED) Gold...

  9. Guided Self-Assembly of Gold Thin Films

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

    ... It does not require chemical modification to any of the components in the composite system ... of many materials besides gold, making it well suited for scalable manufacturing. ...

  10. BioGold Fuels Corporation | Open Energy Information

    Open Energy Info (EERE)

    through joint ventures a lower-cost, higher-output system for the production of diesel fuel derived from Municipal Solid Waste ("MSW"). References: BioGold Fuels...

  11. Active Geothermal Systems And Associated Gold Deposits In The...

    Open Energy Info (EERE)

    Geothermal Systems And Associated Gold Deposits In The Great Basin Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Paper: Active Geothermal Systems...

  12. Charles E. Messick receives the Administrator's Gold Award |...

    National Nuclear Security Administration (NNSA)

    E. Messick receives the Administrator's Gold Award | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  13. Gold River, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    (Redirected from Gold River, CA) Jump to: navigation, search Equivalent URI DBpedia Coordinates 38.6262937, -121.2466156 Show Map Loading map... "minzoom":false,"mappingservic...

  14. NNSA Nevada Support Facility Receives LEED Gold Certificate ...

    National Nuclear Security Administration (NNSA)

    Nevada Support Facility as Leadership in Energy and Environmental Design (LEED) Gold ... The LEED rating system, developed by the U.S. Green Building Council, is the foremost ...

  15. Federal Electronics Challenge Gold Award | Department of Energy

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

    On June 18th, DOE Headquarters was presented the Federal Electronics Challenge Gold Award for exemplary performance in Green Computing, including green procurement, energy ...

  16. Gold nanoparticle formation in diamond-like carbon using two different methods: Gold ion implantation and co-deposition of gold and carbon

    SciTech Connect (OSTI)

    Salvadori, M. C.; Teixeira, F. S.; Araujo, W. W. R.; Sgubin, L. G.; Cattani, M.; Spirin, R. E.; Brown, I. G.

    2012-10-01

    We describe work in which gold nanoparticles were formed in diamond-like carbon (DLC), thereby generating a Au-DLC nanocomposite. A high-quality, hydrogen-free DLC thin film was formed by filtered vacuum arc plasma deposition, into which gold nanoparticles were introduced using two different methods. The first method was gold ion implantation into the DLC film at a number of decreasing ion energies, distributing the gold over a controllable depth range within the DLC. The second method was co-deposition of gold and carbon, using two separate vacuum arc plasma guns with suitably interleaved repetitive pulsing. Transmission electron microscope images show that the size of the gold nanoparticles obtained by ion implantation is 3-5 nm. For the Au-DLC composite obtained by co-deposition, there were two different nanoparticle sizes, most about 2 nm with some 6-7 nm. Raman spectroscopy indicates that the implanted sample contains a smaller fraction of sp{sup 3} bonding for the DLC, demonstrating that some sp{sup 3} bonds are destroyed by the gold implantation.

  17. Method for aqueous gold thiosulfate extraction using copper-cyanide pretreated carbon adsorption

    SciTech Connect (OSTI)

    Young, Courtney; Melashvili, Mariam; Gow, Nicholas V

    2013-08-06

    A gold thiosulfate leaching process uses carbon to remove gold from the leach liquor. The activated carbon is pretreated with copper cyanide. A copper (on the carbon) to gold (in solution) ratio of at least 1.5 optimizes gold recovery from solution. To recover the gold from the carbon, conventional elution technology works but is dependent on the copper to gold ratio on the carbon.

  18. Prime Supplier Sales Volumes

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

    68,630.0 13,240.0 86,640.3 268,510.4 16,445.7 1,775.8 10,716.9 28,938.4 February ... 176,320.8 12,607.6 89,733.9 278,662.3 17,600.5 1,816.9 11,099.4...

  19. Prime Supplier Sales Volumes

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

    1,515.4 24,168.6 49,958.8 205,642.8 21,325.8 3,583.5 13,512.4 38,421.7 February ... 150,955.0 13,660.5 51,987.1 216,602.6 25,038.0 1,397.6 14,426.9...

  20. Prime Supplier Report

    Reports and Publications (EIA)

    2016-01-01

    Measures primary petroleum product deliveries into the states where they are locally marketed and consumed.

  1. Prime Supplier Sales Volumes

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

    47,959.1 11,050.9 67,812.0 226,822.0 21,260.7 1,818.7 15,161.7 38,241.1 February ... 154,899.9 10,617.6 70,698.9 236,216.5 22,197.4 1,690.4 15,506.0...

  2. Prime Supplier Sales Volumes

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

    ... 33,392.4 470.2 21,307.9 55,170.5 232,813.4 4,156.4 108,849.1 345,818.8 June ... 34,545.7 496.8 22,352.4 57,394.8...

  3. Prime Supplier Sales Volumes

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

    - 5,035.0 12,682.6 September ... 57,075.9 - 34,030.7 91,106.6 7,194.8 - 4,922.6 12,117.4 October ... 58,271.3 -...

  4. Prime Supplier Sales Volumes

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

    ... 168,286.2 12,993.4 79,830.4 261,110.0 20,869.6 1,997.4 13,951.7 36,818.8 December ... 177,468.1 14,403.3 85,758.4 277,629.8...

  5. Prime Supplier Sales Volumes

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

    180.4 - 1,565.8 1,746.2 December ... 1,672.1 - 10,357.9 12,030.0 182.5 - 1,583.4 1,765.9 1998 Average ... 1,692.9 - 10,184.7...

  6. Prime Supplier Sales Volumes

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

    - 52,118.5 135,620.8 September ... 10,627.5 - 9,403.4 20,030.9 76,222.0 - 49,285.1 125,507.2 October ... 11,834.2 -...

  7. Supplier, Vendor Forms

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

    LANL seeks to do business with qualified companies that offer value and high quality products and services. Contact Small Business Office (505) 667-4419 Email Form No. Name...

  8. Gold-catalyzed synthesis of carbonates and carbamates from carbon monoxide

    SciTech Connect (OSTI)

    Friend, Cynthia M; Madix, Robert J; Xu, Bingjun

    2015-01-20

    The invention provides a method for producing organic carbonates via the reaction of alcohols and carbon monoxide with oxygen adsorbed on a metallic gold or gold alloy catalyst.

  9. Argonne/EPA system captures mercury from air in gold shops |...

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

    Typical gold shop hood used to purify gold by superheating the goldmercury amalgam until the mercury vaporizes. The vaporized mercury is directed outside the shop into the open...

  10. Seeing Gold Nanoparticles Self-Assemble with in situ Liquid Transmissi...

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

    Seeing Gold Nanoparticles Self-Assemble with in situ Liquid Transmission Electron Microscopy December 15, 2014 Tweet EmailPrint Scientific Achievement The self-assembly of gold...