National Library of Energy BETA

Sample records for disposition field production

  1. Natural Gas Dry Production (Annual Supply & Disposition)

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

    Data Series: Dry Production Supplemental Gaseous Fuels Interstate Receipts Receipts Across U.S. Borders Withdrawals from Underground Storage Consumption Interstate Deliveries Deliveries Across U.S. Borders Injections into Storage Balancing Item Period: Monthly Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Data Series Area 2010 2011 2012 2013 2014 2015 View History U.S. 21,315,507 22,901,879 24,033,266

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

    SciTech Connect (OSTI)

    Marra, J

    2006-01-19

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

  3. DOE/EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/04)

    Office of Environmental Management (EM)

    488 FINAL Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee December 2004 U. S. Department of Energy Oak Ridge Operations 04-049(doc)/120204 04-049(doc)/120204 SCIENCE APPLICATIONS INTERNATIONAL CORPORATION contributed to the preparation of this document and should not be considered an eligible contractor for its review. Environmental Assessment for the U-233 Disposition,

  4. Records Disposition

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

    1988-09-13

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

  5. Records Disposition

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

    1980-05-28

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

  6. Waste and Materials Disposition Information | Department of Energy

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

    Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to

  7. Production optimization in the Provincia field, Colombia

    SciTech Connect (OSTI)

    Blann, J.; Jacobson, L.; Faber, C.

    1989-02-01

    Designing or redesigning production facilities for optimum operation usually results in the generation of maximum profit from an installation. But in older fields, or fields where a short life is expected, design changes may not be a viable option. In such cases, obtaining maximum production within the limits of existing facilities, thereby minimizing new investments, may be an attractive option. This paper discusses application of the latter technique in the Provincia field, Colombia, to optimize oil and gas production within constraints imposed by periodic temporary gas-compression-capacity restrictions and by the configuration of existing oil and gas facilities. The multistep optimization program used at Provincia included improvement of individual well performance, optimization of individual well facilities, fieldwide optimization of surface facilities, and optimization of the field production scheme.

  8. Disposition Schedules | Department of Energy

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

    Disposition Schedules Disposition Schedules keyboard-70506__180.jpg Records Disposition Schedules The DOE Records Disposition Schedules provide the authority for transfer and disposal of records created and maintained by the Department. Disposition Schedules and the citations to the disposition authorities are available at the following links: DOE Administrative Records Schedules -- provides a list of records contained in the NARA General Records Schedule as customized to the needs of the

  9. Charm production in a strong magnetic field

    SciTech Connect (OSTI)

    Machado, C. S.; Navarra, F. S.; Noronha, J.; Oliveira, E. G. de; Strickland, M.

    2014-11-11

    We discuss the effects of a strong magnetic field on B and D mesons, focusing on the changes of the energy levels and the masses of the bound states. Using the Color Evaporation Model we discuss the possible changes in the production of J/? and ?. We briefly comment the recent experimental data.

  10. Field Testing of Pre-Production Prototype Residential Heat Pump...

    Energy Savers [EERE]

    Field Testing of Pre-Production Prototype Residential Heat Pump Water Heaters Field Testing of Pre-Production Prototype Residential Heat Pump Water Heaters Provides and overview of ...

  11. Nuclear Materials Disposition

    Broader source: Energy.gov [DOE]

    In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel.  These are not waste. They are nuclear materials no longer needed for...

  12. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY Request for Records Disposition Authority PDF icon REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Request For Records Disposition Authority Request For Records Disposition Request For Records Disposition Authority

  13. Waste Disposition News | Department of Energy

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

    Waste Disposition News Waste Disposition News April 27, 2016 The WIPP Blue Mine Rescue Team moves through the course in the field competition of the Southwest Regional Mine Rescue Contest. WIPP's Mine Rescue Teams Win Big in Contest CARLSBAD, N.M. - The EM Waste Isolation Pilot Plant (WIPP) Blue Mine Rescue Team was named the overall champion at the Southwest Regional Mine Rescue Contest held in Carlsbad in April. WIPP's Red Mine Rescue Team took first place in the first aid competition. April

  14. EA-1488: Environmental Assessment for the U-233 Disposition, Medical

    Energy Savers [EERE]

    Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee | Department of Energy 88: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge,

  15. ,"U.S. Natural Gas Plant Field Production"

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

    Gas Plant Field Production" "Sourcekey","MNGFPUS1","MPPFPUS1","MLPFPUS1","METFPUS1","MPRFPUS1","MBNFPUS1","MBIFPUS1" "Date","U.S. Gas Plant Production of Natural Gas Liquids ...

  16. ,"Natural Gas Plant Field Production: Natural Gas Liquids "

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

    Field Production: Natural Gas Liquids " ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data...

  17. Conformal field theories at nonzero temperature: Operator product...

    Office of Scientific and Technical Information (OSTI)

    nonzero temperature: Operator product expansions, Monte Carlo, and holography Citation Details In-Document Search Title: Conformal field theories at nonzero temperature: Operator ...

  18. Facility Disposition Safety Strategy RM

    Broader source: Energy.gov [DOE]

    The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the facility documentation, preparations or...

  19. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

    Energy Savers [EERE]

    Storage and Transportation Overview Steve Marschman Field Demonstration Lead Idaho National Laboratory NEET ASI Review Meeting September 17, 2014 Used Fuel Disposition Today's Discussion n Our R&D Objectives n What Guides Our Work n FY14 and FY15 Work - Full-Scale High Burn-Up Demo - Experiments - Transportation - Analysis Used Fuel Disposition 3 Overall Objectives * Develop the technical bases to demonstrate the continued safe and secure storage of used nuclear fuel for extended

  20. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Lemons, T.R.

    1991-12-31

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

  1. Portsmouth Waste Disposition Record of Decision | Department...

    Office of Environmental Management (EM)

    Waste Disposition Record of Decision Portsmouth Waste Disposition Record of Decision The Ohio Environmental Protection Agency (Ohio EPA) and the U.S. Department of Energy (DOE) ...

  2. Savannah River Site Waste Disposition Project

    Office of Environmental Management (EM)

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

  3. Fission Product Transmutation in Mixed Radiation Fields

    SciTech Connect (OSTI)

    Harmon, Frank; Burgett, Erick; Starovoitova, Valeriia; Tsveretkov, Pavel

    2015-01-15

    Work under this grant addressed a part of the challenge facing the closure of the nuclear fuel cycle; reducing the radiotoxicity of lived fission products (LLFP). It was based on the possibility that partitioning of isotopes and accelerator-based transmutation on particular LLFP combined with geological disposal may lead to an acceptable societal solution to the problem of management. The feasibility of using photonuclear processes based on the excitation of the giant dipole resonance (GDR) by bremsstrahlung radiation as a cost effective transmutation method was accessed. The nuclear reactions of interest: (?,xn), (n,?), (?,p) can be induced by bremsstrahlung radiation produced by high power electron accelerators. The driver of these processes would be an accelerator that produces a high energy and high power electron beam of ~ 100 MeV. The major advantages of such accelerators for this purpose are that they are essentially available off the shelf and potentially would be of reasonable cost for this application. Methods were examined that used photo produced neutrons or the bremsstrahlung photons only, or use both photons and neutrons in combination for irradiations of selected LLFP. Extrapolating the results to plausible engineering scale transmuters it was found that the energy cost for 129I and 99Tc transmutation by these methods are about 2 and 4%, respectively, of the energy produced from 1000MWe.

  4. Uranium Downblending and Disposition Project Technology Readiness

    Energy Savers [EERE]

    Assessment | Department of Energy Uranium Downblending and Disposition Project Technology Readiness Assessment Uranium Downblending and Disposition Project Technology Readiness Assessment Full Document and Summary Versions are available for download PDF icon Uranium Downblending and Disposition Project Technology Readiness Assessment PDF icon Summary - Uranium233 Downblending and Disposition Project More Documents & Publications Compilation of TRA Summaries EA-1574: Final Environmental

  5. DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM |

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

    Department of Energy DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM Listed on this document are all the disposition authorities which are under the moratorium on the destruction of health related records as of March 2008. PDF icon DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 17: CARTOGRAPHIC, AERIAL PHOTOGRAPHIC,

  6. FS65 Disposition Option Report

    SciTech Connect (OSTI)

    Wenz, Tracy R.

    2015-09-25

    This report outlines the options for dispositioning the MOX fuel stored in FS65 containers at LANL. Additional discussion regarding the support equipment for loading and unloading the FS65 transport containers is included at the end of the report.

  7. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY RS-Weapons X-Rays PDF icon REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications...

  8. Locally smeared operator product expansions in scalar field theory

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

    Monahan, Christopher; Orginos, Kostas

    2015-04-01

    We propose a new locally smeared operator product expansion to decompose non-local operators in terms of a basis of smeared operators. The smeared operator product expansion formally connects nonperturbative matrix elements determined numerically using lattice field theory to matrix elements of non-local operators in the continuum. These nonperturbative matrix elements do not suffer from power-divergent mixing on the lattice, which significantly complicates calculations of quantities such as the moments of parton distribution functions, provided the smearing scale is kept fixed in the continuum limit. The presence of this smearing scale complicates the connection to the Wilson coefficients of the standardmore » operator product expansion and requires the construction of a suitable formalism. We demonstrate the feasibility of our approach with examples in real scalar field theory.« less

  9. Disposition of Uranium Oxide From Conversion of Depleted Uranium Hexafluoride

    Broader source: Energy.gov [DOE]

    This Supplemental Environmental Impact Statement (SEIS) for Disposition of Uranium Oxide Conversion Product Generated from Conversion of DOE’s Inventory of Depleted Uranium Hexafluoride [DOE/EIS-0359-S1 and DOE/EIS-0360-S1] evaluates the environmental impacts resulting from the disposition of up to 800,000 metric tons of uranium oxide resulting from the conversion of depleted uranium hexafluoride (DUF6) at the Department’s two operating DUF6 conversion facilities in Paducah, Kentucky and Portsmouth, Ohio.

  10. Request For Records Disposition | Department of Energy

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

    Request For Records Disposition Request For Records Disposition Spent Nuclear Fuels PDF icon Request For Records Disposition More Documents & Publications Report on Separate Disposal of Defense High-Level Radioactive Waste The Report To The President And The Congress By The Secretary Of Energy On The Need For A Second Repository A REPORT TO CONGRESS BY THE SECRETARY OF ENERGY

  11. Product component genealogy modeling and field-failure prediction

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

    King, Caleb; Hong, Yili; Meeker, William Q.

    2016-04-13

    Many industrial products consist of multiple components that are necessary for system operation. There is an abundance of literature on modeling the lifetime of such components through competing risks models. During the life-cycle of a product, it is common for there to be incremental design changes to improve reliability, to reduce costs, or due to changes in availability of certain part numbers. These changes can affect product reliability but are often ignored in system lifetime modeling. By incorporating this information about changes in part numbers over time (information that is readily available in most production databases), better accuracy can bemore » achieved in predicting time to failure, thus yielding more accurate field-failure predictions. This paper presents methods for estimating parameters and predictions for this generational model and a comparison with existing methods through the use of simulation. Our results indicate that the generational model has important practical advantages and outperforms the existing methods in predicting field failures.« less

  12. Transmission, storage and export of product from the Arun field

    SciTech Connect (OSTI)

    Soeryanto, J.

    1982-01-01

    Arun liquefied natural gas (LNG) plant is the second Indonesian LNG plant. It began production in August 1978. Plant feed is supplied from the Arun gas condensate field located ca. 30 km from the plant. The overall complex is designed to produced LNG equivalent to 18 million cu m/day of gas, and 12,000 cu m/day of stabilized condensate. Field facilities produce and separate gas and condensate for delivery through separate pipelines to the LNG plant. At the plant, condensate is stabilized and stored in four 78,705-cu m floating roof tanks and shipped in conventional tankers, moored off shore. The gas is treated, dehydrated, and liquefied. Gas treating is accomplished by the Benfield Hi-pure Process. Liquefaction is accomplished using the propane pre-cooled multi-component refrigerant process. Refrigerant components required for the liquefaction process are produced from 2 fractionation trains.

  13. Usefulness of effective field theory for boosted Higgs production

    SciTech Connect (OSTI)

    Dawson, S.; Lewis, I. M.; Zeng, Mao

    2015-04-07

    The Higgs + jet channel at the LHC is sensitive to the effects of new physics both in the total rate and in the transverse momentum distribution at high pT. We examine the production process using an effective field theory (EFT) language and discussing the possibility of determining the nature of the underlying high-scale physics from boosted Higgs production. The effects of heavy color triplet scalars and top partner fermions with TeV scale masses are considered as examples and Higgs-gluon couplings of dimension-5 and dimension-7 are included in the EFT. As a byproduct of our study, we examine the region of validity of the EFT. Dimension-7 contributions in realistic new physics models give effects in the high pT tail of the Higgs signal which are so tiny that they are likely to be unobservable.

  14. DOE Records Disposition Schedule Changes | Department of Energy

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

    Records Disposition Schedule Changes DOE Records Disposition Schedule Changes Disposition Schedule Changes PDF icon DOE Records Disposition Schedule Changes More Documents & Publications DOE Administrative Records Schedules Changes DOERS Records Schedule Cross Index to DOE Administrative Records Disposition Schedules ADMINISTRATIVE RECORDS SCHEDULE 18: SECURITY, EMERGENCY PLANNING, AND SAFETY RECORDS

  15. Personal Property Disposition - Community Reuse Organizations (CROs) |

    Energy Savers [EERE]

    Department of Energy Personal Property Disposition - Community Reuse Organizations (CROs) Personal Property Disposition - Community Reuse Organizations (CROs) MEMORANDUM TO: DISTRIBUTION FROM: Michael Owen (signed) Director, Office of Worker and Community Transition Department of Energy Washington, DC 20505 January 22, 2003 Disposition of Excess Personal Property BACKGROUND AND PURPOSE CROs have been operating asset conversion and personal property transfer programs since shortly after the

  16. Surplus Plutonium Disposition Supplemental Environmental Impact Statement |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Surplus Plutonium Disposition Supplemental Environmental Impact Statement ANNOUNCEMENT - March 30, 2016 Today I signed the Record of Decision (ROD) for Disposition of Surplus Non-Pit Plutonium for the Final Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (Supplemental EIS). The ROD outlines the Department of Energy's National Nuclear Security Administration (DOE/NNSA) path forward to prepare and process six metric tons

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

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

    Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to ...

  18. Weapons Dismantlement and Disposition NNSS Capabilities

    SciTech Connect (OSTI)

    Pat Arnold

    2011-12-01

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

  19. EIS-0283: Surplus Plutonium Disposition Environmental Impact...

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

    10, 2008 EIS-0283: Amended Record of Decision Surplus Plutonium Disposition: Waste Solidification Building November 26, 2008 EIS-0283-SA-02: Supplement Analysis Surplus Plutonium...

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

    Office of Environmental Management (EM)

    Office of Environmental Management (DOE-EM) External Technical Review of the Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN Why DOE-EM Did...

  1. 8.0 FACILITY DISPOSITION PROCESS

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

    8-1 8.0 FACILITY DISPOSITION PROCESS 8.1 INTRODUCTION The facility disposition process defines the approach by which DOE, with involvement of the lead regulatory agencies, will take a facility from operational status to its end state condition (final disposition) at Hanford. This is accomplished by the completion of facility transition, surveillance and maintenance (S&M), and disposition phase activities. The process is designed to integrate DOE Order 430.1B, U.S. Department of Energy Real

  2. Consent Order, Uranium Disposition Services, LLC - NCO-2010-01...

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

    Uranium Disposition Services, LLC - NCO-2010-01 Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 March 26, 2010 Issued to Uranium Disposition Services, LLC related to ...

  3. Field Testing of Pre-Production Prototype Residential Heat Pump Water Heaters

    Broader source: Energy.gov [DOE]

    Provides and overview of field testing of 18 pre-production prototype residential heat pump water heaters

  4. Used Fuel Disposition Stainless Steel Canister Challenges Steve Marschman

    Energy Savers [EERE]

    Stainless Steel Canister Challenges Steve Marschman Field Demonstration Lead Idaho National Laboratory NEET ASI Review Meeting September 17, 2014 Used Fuel Disposition Date 2 Overview n Chloride-Induced Stress Corrosion Cracking (CISCC) has been identified by the NRC as a potential degradation mechanism for welded, stainless steel used fuel canisters (not bare fuel storage casks). n Systems are difficult to inspect and monitor n Three in-service inspections have been performed - Results

  5. Request For Records Disposition Authority | Department of Energy

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

    Fossil Energy Equity Re-determination Records PDF icon Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Inspection ...

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

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

    Disposition Excess Equipment from Alpha 1 (4605) Y-12 Site Office Oak Ridge, Anderson County, Tennessee The proposed action is to characterize and disposition equipment that was...

  7. Topic Index to the DOE Administrative Records Disposition Schedules...

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

    Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative...

  8. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    Lawrence Berkeley National Laboratory: Cyclotron Records PDF icon REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY...

  9. Integrated Tool Development for Used Fuel Disposition Natural...

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

    Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase...

  10. PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...

    Energy Savers [EERE]

    records inventory and disposition schedules PDF icon PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) More Documents & Publications DOE F 1324.10...

  11. Used Fuel Disposition Used Nuclear Fuel Storage and Transportation

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

    ASI Review Meeting September 17, 2014 Used Fuel Disposition Today's Discussion n Our ... - Transportation - Analysis Used Fuel Disposition 3 Overall Objectives * Develop ...

  12. Dismantlement and Disposition | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Dismantlement and Disposition Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires increased investments across the nuclear security enterprise. Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires increased investments across the nuclear security enterprise. Weapons dismantlement [1] and disposition are major parts of

  13. ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Moore, E.

    2013-07-17

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

  14. disposition

    National Nuclear Security Administration (NNSA)

    MT of surplus HEU has been down-blended for use as fuel in Tennessee Valley Authority reactors (completed in October 2011);

  15. 22 MT of surplus HEU has been set aside for...

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

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

    Monthly Supply and Disposition Balance (Billion Cubic Feet) Period: Monthly Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Data Series Sep-15 Oct-15 Nov-15 Dec-15 Jan-16 Feb-16 View History Gross Withdrawals 2,750 2,818 2,744 2,824 2,823 2,669 1973-2016 Marketed Production 2,407 2,456 2,376 2,441 2,448 2,323 1973-2016 NGPL Production, Gaseous Equivalent 144 153 149 151 148 140 1973-2016 Dry Production 2,263 2,303 2,227 2,290

  17. Independent Analysis of Alternatives for Disposition of the Idaho Calcined High-Level Waste Inventory Volume 1- Summary Report

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Idaho Field Office and the Office of Environmental Management (EM) chartered an independent Analysis of Alternatives for the Idaho Calcine Disposition Project (CDP), part of the overall Idaho Cleanup Project.

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

    Broader source: Energy.gov [DOE]

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

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

    Energy Savers [EERE]

    Department of Energy to the Integrated Facility Disposition Project Major Risk Factors to the Integrated Facility Disposition Project The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). PDF icon Major Risk Factors to the Integrated Facility Disposition Project More Documents & Publications Major Risk Factors Integrated Facility Disposition Project - Oak Ridge

  20. Excess plutonium disposition using ALWR technology

    SciTech Connect (OSTI)

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

    1993-02-01

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

  21. Waste Disposition Update by Christine Gelles

    Office of Environmental Management (EM)

    Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o ...

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

    Broader source: Energy.gov [DOE]

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

  2. NRC comprehensive records disposition schedule. Revision 3

    SciTech Connect (OSTI)

    1998-02-01

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

  3. Request For Records Disposition Authority | Department of Energy

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

    Records Schedule Contractor Checks PDF icon Request For Records Disposition Authority More Documents & Publications DOE-STD-4001-2000 DOE Records Disposition Schedule Changes Audit Letter Report: INS-L-07-05

  4. H. R. S. 182 - Reservation and Disposition of Government Mineral...

    Open Energy Info (EERE)

    (Redirected from Hawaii Revised Statute 182-1, Definitions for Reservation and Disposition of Government Mineral Rights)...

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

    SciTech Connect (OSTI)

    Allender, J; Moore, E

    2010-07-14

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

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

    SciTech Connect (OSTI)

    J. T. Beck

    2007-04-26

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

  7. Characterizing Surplus US Plutonium for Disposition - 13199

    SciTech Connect (OSTI)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-07-01

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

  8. Characterizing surplus US plutonium for disposition

    SciTech Connect (OSTI)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-02-26

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

  9. A theoretical model of subsidence caused by petroleum production: Big Hill Field, Jefferson County, Texas

    SciTech Connect (OSTI)

    Hill, D.W.; Sharp, J.M. Jr. . Dept. of Geological Sciences)

    1993-02-01

    In the Texas Gulf Coastal Plain, there is a history of oil and gas production extending over 2 to 5 decades. Concurrent with this production history, there has been unprecedented population growth accompanied by vastly increased groundwater demands. Land subsidence on both local and regional bases in this geologic province has been measured and predicted in several studies. The vast majority of these studies have addressed the problem from the standpoint of groundwater usage while only a few have considered the effects of oil and gas production. Based upon field-based computational techniques (Helm, 1984), a model has been developed to predict land subsidence caused by oil and gas production. This method is applied to the Big Hill Field in Jefferson County, Texas. Inputs include production data from a series of wells in this field and lithologic data from electric logs of these same wells. Outputs include predicted amounts of subsidence, the time frame of subsidence, and sensitivity analyses of compressibility and hydraulic conductivity estimates. Depending upon estimated compressibility, subsidence, to date, is predicted to be as high as 20 cm. Similarly, depending upon estimated vertical hydraulic conductivity, the time frame may be decades for this subsidence. These same methods can be applied to other oil/gas fields with established production histories as well as new fields when production scenarios are assumed. Where subsidence has been carefully measured above petroleum reservoir, the model may be used inversely to calculate sediment compressibilities.

  10. Exemptions from OSHA`s PSM rule oil and gas field production

    SciTech Connect (OSTI)

    West, H.H. [Shawnee Engineers, Houston, TX (United States); Landes, S. [SH Landes, Houston, TX (United States)

    1995-12-31

    The OSHA Process Safety Management (PSM) regulation, OSHA 1910.119, contains a number of exemptions which are specifically directed to the low hazard situations typically found in the field production facilities of the oil and gas industry. Each relevant PSM exemption is discussed with particular regard to the requirements of hydrocarbon production facilities.

  11. CHARACTERIZATION OF SURPLUS PLUTONIUM FOR DISPOSITION OPTIONS

    SciTech Connect (OSTI)

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

    2008-07-15

    The United States (U.S.) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Except for materials that remain in use for programs outside of national defense, including programs for nuclear-energy development, the surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. Some items will be disposed as transuranic waste, low-level waste, or spent fuel. The remaining surplus plutonium will be managed through: (1) the Mixed Oxide (MOX) Fuel Fabrication Facility (FFF), to be constructed at the Savannah River Site (SRS), where the plutonium will be converted to fuel that will be irradiated in civilian power reactors and later disposed to a high-level waste (HLW) repository as spent fuel; (2) the SRS H-Area facilities, by dissolving and transfer to HLW systems, also for disposal to the repository; or (3) alternative immobilization techniques that would provide durable and secure disposal. From the beginning of the U.S. program for surplus plutonium disposition, DOE has sponsored research to characterize the surplus materials and to judge their suitability for planned disposition options. Because many of the items are stored without extensive analyses of their current chemical content, the characterization involves three interacting components: laboratory sample analysis, if available; non-destructive assay data; and rigorous evaluation of records for the processing history for items and inventory groups. This information is collected from subject-matter experts at inventory sites and from materials stabilization and surveillance programs, in cooperation with the design agencies for the disposition facilities. This report describes the operation and status of the characterization program.

  12. ,"Natural Gas Plant Field Production: Natural Gas Liquids "

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

    Field Production: Natural Gas Liquids " ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Field Production: Natural Gas Liquids ",16,"Monthly","2/2016","1/15/1981" ,"Release Date:","4/29/2016" ,"Next Release Date:","5/31/2016" ,"Excel

  13. Pampo, Linguado, and Badejo Fields: Their discoveries, appraisals, and early production systems

    SciTech Connect (OSTI)

    Tigre, C.A.; Possato, S.

    1983-05-01

    The three oil fields Pampo, Linguado and Badejo are located in the southwesternmost known producing areas of the offshore Brazilian Campos Basin. They were discovered as a result of reflection seismic survey and produce from fractured lower Cretaceous (Neocomian) basalts, coquinas of the Aptian Lagoa Feia Formation, carbonates of the Albian Macae Formation and from Eocene sandstones of the Carapebus Member of the Campos Formation. This work describes the prospects, their results, the main reservoirs, correlations, continuity and diagenetic problems. Two early production systems are in operation engaged in gathering a better knowledge of the fields for the planning of a definitive production system.

  14. Dynamics of particle production by strong electric fields in non-Abelian plasmas

    SciTech Connect (OSTI)

    Dawson, John F.; Mihaila, Bogdan; Cooper, Fred

    2010-03-01

    We develop methods for computing the dynamics of fermion pair production by strong color electric fields including backreaction using the semiclassical Boltzmann-Vlasov (B-V) equation. We implement the Schwinger pair production by inserting a source term in the B-V equation which includes Pauli-Blocking effects. We present numerical results for a model with SU(2) symmetries in (1+1) Cartesian dimensions.

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

    Energy Savers [EERE]

    Department of Energy WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting

  16. Major Risk Factors to the Integrated Facility Disposition Project

    Office of Environmental Management (EM)

    Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization,

  17. Analysis of Surplus Weapons-Grade Plutonium Disposition Options...

    National Nuclear Security Administration (NNSA)

    that cost analysis along with a preliminary study of the potential options, which will serve as a basis for determining the most efficient path forward for plutonium disposition. ...

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

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

    Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear...

  19. Table 6. Source and disposition of photovoltaic module shipments...

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

    Source and disposition of photovoltaic module shipments, 2013" "(peak kilowatts)" "Module ... Administration, Form EIA-63B, 'Annual Photovoltaic CellModule Shipments Report.'rounding. ...

  20. Used Fuel Disposition Campaign Phase I Ring Compression Testing...

    Energy Savers [EERE]

    Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign ... of the technical basis for extended storage and transportation of high-burnup fuel. ...

  1. REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy

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

    Nuclear Power Plant Docket Records PDF icon REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications PIA - Savannah River Remediation Accreditation Boundary (SRR AB) ...

  2. EIS-0327: Disposition of Scrap Metals Programmatic EIS | Department...

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

    intent to prepare an EIS that would evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel)...

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

    Energy Savers [EERE]

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

  4. DEPARTMENT OF ENERGY Surplus Plutonium Disposition AGENCY: National...

    National Nuclear Security Administration (NNSA)

    6450-01-P DEPARTMENT OF ENERGY Surplus Plutonium Disposition AGENCY: National Nuclear Security Administration, U.S. Department of Energy. ACTION: Record of Decision. SUMMARY: On ...

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

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

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

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

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

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

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

    Office of Environmental Management (EM)

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

  8. Used Fuel Disposition R&D Documents | Department of Energy

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

    28, 2012 Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear...

  9. Request For Records Disposition Autnority | Department of Energy

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

    Posters depicting Department of Energy facilities, research projects, security awareness themes, and related topics. PDF icon Request For Records Disposition Autnority More...

  10. Processing and Disposition of Remote-Handled Transuranic Liquid...

    Office of Scientific and Technical Information (OSTI)

    Liquid Waste Generated at Oak Ridge National Laboratory Citation Details In-Document Search Title: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated ...

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

    Office of Environmental Management (EM)

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

  12. field

    National Nuclear Security Administration (NNSA)

    09%2A en Ten-Year Site Plans (TYSP) http:nnsa.energy.govaboutusouroperationsinfopsinfopstysp

    field field-type-text field-field-page-name">
  13. field

    National Nuclear Security Administration (NNSA)

    09%2A en Ten-Year Site Plans (TYSP) http:www.nnsa.energy.govaboutusouroperationsinfopsinfopstysp

    field field-type-text field-field-page-name">
  14. Disposition of ORNL's Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Turner, D. W.; DeMonia, B. C.; Horton, L. L.

    2002-02-26

    This paper describes the process of retrieving, repackaging, and preparing Oak Ridge spent nuclear fuel (SNF) for off-site disposition. The objective of the Oak Ridge SNF Project is to safely, reliably, and efficiently manage SNF that is stored on the Oak Ridge Reservation until it can be shipped off-site. The project required development of several unique processes and the design and fabrication of special equipment to enable the successful retrieval, transfer, and repackaging of Oak Ridge SNF. SNF was retrieved and transferred to a hot cell for repackaging. After retrieval of SNF packages, the storage positions were decontaminated and stainless steel liners were installed to resolve the vulnerability of water infiltration. Each repackaged SNF canister has been transferred from the hot cell back to dry storage until off-site shipments can be made. Three shipments of aluminum-clad SNF were made to the Savannah River Site (SRS), and five shipments of non-aluminum-clad SNF are planned to the Idaho National Engineering and Environmental Laboratory (INEEL). Through the integrated cooperation of several organizations including the U.S. Department of Energy (DOE), Bechtel Jacobs Company LLC (BJC), Oak Ridge National Laboratory (ORNL), and various subcontractors, preparations for the disposition of SNF in Oak Ridge have been performed in a safe and successful manner.

  15. The Bulalo geothermal field, Philippines: Reservoir characteristics and response to production

    SciTech Connect (OSTI)

    Clemente, W.C.; Villadolid-Abrigo, F.L.

    1993-10-01

    The Bulalo geothermal field has been operating since 1979, and currently has 330 MWe of installed capacity. The field is associated with a 0.5 Ma dacite dome on the southeastern flank of the Late Pliocene to Quaternary Mt. Makiling stratovolcano. The reservoir occurs within pre-Makiling andesite flows and pyroclastic rocks capped by the volcanic products of Mt. Makiling. Initially, the reservoir was liquid-dominated with a two-phase zone overlying the neutral-pH liquid. Exploitation has resulted in an enlargement of the two-phase zone, return to the reservoir of separated waste liquid that has been injected, scaling in the wellbores and rock formation, and influx of cooler groundwaters. Return of injected waters to the reservoir and scaling have been the major reservoir management concerns. These have been mitigated effectively by relocating injection wells farther away from the production area and by dissolving scale from wells with an acid treatment.

  16. Overview of NETL Field Studies Related to Oil and Gas Production

    Energy Savers [EERE]

    ENERGY lab 18 Aug 2015 Richard Hammack, Monitoring Team Lead USDOE National Energy Technology Laboratory, Pittsburgh, PA Overview of NETL Field Studies Related to Oil and Gas Production DOE Tribal Leaders Forum Denver, Colorado Newfield Exploration, Bakken Petroleum System, North Dakota * Reduce Environmental Impacts * Demonstrate Safe/Reliable Operations * Improve Efficiency of Hydraulic Fracturing Program Objectives * Surface Monitoring - Ambient Air Quality - Air Emissions - Ground Motion -

  17. A review of the Arun field gas production/cycling and LNG export project. [Sumatra, Indonesia

    SciTech Connect (OSTI)

    Alford, M.E.

    1983-03-01

    The Arun field was discovered by Mobil Oil Indonesia Inc. in late 1971 in its Bee block in the Aceh province on the north coast of Sumatra, Indonesia. Mobil's operations in this area are conducted under the terms of a production sharing agreement with Pertamina, the Indonesian state-owned oil and gas enterprise. The scope of operations covered by this paper is from production of gas and raw condensate in the field through stabilization and export of condensate and purification, liquefaction, and export of gas at the LNG plant at Blang Lancang, near Lho Seumawe (Sumatra) Indonesia. Mobil Oil Indonesia, Inc. is the field operator and P.T. Arun NGL Company operates the pipelines and LNG plant facilities. All the facilities which will be described are owned by Pertamina; P.T. Arun is owned by Pertamina, Mobil Oil Indonesia, and Japan Indonesia LNG company (JILCO). JILCO represents the five (5) original Japanese LNG purchasers. Brief descriptions are included of the geology, reservoir geometry, well producing characteristics, field producing and cycling facilities, and the treating, liquefaction and export facilities.

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

    SciTech Connect (OSTI)

    Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

    1993-06-01

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

  19. Integration of the geological/engineering model with production performance for Patrick Draw Field, Wyoming

    SciTech Connect (OSTI)

    Jackson, S.

    1993-03-01

    The NIPER Reservoir Assessment and Characterization Research Program incorporates elements of the near-term, mid-term and long-term objectives of the National Energy Strategy-Advanced Oil Recovery Program. The interdisciplinary NIPER team focuses on barrier island reservoirs, a high priority class of reservoirs, that contains large amounts of remaining oil in place located in mature fields with a high number of shut-in and abandoned wells. The project objectives are to: (1) identify heterogeneities that influence the movement and trapping of reservoir fluids in two examples of shoreline barrier reservoirs (Patrick Draw Field, WY and Bell Creek Field, MT); (2) develop geological and engineering reservoir characterization methods to quantify reservoir architecture and predict mobile oil saturation distribution for application of targeted infill drilling and enhanced oil recovery (EOR) processes; and (3) summarize reservoir and production characteristics of shoreline barrier reservoirs to determine similarities and differences. The major findings of the research include: (1) hydrogeochemical analytical techniques were demonstrated to be an inexpensive reservoir characterization tool that provides information on reservoir architecture and compartmentalization; (2) the formation water salinity in Patrick Draw Field varies widely across the field and can result in a 5 to 12% error in saturation values calculated from wireline logs if the salinity variations and corresponding resistivity values are not accounted for; and (3) an analysis of the enhanced oil recovery (EOR) potential of Patrick Draw Field indicates that CO[sub 2] flooding in the Monell Unit and horizontal drilling in the Arch Unit are potential methods to recover additional oil from the field.

  20. Integration of the geological/engineering model with production performance for Patrick Draw Field, Wyoming

    SciTech Connect (OSTI)

    Jackson, S.

    1993-03-01

    The NIPER Reservoir Assessment and Characterization Research Program incorporates elements of the near-term, mid-term and long-term objectives of the National Energy Strategy-Advanced Oil Recovery Program. The interdisciplinary NIPER team focuses on barrier island reservoirs, a high priority class of reservoirs, that contains large amounts of remaining oil in place located in mature fields with a high number of shut-in and abandoned wells. The project objectives are to: (1) identify heterogeneities that influence the movement and trapping of reservoir fluids in two examples of shoreline barrier reservoirs (Patrick Draw Field, WY and Bell Creek Field, MT); (2) develop geological and engineering reservoir characterization methods to quantify reservoir architecture and predict mobile oil saturation distribution for application of targeted infill drilling and enhanced oil recovery (EOR) processes; and (3) summarize reservoir and production characteristics of shoreline barrier reservoirs to determine similarities and differences. The major findings of the research include: (1) hydrogeochemical analytical techniques were demonstrated to be an inexpensive reservoir characterization tool that provides information on reservoir architecture and compartmentalization; (2) the formation water salinity in Patrick Draw Field varies widely across the field and can result in a 5 to 12% error in saturation values calculated from wireline logs if the salinity variations and corresponding resistivity values are not accounted for; and (3) an analysis of the enhanced oil recovery (EOR) potential of Patrick Draw Field indicates that CO{sub 2} flooding in the Monell Unit and horizontal drilling in the Arch Unit are potential methods to recover additional oil from the field.

  1. Seasonal Production and Emission of Methane from Rice Fields, Final Report

    SciTech Connect (OSTI)

    Khalil, M. Aslam K.; Rasmussen,Reinhold A.

    2002-12-03

    B 139 - Methane (CH4) is a greenhouse gas regarded second only to carbon dioxide in its ability to cause global warming. Methane is important because of its relatively fast increase, and also because it is, per molecule, some 60 times more effective than carbon dioxide in causing global warming. The largest present anthropogenic sources of methane are rice fields, cattle and biomass burning. The global emissions from these sources are still not well known. In the middle 1980s there were few available data on methane emissions from rice fields leading to estimates of a global source between 100-280 Tg/yr. Extensive worldwide research during the last decade has shown that the global emissions from rice fields are more likely to be in the range of 30-80Tg/yr. While this work has led to a substantial reduction in the estimated emissions, the uncertainty is still quite large, and seriously affects our ability to include methane in integrated assessments for future climate change and environmental management.China dominated estimates of methane emissions from rice fields because it was, and is, the largest producer of rice, and major increases in rice production had taken place in the country over the last several decades. This report summarizes the work in Sichuan Province, China, in each of the following areas: the design of the experiment; the main results on methane emissions from rice fields, delineating the factors controlling emissions; production of methane in the soil; a survey of water management practices in sample of counties in Sichuan province; and results of ambient measurements including data from the background continental site. B139

  2. Topic: Cesium Management and Disposition Alternatives for the Low Activity Waste Pre-Treatment

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

    Department of Energy Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative Records Disposition Schedules PDF icon Topic Index to the DOE Administrative Records Disposition Schedules More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 20: ELECTRONIC RECORDS ADMINISTRATIVE RECORDS SCHEDULE 20: ELECTRONIC RECORDS ADMINISTRATIVE RECORDS SCHEDULE 12: COMMUNICATIONS

  3. Shapiro-like resonance in ultracold molecule production via an oscillating magnetic field

    SciTech Connect (OSTI)

    Liu Bin; Fu Libin; Liu Jie

    2010-01-15

    We study the process of the production of ultracold molecules from ultracold atoms using a sinusoidally oscillating magnetic-field modulation. Our study is based on a two-mode mean-field treatment of the problem. When the magnetic field is resonant roughly with the molecular binding energy, Shapiro-like resonances are observed. Their resonance profiles are well fitted by the Lorentzian functions. The linewidths depend on both the amplitude and the duration of the applied modulations and are found to be dramatically broadened by the thermal dephasing effect. The resonance centers shift due to both the many-body effect and the finite temperature effect. Our theory is consistent with a recent experiment [S. T. Thompson, E. Hodby, and C. E. Wieman, Phys. Rev. Lett. 95, 190404 (2005)]. Our model predicts a 1/3 ceiling for the molecular production yield in uncondensed ultracold atomic clouds for a long coupling time, while for condensed atoms the optimal conversion yield could be beyond the limit.

  4. Electric field induced needle-pulsed arc discharge carbon nanotube production apparatus: Circuitry and mechanical design

    SciTech Connect (OSTI)

    Kia, Kaveh Kazemi; Bonabi, Fahimeh

    2012-12-15

    A simple and low cost apparatus is reported to produce multiwall carbon nanotubes and carbon nano-onions by a low power short pulsed arc discharge reactor. The electric circuitry and the mechanical design details and a micro-filtering assembly are described. The pulsed-plasma is generated and applied between two graphite electrodes. The pulse width is 0.3 {mu}s. A strong dc electric field is established along side the electrodes. The repetitive discharges occur in less than 1 mm distance between a sharp tip graphite rod as anode, and a tubular graphite as cathode. A hydrocarbon vapor, as carbon source, is introduced through the graphite nozzle in the cathode assembly. The pressure of the chamber is controlled by a vacuum pump. A magnetic field, perpendicular to the plasma path, is provided. The results show that the synergetic use of a pulsed-current and a dc power supply enables us to synthesize carbon nanoparticles with short pulsed plasma. The simplicity and inexpensiveness of this plan is noticeable. Pulsed nature of plasma provides some extra degrees of freedom that make the production more controllable. Effects of some design parameters such as electric field, pulse frequency, and cathode shape are discussed. The products are examined using scanning probe microscopy techniques.

  5. Notice of Intent to Develop DOE G 410.2-1, Nuclear Materials Disposition Guidance

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

    2015-10-01

    DOE O 410.2, Management of Nuclear Materials, identifies the Office of Nuclear Materials Integration (ONMI) asthe organization responsible for nuclear materials management policy, guidance, and integration of DOEagency-wide management, consolidation, and/or disposition of nuclear materials. Specifically,the Order directs ONMI to provide guidance to DOE field elements, as required, for Defined Use and No Defined Use nuclear materials. Further, the Order authorizes this office to review and evaluate justifications for nuclear materials designated as No Defined Use. DOE O 410.2 also requires ONMI to provide guidance to DOE field elements regarding nuclear material discard limits in coordination with relevant DOE headquarters organizations.

  6. Twisted noncommutative field theory with the Wick-Voros and Moyal products

    SciTech Connect (OSTI)

    Galluccio, Salvatore; Lizzi, Fedele; Vitale, Patrizia

    2008-10-15

    We present a comparison of the noncommutative field theories built using two different star products: Moyal and Wick-Voros (or normally ordered). For the latter we discuss both the classical and the quantum field theory in the quartic potential case and calculate the Green's functions up to one loop, for the two- and four-point cases. We compare the two theories in the context of the noncommutative geometry determined by a Drinfeld twist, and the comparison is made at the level of Green's functions and S matrix. We find that while the Green's functions are different for the two theories, the S matrix is the same in both cases and is different from the commutative case.

  7. Curing the UV/IR mixing for field theories with translation-invariant star products

    SciTech Connect (OSTI)

    Tanasa, Adrian; Vitale, Patrizia

    2010-03-15

    The ultraviolet/infrared (UV/IR) mixing of noncommutative field theories has been recently shown to be a generic feature of translation-invariant associative products. In this paper we propose to take into account the quantum corrections of the model to modify in this way the noncommutative action. This idea was already used to cure the UV/IR mixing for theories on Moyal space. We show that in the present framework also, this proposal proves successful for curing the mixing. We achieve this task by explicit calculations of one and higher loops Feynman amplitudes. For the sake of completeness, we compute the form of the new action in the matrix base for the Wick-Voros product.

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

    SciTech Connect (OSTI)

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

    2009-06-01

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

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

    Broader source: Energy.gov [DOE]

    DOE announced its intent to prepare an EIS that would evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE cancelled this EIS.

  10. EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing...

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

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

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

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

    Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review...

  12. EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing...

    Energy Savers [EERE]

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

  13. Low Level Waste Disposition – Quantity and Inventory

    Broader source: Energy.gov [DOE]

    This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the...

  14. Used Fuel Disposition Campaign Disposal Research and Development Roadmap

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and...

  15. Americium/Curium Disposition Life Cycle Planning Study

    SciTech Connect (OSTI)

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

    1998-04-30

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

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

    National Nuclear Security Administration (NNSA)

    Our Jobs Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline U.S. and Russia Sign Plutonium Disposition Agreement U.S. and Russia Sign Plutonium...

  17. SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP

    SciTech Connect (OSTI)

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

    2012-06-08

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

  18. Office of UNF Disposition International Program- Strategic Plan

    Broader source: Energy.gov [DOE]

    The Department of Energy’s Office of Nuclear Energy, Used Nuclear Fuel Disposition Research and Development Office (UFD), performs the critical mission of addressing the need for an integrated...

  19. Update of the Used Fuel Disposition Campaign Implementation Plan

    Broader source: Energy.gov [DOE]

    The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles.

  20. Experimental Program for Used Fuel Disposition in Crystalline Rocks.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Experimental Program for Used Fuel Disposition in Crystalline Rocks. Citation Details In-Document Search Title: Experimental Program for Used Fuel Disposition in Crystalline Rocks. Abstract not provided. Authors: Wang, Yifeng Publication Date: 2014-10-01 OSTI Identifier: 1242086 Report Number(s): SAND2014-19251C 540815 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource Relation: Conference: Proposed for presentation at the DOE Fuel Cycle

  1. Experimental Program for Used Fuel Disposition in Crystalline Rocks.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Experimental Program for Used Fuel Disposition in Crystalline Rocks. Citation Details In-Document Search Title: Experimental Program for Used Fuel Disposition in Crystalline Rocks. Abstract not provided. Authors: Wang, Yifeng Publication Date: 2015-04-01 OSTI Identifier: 1248848 Report Number(s): SAND2015-2980C 583331 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource Relation: Conference: Proposed for presentation at the USA-ROK Joint Fuel

  2. Hanford Tank Waste Retrieval, Treatment and Disposition Framework |

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

    Department of Energy Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with

  3. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation

    Energy Savers [EERE]

    Plan | Department of Energy Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to

  4. Processing and Disposition of Remote-Handled Transuranic Liquid Waste

    Office of Scientific and Technical Information (OSTI)

    Generated at Oak Ridge National Laboratory (Conference) | SciTech Connect SciTech Connect Search Results Conference: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated at Oak Ridge National Laboratory Citation Details In-Document Search Title: Processing and Disposition of Remote-Handled Transuranic Liquid Waste Generated at Oak Ridge National Laboratory Authors: Robinson, Sharon M [1] ; DePaoli, David W [1] ; Jubin, Robert Thomas [1] ; Patton, Bradley D [1] ;

  5. Processing and Disposition of Special Actinide Target Materials

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect SciTech Connect Search Results Conference: Processing and Disposition of Special Actinide Target Materials Citation Details In-Document Search Title: Processing and Disposition of Special Actinide Target Materials Authors: Robinson, Sharon M [1] ; Patton, Bradley D [1] + Show Author Affiliations ORNL Publication Date: 2013-01-01 OSTI Identifier: 1088123 DOE Contract Number: DE-AC05-00OR22725 Resource Type: Conference Resource Relation: Conference: WM2013,

  6. Disposition of DOE Excess Depleted Uranium, Natural Uranium, and

    Energy Savers [EERE]

    Low-Enriched Uranium | Department of Energy Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium The U.S. Department of Energy (DOE) owns and manages an inventory of depleted uranium (DU), natural uranium (NU), and low-enriched uranium (LEU) that is currently stored in large cylinders as depleted uranium hexafluoride (DUF6), natural uranium hexafluoride (NUF6), and

  7. EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing

    Energy Savers [EERE]

    U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany | Department of Energy 7: Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany SUMMARY This EA will evaluate the potential environmental impacts of a DOE proposal to accept spent nuclear fuel from the

  8. Hanford Tank Waste Retrieval, Treatment, and Disposition Framework |

    Office of Environmental Management (EM)

    Department of Energy Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with

  9. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    Savannah River Site - South Carolina Sequoyah Nuclear Plant - Tennessee Browns Ferry Nuclear Plant - Alabama Waste Isolation Pilot Plant - New Mexico Los Alamos National Laboratory - New Mexico DOE/EIS-0283-S2 July 2012 U.S. Department of Energy Office of Fissile Materials Disposition and Office of Environmental Management Washington, DC AVAILABILITY OF THE DRAFT SURPLUS PLUTONIUM DISPOSITION SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT (SPD Supplemental EIS) To submit comments on this SPD

  10. Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    283-S2 April 2015 U.S. Department of Energy Office of Material Management and Minimization and Office of Environmental Management Washington, DC Summary Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement AVAILABILITY OF THE FINAL SURPLUS PLUTONIUM DISPOSITION SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT (SPD Supplemental EIS) For further information on this SPD Supplemental EIS, or to request a copy, please contact: Sachiko McAlhany, NEPA Document Manager SPD

  11. Draft - DOE G 410.2-1, Nuclear Material Disposition

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

    This document provides a roadmap for implementing the requirements for disposition of nuclear material as outlined in the U.S. Department of Energy (DOE) Order 410.2, Management of Nuclear Materials, and DOE Order 474.2, Nuclear Material Control and Accountability. This Guide provides the basic framework for the nuclear material disposition process, includes information related to the Programmatic Value Determination (PVD) process, and identifies Discard Limits (DL) for specific low-equity nuclear materials.

  12. ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

    SciTech Connect (OSTI)

    O'LEARY, GERALD A.

    2007-01-04

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuramic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dispositioning the transuranic waste inventory requires retrieval of the containers from above and below-ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LAN L does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contract in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquaeters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approch include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safetly remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Facility and Dome 231 Permacon will be reconfigured to remediate and repackage oversized containers. Actions are underway to stage the inventory in a manner that facilitiates handling and processing, and builds a backlog at key process steps to improve efficienty and minimize the impact of operational slowdown elsewhere in the process. Several initiatives will improve safety and strengthen disciplined operations and compliance with established requirements. Retrieval is a critical element in dispositioning the below-ground contact-handled and remote-handled transuranic waste inventory and will be subcontracted to a firm(s) with the experience and specialized capability to retrieve the contact-handled and remote-handled inventories. Performance specifications consider likely container integrity issues and anticipated challenges recoveirng the waste from storage in pits, trenches, and lined shafts.

  13. DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS

    SciTech Connect (OSTI)

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

    2003-02-27

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

  14. Supply and Disposition of Crude Oil and Petroleum Products

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

    4,636,835 399,635 7,260,943 3,431,210 125,091 158,333 6,882,105 1,733,771 7,079,504 2,014,788 PADD 1 119,248 10,299 1,386,705 615,305 1,340,322 41,374 35,012 1,368,120 90,331 2,019,791 192,970 PADD 2 937,536 337,875 1,648,603 880,978 -178,536 6,251 45,559 1,573,850 158,221 1,855,077 334,507 PADD 3 2,775,820 37,360 2,865,360 1,309,259 -1,093,041 44,970 70,483 2,650,249 1,331,308 1,887,688 1,297,642 PADD 4 390,381 5,367 241,768 124,089 -261,107 -7,805 3,558 232,453 6,470 250,212 45,547 PADD 5

  15. Supply and Disposition of Crude Oil and Petroleum Products

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

    12,704 1,095 19,893 9,401 343 434 18,855 4,750 19,396 PADD 1 327 28 3,799 1,686 3,672 113 96 3,748 247 5,534 PADD 2 2,569 926 4,517 2,414 -489 17 125 4,312 433 5,082 PADD 3 7,605 102 7,850 3,587 -2,995 123 193 7,261 3,647 5,172 PADD 4 1,070 15 662 340 -715 -21 10 637 18 686 PADD 5 1,134 24 3,064 1,374 527 110 10 2,897 404 2,923

  16. Supply and Disposition of Crude Oil and Petroleum Products

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

    361,277 32,595 560,048 290,577 3,090 4,014 529,373 143,480 570,721 2,044,571 Crude Oil 264,739 - - - - 229,402 -3,032 19,621 460,629 10,860 0 1,214,807 Natural Gas Plant Liquids and Liquefied Refinery Gases 96,538 -620 12,130 6,369 - - -17,151 16,455 36,109 79,004 147,761 Pentanes Plus 11,708 -620 - - 289 - - 922 3,963 6,464 28 20,579 Liquefied Petroleum Gases 84,830 - - 12,130 6,080 - - -18,073 12,492 29,646 78,975 127,182 Ethane/Ethylene 33,304 - - 114 - - - -510 - 2,197 31,731 32,733

  17. Supply and Disposition of Crude Oil and Petroleum Products

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

    2,458 1,124 19,312 10,020 107 138 18,254 4,948 19,680 Crude Oil 9,129 - - - - 7,910 -105 677 15,884 374 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 3,329 -21 418 220 - - -591 567 1,245 2,724 Pentanes Plus 404 -21 - - 10 - - 32 137 223 1 Liquefied Petroleum Gases 2,925 - - 418 210 - - -623 431 1,022 2,723 Ethane/Ethylene 1,148 - - 4 - - - -18 - 76 1,094 Propane/Propylene 1,149 - - 566 190 - - -470 - 884 1,490 Normal Butane/Butylene 326 - - -149 9 - - -161 234 57 57

  18. Supply and Disposition of Crude Oil and Petroleum Products

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

    0,595 836 108,298 55,971 107,313 222 1,592 106,873 8,222 166,548 201,514 Crude Oil 1,376 - - - - 25,376 11,443 158 2,627 31,685 4,041 0 18,847 Natural Gas Plant Liquids and Liquefied Refinery Gases 9,219 -14 258 2,412 -544 - - -1,435 1,271 1,017 10,478 5,074 Pentanes Plus 1,002 -14 - - - -10 - - 21 217 35 705 169 Liquefied Petroleum Gases 8,217 - - 258 2,412 -534 - - -1,456 1,054 982 9,773 4,905 Ethane/Ethylene 3,228 - - 10 - -3,420 - - 164 - - -346 317 Propane/Propylene 3,422 - - 945 2,285

  19. Supply and Disposition of Crude Oil and Petroleum Products

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

    365 29 3,734 1,930 3,700 8 55 3,685 284 5,743 Crude Oil 47 - - - - 875 395 5 91 1,093 139 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 318 0 9 83 -19 - - -49 44 35 361 Pentanes Plus 35 0 - - - 0 - - 1 7 1 24 Liquefied Petroleum Gases 283 - - 9 83 -18 - - -50 36 34 337 Ethane/Ethylene 111 - - 0 - -118 - - 6 - - -12 Propane/Propylene 118 - - 33 79 100 - - -52 - 30 352 Normal Butane/Butylene 37 - - -23 1 0 - - -4 23 4 -8 Isobutane/Isobutylene 17 - - -1 3 0 - - 1 14 0 5 Other Liquids - -

  20. Supply and Disposition of Crude Oil and Petroleum Products

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

    73,037 27,491 129,316 81,450 -25,060 -4,495 -172 122,777 13,415 145,719 338,140 Crude Oil 50,914 - - - - 77,572 -13,800 -5,649 2,262 105,182 1,592 0 153,779 Natural Gas Plant Liquids and Liquefied Refinery Gases 22,123 -566 1,709 2,997 -3,783 - - -5,025 3,017 8,624 15,864 37,883 Pentanes Plus 2,530 -566 - - 2 3,657 - - 460 321 6,205 -1,363 9,836 Liquefied Petroleum Gases 19,593 - - 1,709 2,995 -7,440 - - -5,485 2,696 2,419 17,227 28,047 Ethane/Ethylene 6,172 - - - - -2,169 - - -36 - 2,197 1,842

  1. Supply and Disposition of Crude Oil and Petroleum Products

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

    ,519 948 4,459 2,809 -864 -155 -6 4,234 463 5,025 Crude Oil 1,756 - - - - 2,675 -476 -195 78 3,627 55 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 763 -20 59 103 -130 - - -173 104 297 547 Pentanes Plus 87 -20 - - 0 126 - - 16 11 214 -47 Liquefied Petroleum Gases 676 - - 59 103 -257 - - -189 93 83 594 Ethane/Ethylene 213 - - - - -75 - - -1 - 76 64 Propane/Propylene 306 - - 113 89 -130 - - -101 - 3 475 Normal Butane/Butylene 108 - - -53 8 -59 - - -86 44 5 42 Isobutane/Isobutylene 49 -

  2. Supply and Disposition of Crude Oil and Petroleum Products

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

    14,513 3,300 216,319 105,782 -79,661 7,172 4,678 199,656 110,417 152,673 1,307,049 Crude Oil 161,429 - - - - 85,725 9,831 3,529 14,314 240,985 5,215 0 960,459 Natural Gas Plant Liquids and Liquefied Refinery Gases 53,084 -17 9,383 287 11,383 - - -9,829 9,271 25,194 49,484 99,337 Pentanes Plus 5,602 -17 - - 287 -2,524 - - 466 2,464 72 346 10,222 Liquefied Petroleum Gases 47,482 - - 9,383 - 13,907 - - -10,295 6,807 25,122 49,138 89,115 Ethane/Ethylene 21,487 - - 104 - 7,029 - - -649 - - 29,269

  3. Supply and Disposition of Crude Oil and Petroleum Products

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

    7,397 114 7,459 3,648 -2,747 247 161 6,885 3,807 5,265 Crude Oil 5,567 - - - - 2,956 339 122 494 8,310 180 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,830 -1 324 10 393 - - -339 320 869 1,706 Pentanes Plus 193 -1 - - 10 -87 - - 16 85 2 12 Liquefied Petroleum Gases 1,637 - - 324 - 480 - - -355 235 866 1,694 Ethane/Ethylene 741 - - 4 - 242 - - -22 - - 1,009 Propane/Propylene 580 - - 371 - 127 - - -309 - 819 567 Normal Butane/Butylene 116 - - -48 - 96 - - -46 128 41 41

  4. Supply and Disposition of Crude Oil and Petroleum Products

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

    29,944 385 18,121 9,024 -18,088 -110 524 17,196 286 21,271 46,253 Crude Oil 19,880 - - - - 8,463 -11,220 -305 125 16,681 12 0 24,347 Natural Gas Plant Liquids and Liquefied Refinery Gases 10,064 -10 353 436 -7,056 - - -81 558 205 3,105 3,003 Pentanes Plus 1,598 -10 - - - -1,123 - - -27 131 149 212 311 Liquefied Petroleum Gases 8,466 - - 353 436 -5,933 - - -54 427 57 2,892 2,692 Ethane/Ethylene 2,415 - - - - -1,440 - - 11 - - 964 452 Propane/Propylene 3,870 - - 245 420 -2,796 - - -25 - - 1,764

  5. Supply and Disposition of Crude Oil and Petroleum Products

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

    1,033 13 625 311 -624 -4 18 593 10 733 Crude Oil 686 - - - - 292 -387 -11 4 575 0 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 347 0 12 15 -243 - - -3 19 7 107 Pentanes Plus 55 0 - - - -39 - - -1 5 5 7 Liquefied Petroleum Gases 292 - - 12 15 -205 - - -2 15 2 100 Ethane/Ethylene 83 - - - - -50 - - 0 - - 33 Propane/Propylene 133 - - 8 14 -96 - - -1 - - 61 Normal Butane/Butylene 52 - - 3 - -37 - - -3 7 2 11 Isobutane/Isobutylene 23 - - 1 1 -22 - - 1 7 - -6 Other Liquids - - 14 - - 2 7

  6. Supply and Disposition of Crude Oil and Petroleum Products

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

    33,189 582 87,994 38,350 15,497 301 -2,608 82,871 11,140 84,511 151,614 Crude Oil 31,141 - - - - 32,266 3,747 -765 293 66,096 - 0 57,375 Natural Gas Plant Liquids and Liquefied Refinery Gases 2,048 -13 427 237 - - - -781 2,338 1,069 73 2,464 Pentanes Plus 976 -13 - - - - - - 2 830 2 129 41 Liquefied Petroleum Gases 1,072 - - 427 237 - - - -783 1,508 1,066 -55 2,423 Ethane/Ethylene 2 - - - - - - - - - - 2 - Propane/Propylene 338 - - 1,169 237 - - - -200 - 937 1,007 733 Normal Butane/Butylene 401

  7. Supply and Disposition of Crude Oil and Petroleum Products

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

    1,144 20 3,034 1,322 534 10 -90 2,858 384 2,914 Crude Oil 1,074 - - - - 1,113 129 -26 10 2,279 - 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 71 0 15 8 - - - -27 81 37 3 Pentanes Plus 34 0 - - - - - - 0 29 0 4 Liquefied Petroleum Gases 37 - - 15 8 - - - -27 52 37 -2 Ethane/Ethylene 0 - - - - - - - - - - 0 Propane/Propylene 12 - - 40 8 - - - -7 - 32 35 Normal Butane/Butylene 14 - - -29 - - - - -23 32 4 -29 Isobutane/Isobutylene 11 - - 4 - - - - 3 20 - -7 Other Liquids - - 21 - - 119

  8. Supply and Disposition of Crude Oil and Petroleum Products

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

    386,956 34,242 579,640 301,768 10,444 25,769 545,351 151,212 590,718 2,040,557 PADD 1 11,238 761 111,134 52,931 111,434 2,426 6,952 109,389 9,055 164,527 199,923 PADD 2 77,002 ...

  9. Supply and Disposition of Crude Oil and Petroleum Products

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

    12,458 1,124 19,312 10,020 107 138 18,254 4,948 19,680 PADD 1 365 29 3,734 1,930 3,700 8 55 3,685 284 5,743 PADD 2 2,519 948 4,459 2,809 -864 -155 -6 4,234 463 5,025 PADD 3 7,397 114 7,459 3,648 -2,747 247 161 6,885 3,807 5,265 PADD 4 1,033 13 625 311 -624 -4 18 593 10 733 PADD 5 1,144 20 3,034 1,322 534 10 -90 2,858 384 2,9

  10. Supply and Disposition of Crude Oil and Petroleum Products

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

    4,636,835 399,635 7,260,943 3,431,210 125,091 158,333 6,882,105 1,733,771 7,079,504 2,014,788 Crude Oil 3,442,205 - - - - 2,682,946 49,626 91,814 5,915,532 167,258 173 1,176,487 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,194,630 -7,655 223,448 52,563 - - 21,920 188,270 353,016 899,780 197,273 Pentanes Plus 156,568 -7,655 - - 4,027 - - -45 53,404 66,494 33,087 20,543 Liquefied Petroleum Gases 1,038,062 - - 223,448 48,536 - - 21,965 134,866 286,522 866,693 176,730 Ethane/Ethylene

  11. Supply and Disposition of Crude Oil and Petroleum Products

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

    12,704 1,095 19,893 9,401 343 434 18,855 4,750 19,396 Crude Oil 9,431 - - - - 7,351 136 252 16,207 458 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 3,273 -21 612 144 - - 60 516 967 2,465 Pentanes Plus 429 -21 - - 11 - - 0 146 182 91 Liquefied Petroleum Gases 2,844 - - 612 133 - - 60 369 785 2,375 Ethane/Ethylene 1,108 - - 6 0 - - -3 - 65 1,051 Propane/Propylene 1,117 - - 559 112 - - 51 - 615 1,121 Normal Butane/Butylene 324 - - 55 10 - - 12 169 98 110 Isobutane/Isobutylene 296 - - -7

  12. Supply and Disposition of Crude Oil and Petroleum Products

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

    19,248 10,299 1,386,705 615,305 1,340,322 41,374 35,012 1,368,120 90,331 2,019,791 192,970 Crude Oil 18,216 - - - - 227,582 153,688 40,084 1,159 409,330 28,908 173 16,298 Natural Gas Plant Liquids and Liquefied Refinery Gases 101,032 -191 14,223 16,761 -4,395 - - 937 12,599 16,573 97,321 8,270 Pentanes Plus 11,667 -191 - - 9 4 - - 99 583 706 10,101 209 Liquefied Petroleum Gases 89,365 - - 14,223 16,752 -4,399 - - 838 12,016 15,867 87,220 8,061 Ethane/Ethylene 30,795 - - 170 - -31,804 - - 30 - -

  13. Supply and Disposition of Crude Oil and Petroleum Products

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

    327 28 3,799 1,686 3,672 113 96 3,748 247 5,534 Crude Oil 50 - - - - 624 421 110 3 1,121 79 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 277 -1 39 46 -12 - - 3 35 45 267 Pentanes Plus 32 -1 - - 0 0 - - 0 2 2 28 Liquefied Petroleum Gases 245 - - 39 46 -12 - - 2 33 43 239 Ethane/Ethylene 84 - - 0 - -87 - - 0 - - -2 Propane/Propylene 110 - - 37 41 76 - - 3 - 38 223 Normal Butane/Butylene 36 - - 2 1 0 - - -1 23 6 11 Isobutane/Isobutylene 14 - - -1 4 0 - - 0 10 0 7 Other Liquids - - 29 -

  14. Supply and Disposition of Crude Oil and Petroleum Products

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

    937,536 337,875 1,648,603 880,978 -178,536 6,251 45,559 1,573,850 158,221 1,855,077 334,507 Crude Oil 683,387 - - - - 841,415 -149,878 -6,282 39,872 1,299,921 28,849 0 150,472 Natural Gas Plant Liquids and Liquefied Refinery Gases 254,149 -6,980 40,909 25,611 -16,520 - - 2,143 33,456 92,412 169,158 54,687 Pentanes Plus 32,237 -6,980 - - 45 46,186 - - 857 6,692 62,712 1,227 9,997 Liquefied Petroleum Gases 221,912 - - 40,909 25,566 -62,706 - - 1,286 26,764 29,700 167,931 44,690 Ethane/Ethylene

  15. Supply and Disposition of Crude Oil and Petroleum Products

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

    569 926 4,517 2,414 -489 17 125 4,312 433 5,082 Crude Oil 1,872 - - - - 2,305 -411 -17 109 3,561 79 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 696 -19 112 70 -45 - - 6 92 253 463 Pentanes Plus 88 -19 - - 0 127 - - 2 18 172 3 Liquefied Petroleum Gases 608 - - 112 70 -172 - - 4 73 81 460 Ethane/Ethylene 191 - - 0 0 -27 - - 2 - 65 98 Propane/Propylene 274 - - 112 57 -122 - - -2 - 4 318 Normal Butane/Butylene 94 - - 2 7 -26 - - 4 27 12 33 Isobutane/Isobutylene 48 - - -1 6 4 - - 0 46 0

  16. Supply and Disposition of Crude Oil and Petroleum Products

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

    775,820 37,360 2,865,360 1,309,259 -1,093,041 44,970 70,483 2,650,249 1,331,308 1,887,688 1,297,642 Crude Oil 2,078,550 - - - - 1,085,333 95,440 -263 41,650 3,113,888 103,522 0 931,007 Natural Gas Plant Liquids and Liquefied Refinery Gases 697,270 -207 145,337 4,588 129,222 - - 18,599 109,314 228,253 620,044 125,761 Pentanes Plus 81,397 -207 - - 3,955 -29,697 - - -991 34,994 439 21,006 9,983 Liquefied Petroleum Gases 615,873 - - 145,337 633 158,919 - - 19,590 74,320 227,814 599,038 115,778

  17. Supply and Disposition of Crude Oil and Petroleum Products

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

    7,605 102 7,850 3,587 -2,995 123 193 7,261 3,647 5,172 Crude Oil 5,695 - - - - 2,974 261 -1 114 8,531 284 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,910 -1 398 13 354 - - 51 299 625 1,699 Pentanes Plus 223 -1 - - 11 -81 - - -3 96 1 58 Liquefied Petroleum Gases 1,687 - - 398 2 435 - - 54 204 624 1,641 Ethane/Ethylene 755 - - 5 - 190 - - -4 - - 955 Propane/Propylene 599 - - 360 0 156 - - 52 - 551 512 Normal Butane/Butylene 131 - - 40 2 67 - - 6 86 66 81 Isobutane/Isobutylene 202 -

  18. Supply and Disposition of Crude Oil and Petroleum Products

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

    390,381 5,367 241,768 124,089 -261,107 -7,805 3,558 232,453 6,470 250,212 45,547 Crude Oil 272,388 - - - - 119,074 -155,263 -10,098 3,234 219,796 3,070 0 23,545 Natural Gas Plant Liquids and Liquefied Refinery Gases 117,993 -123 4,589 3,561 -108,299 - - 387 7,148 2,691 7,495 3,622 Pentanes Plus 20,168 -123 - - - -16,493 - - 20 2,045 1,914 -427 310 Liquefied Petroleum Gases 97,825 - - 4,589 3,561 -91,806 - - 367 5,103 777 7,922 3,312 Ethane/Ethylene 27,979 - - - - -27,855 - - -86 - - 210 432

  19. Supply and Disposition of Crude Oil and Petroleum Products

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

    1,070 15 662 340 -715 -21 10 637 18 686 Crude Oil 746 - - - - 326 -425 -28 9 602 8 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 323 0 13 10 -297 - - 1 20 7 21 Pentanes Plus 55 0 - - - -45 - - 0 6 5 -1 Liquefied Petroleum Gases 268 - - 13 10 -252 - - 1 14 2 22 Ethane/Ethylene 77 - - - - -76 - - 0 - - 1 Propane/Propylene 122 - - 9 9 -110 - - 0 - 0 29 Normal Butane/Butylene 50 - - 3 0 -40 - - 1 7 2 5 Isobutane/Isobutylene 19 - - 0 1 -25 - - 0 7 0 -13 Other Liquids - - 15 - - 1 16 -12 1

  20. Supply and Disposition of Crude Oil and Petroleum Products

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

    413,849 8,734 1,118,507 501,579 192,362 40,300 3,721 1,057,433 147,442 1,066,735 144,121 Crude Oil 389,663 - - - - 409,542 56,014 26,186 5,899 872,597 2,909 0 55,165 Natural Gas Plant Liquids and Liquefied Refinery Gases 24,186 -154 18,390 2,042 -8 - - -146 25,753 13,086 5,763 4,933 Pentanes Plus 11,099 -154 - - 18 - - - -30 9,090 723 1,180 44 Liquefied Petroleum Gases 13,087 - - 18,390 2,024 -8 - - -116 16,663 12,363 4,583 4,889 Ethane/Ethylene 35 - - - - - - - - - - 35 - Propane/Propylene

  1. Supply and Disposition of Crude Oil and Petroleum Products

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

    1,134 24 3,064 1,374 527 110 10 2,897 404 2,923 Crude Oil 1,068 - - - - 1,122 153 72 16 2,391 8 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 66 0 50 6 0 - - 0 71 36 16 Pentanes Plus 30 0 - - 0 - - - 0 25 2 3 Liquefied Petroleum Gases 36 - - 50 6 0 - - 0 46 34 13 Ethane/Ethylene 0 - - - - - - - - - - 0 Propane/Propylene 12 - - 41 5 - - - -2 - 22 39 Normal Butane/Butylene 12 - - 7 0 - - - 2 25 12 -20 Isobutane/Isobutylene 11 - - 3 0 0 - - 0 21 0 -6 Other Liquids - - 24 - - 114 314 15 3

  2. Supply and Disposition of Crude Oil and Petroleum Products

    Gasoline and Diesel Fuel Update (EIA)

    Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1990's 1,451 208 NA 2000's NA 1,529 1,477 33 15 1,304 2,529 6,560 10,603 12,530 2010's 7,769 9,768 6,016 10,409 3,547 5,333

    Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1990's 356,711 360,261 374,666 415,636 2000's 347,992 366,050 394,929 366,257 339,051 336,684 255,743 254,086 300,453 309,516 2010's 332,358 313,922 312,236 333,050 359,343 429,64

    August 13, 2014 MEMORANDUM FOR:

  3. TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION

    SciTech Connect (OSTI)

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

    2013-07-16

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

  4. Drilling and Production Testing the Methane Hydrate Resource Potential Associated with the Barrow Gas Fields

    SciTech Connect (OSTI)

    Steve McRae; Thomas Walsh; Michael Dunn; Michael Cook

    2010-02-22

    In November of 2008, the Department of Energy (DOE) and the North Slope Borough (NSB) committed funding to develop a drilling plan to test the presence of hydrates in the producing formation of at least one of the Barrow Gas Fields, and to develop a production surveillance plan to monitor the behavior of hydrates as dissociation occurs. This drilling and surveillance plan was supported by earlier studies in Phase 1 of the project, including hydrate stability zone modeling, material balance modeling, and full-field history-matched reservoir simulation, all of which support the presence of methane hydrate in association with the Barrow Gas Fields. This Phase 2 of the project, conducted over the past twelve months focused on selecting an optimal location for a hydrate test well; design of a logistics, drilling, completion and testing plan; and estimating costs for the activities. As originally proposed, the project was anticipated to benefit from industry activity in northwest Alaska, with opportunities to share equipment, personnel, services and mobilization and demobilization costs with one of the then-active exploration operators. The activity level dropped off, and this benefit evaporated, although plans for drilling of development wells in the BGF's matured, offering significant synergies and cost savings over a remote stand-alone drilling project. An optimal well location was chosen at the East Barrow No.18 well pad, and a vertical pilot/monitoring well and horizontal production test/surveillance well were engineered for drilling from this location. Both wells were designed with Distributed Temperature Survey (DTS) apparatus for monitoring of the hydrate-free gas interface. Once project scope was developed, a procurement process was implemented to engage the necessary service and equipment providers, and finalize project cost estimates. Based on cost proposals from vendors, total project estimated cost is $17.88 million dollars, inclusive of design work, permitting, barging, ice road/pad construction, drilling, completion, tie-in, long-term production testing and surveillance, data analysis and technology transfer. The PRA project team and North Slope have recommended moving forward to the execution phase of this project.

  5. Continuous on-line steam quality monitoring system of the Bacman Geothermal Production Field, Philippines

    SciTech Connect (OSTI)

    Solis, R.P.; Chavez, F.C.; Garcia, S.E.

    1997-12-31

    In any operating geothermal power plant, steam quality is one of the most important parameters being monitored. In the Bacon-Manito Geothermal Production Field (BGPF), an online steam quality monitoring system have been installed in two operating power plants which provides an accurate, efficient and continuous real-time data which is more responsive to the various requirements of the field operation. The system utilizes sodium as an indicator of steam purity. Sodium concentration is read by the flame photometer located at the interface after aspirating a sample of the condensed steam through a continuous condensate sampler. The condensate has been degassed through a condensate-NCG separator. The flame photometer analog signal is then converted by a voltage-to-current converter/transmitter and relayed to the processor which is located at the control center through electrical cable to give a digital sodium concentration read-out at the control panel. The system features a high and high-high sodium level alarm, a continuous strip-chart recorder and a central computer for data capture, retrieval, and processing for further interpretation. Safety devices, such as the flame-off indicator at the control center and the automatic fuel cut-off device along the fuel line, are incorporated in the system.

  6. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23

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

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

    SciTech Connect (OSTI)

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

    2001-03-26

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

  8. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Jones, R.; Carter, J.

    2010-10-13

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

  9. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Carter, J.

    2011-01-03

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

  10. Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |

    Energy Savers [EERE]

    Department of Energy Site Achieves Transuranic Waste Disposition Goal in 2013 Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 December 24, 2013 - 12:00pm Addthis Workers gather behind a “Safety and Security begins with Me” banner at the Savannah River Site. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. Workers sort through

  11. Used Fuel Disposition Research & Development | Department of Energy

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

    Used Fuel Disposition Research & Development Used Fuel Disposition Research & Development A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful

  12. Optimizing the Use of Federal Lands Through Disposition | Department of

    Energy Savers [EERE]

    Energy Optimizing the Use of Federal Lands Through Disposition Optimizing the Use of Federal Lands Through Disposition July 14, 2014 - 1:20pm Addthis What does this project do? Goal 4. Optimize the use of land and assets. The foundation of the U.S. Department of Energy (DOE) Office of Legacy Management's (LM) Goal 4, "Optimize the use of land and assets," is to establish environmentally sound and protective land uses on LM sites. LM believes there can be beneficial uses of land

  13. Recommendation 219: Recommendation Regarding the Creation of a Graphic Representation of Waste Disposition Paths

    Broader source: Energy.gov [DOE]

    The Environmental Management Site-Specific Advisory Board recommends that DOE develop graphic representations of waste disposition paths.

  14. Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies, Class III

    SciTech Connect (OSTI)

    City of Long Beach; Tidelands Oil Production Company; University of Southern California; David K. Davies and Associates

    2002-09-30

    The objective of this project was to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. The successful application of these technologies would result in expanding their implementation throughout the Wilmington Field and, through technology transfer, to other slope and basin clastic (SBC) reservoirs.

  15. Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies, Class III

    SciTech Connect (OSTI)

    City of Long Beach; Tidelands Oil Production Company; University of Southern California; David K. Davies and Associates

    2002-09-30

    The objective of this project was to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. It was hoped that the successful application of these technologies would result in their implementation throughout the Wilmington Field and, through technology transfer, will be extended to increase the recoverable oil reserves in other slope and basin clastic (SBC) reservoirs.

  16. An evaluation of gas field rules in light of current conditions and production practices in the Panhandle non-associated gas fields

    SciTech Connect (OSTI)

    Brady, C.L.; O`Rear, C.H.

    1996-09-01

    During the early years of development in the Panhandle fields the Rule of Capture was king. Under the Rule of Capture each property owner has the right to drill as many wells as desired at any location. Adjacent property owners protect their rights by doing the same. Courts adopted the Rule of Capture to protect mineral owners from liability due to migration of oil and gas across property boundary lines. This general practice {open_quotes}to go and do likewise{close_quotes} generally leads to enormous economic and natural resource waste. Established to offset the waste created under the Rule of Capture is the doctrine of Correlative Rights. Correlative Rights is the fight of each mineral owner to obtain oil and gas from a common source of supply under lawful operations conducted from his property. However, each mineral owner has a duty to every other mineral owner not to extract oil and gas in a manner injurious to the common source of supply. This paper will examine the historical context of these common law principles with regard to the Panhandle non-associated gas fields. Discovered in 1917, the Panhandle fields are ideal to evaluate the merit of statutes and regulations enacted in response to production practices. As in many Texas fields, proration in the Panhandle fields is the primary mechanism to protect correlative rights and prevent waste. Signed and made effective May 1989, the current field rules pre-date much of the enhanced recovery techniques that use well-head vacuum compression. This paper reviews the gas rules in the 1989 Texas Railroad Commission order in light of current reservoir conditions and production practices.

  17. DOE Seeks Industry Input on Nickel Disposition Strategy

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – The Energy Department’s prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel.

  18. EM Waste and Materials Disposition & Transportation

    Office of Environmental Management (EM)

    of Energy Waste Isolation Pilot Plant Team's Holiday Spirit Shines EM Waste Isolation Pilot Plant Team's Holiday Spirit Shines December 23, 2013 - 12:00pm Addthis Aspen Cass, a relative of an EM Carlsbad Field Office (CBFO) employee, holds donated coats with Farok Sharif (left), president and project manager of Nuclear Waste Partnership, the WIPP management and operating contractor, and Joe Franco, manager of CBFO. Aspen Cass, a relative of an EM Carlsbad Field Office (CBFO) employee, holds

  19. Analytic Properties of Expectation Values of Products of Field Operators. Lectures

    DOE R&D Accomplishments [OSTI]

    Salam, A , Okubo, S

    1958-12-15

    A review is presented of the latest work on the axiomatic approach of field theory. An account is given of recent work in dispersion theory. (A.C.)

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

    SciTech Connect (OSTI)

    1998-03-01

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

  1. Production of field-reversed mirror plasma with a coaxial plasma gun

    DOE Patents [OSTI]

    Hartman, Charles W.; Shearer, James W.

    1982-01-01

    The use of a coaxial plasma gun to produce a plasma ring which is directed into a magnetic field so as to form a field-reversed plasma confined in a magnetic mirror. Plasma thus produced may be used as a target for subsequent neutral beam injection or other similarly produced and projected plasma rings or for direct fusion energy release in a pulsed mode.

  2. Production of field-reversed mirror plasma with a coaxial plasma gun

    DOE Patents [OSTI]

    Hartman, C.W.; Shearer, J.W.

    The use of a coaxial plasma gun to produce a plasma ring which is directed into a magnetic field so as to form a field-reversed plasma confined in a magnetic mirror. Plasma thus produced may be used as a target for subsequent neutral beam injection or other similarly produced and projected plasma rings or for direct fusion energy release in a pulsed mode.

  3. Plutonium disposition via immobilization in ceramic or glass

    SciTech Connect (OSTI)

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

    1997-03-05

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

  4. Update of the Used Fuel Disposition Campaign Implementation Plan

    SciTech Connect (OSTI)

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

    2014-09-01

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

  5. Experimental Program for Used Fuel Disposition in Crystalline Rocks

    Office of Scientific and Technical Information (OSTI)

    SAND2015-2980C Nuclear Energy Experimental Program for Used Fuel Disposition in Crystalline Rocks Yifeng Wang Sandia National Laboratories Nuclear Energy Crystalline Disposal R&D Work Packages ■ Objectives * Advance our understanding of long-term disposal of used fuel in crystalline rocks; * Develop experimental and computational capabilities to evaluate various disposal concepts in such media. ■ Focus on two key components of deep geologic repository in crystalline rocks * Better

  6. Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx

    Office of Environmental Management (EM)

    Organizational Chart Office of Project Management Oversight and Assessments (PM) PM-1 Paul Bosco Director Under Secretary for Management and Performance (S3) Tony Ermovick PM-20 Departmental Project Oversight Melvin Frank PM-30 Project Management Policy & Systems Linda Ott PM-40 Professional Development PM-2 Michael Peek Deputy Director New Organization Effective: July 12, 2015 John White PM-10 Project Assessments Jay Glascock Chief of Staff

    Materials and Disposition Update Environmental

  7. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    SHEET Lead Agency: U.S. Department of Energy (DOE) / National Nuclear Security Administration (NNSA) Cooperating Agency: Tennessee Valley Authority Title: Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD Supplemental EIS) (DOE/EIS-0283-S2) Locations: South Carolina, New Mexico, Alabama, and Tennessee For further information or for copies of this Draft SPD Supplemental EIS, contact: Sachiko McAlhany, NEPA Document Manager SPD Supplemental EIS U.S. Department

  8. Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement

    National Nuclear Security Administration (NNSA)

    SHEET Lead Agency: U.S. Department of Energy (DOE) / National Nuclear Security Administration (NNSA) Cooperating Agency: Tennessee Valley Authority Title: Draft Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD Supplemental EIS) (DOE/EIS-0283-S2) Locations: South Carolina, New Mexico, Alabama, and Tennessee For further information or for copies of this Draft SPD Supplemental EIS, contact: Sachiko McAlhany, NEPA Document Manager SPD Supplemental EIS U.S. Department of

  9. Research To Underpin The UK Plutonium Disposition Strategy

    SciTech Connect (OSTI)

    Hanson, B.C.; Scales, C.R.; Worrall, A.; Thomas, M.; Davies, P.; Gilchrist, P.

    2006-07-01

    In April 2005, the UK Nuclear Decommissioning Authority (NDA) took ownership of most of the civil nuclear liabilities and assets in the UK. These include separated civil plutonium stocks, which are expected to rise to over 100 tonnes. Future UK national policy for disposition remains to be finalised. The feasibility of management options needs to be determined in order to allow the NDA to advise government on the ultimate disposition of this material. Nexia Solutions has a contract with NDA to develop and carry out a research project which will result in a recommendation on the technical feasibility of a number of disposition options, focussing on re-use and immobilisation of plutonium as a waste for disposal. Initial work is already underway evaluating re-use with MOX and IMF fuels and immobilisation using ceramics, glasses and MOX for disposal. The programme is expected to result, circa 2010, in a recommendation of a preferred route for immobilisation and a preferred route for re-use for the UK's civil Pu stocks. (authors)

  10. Summary - Uranium233 Downblending and Disposition Project

    Office of Environmental Management (EM)

    Product EM wa in Buil to extr from 23 downb mitigat concer dispos downb WIPP condu the "ba allowin assess techno The as Techn Techn * An * C (T * Pr * O The Ele Site: O roject: 2 P Report Date: S ited States 233 Ura Why DOE t Packaging Syste as directed to t ding 3019 at O ract 229 Th (an is 33 U. The missi blend the inven te security and rns and prepar sal. The projec blended materia or the Nevada cted to coincid ack-end" of the ng observation sment team to ology maturity p What th

  11. Field-project designs for carbon dioxide sequestration and enhanced coalbed methane production

    SciTech Connect (OSTI)

    W. Neal Sams; Grant Bromhal; Sinisha Jikich; Turgay Ertekin; Duane H. Smith

    2005-12-01

    Worldwide concerns about global warming and possible contributions to it from anthropogenic carbon dioxide have become important during the past several years. Coal seams may make excellent candidates for CO{sub 2} sequestration; coal-seam sequestration could enhance methane production and improve sequestration economics. Reservoir-simulation computations are an important component of any engineering design before carbon dioxide is injected underground. We have performed such simulations for a hypothetical pilot-scale project in representative coal seams. In these simulations we assume four horizontal production wells that form a square, that is, two wells drilled at right angles to each other forming two sides of a square, with another pair of horizontal wells similarly drilled to form the other two sides. Four shorter horizontal wells are drilled from a vertical well at the center of the square, forming two straight lines orthogonal to each other. By modifying coal properties, especially sorption rate, we have approximated different types of coals. By varying operational parameters, such as injector length, injection well pressure, time to injection, and production well pressure, we can evaluate different production schemes to determine an optimum for each coal type. Any optimization requires considering a tradeoff between total CO{sub 2} sequestered and the rate of methane production. Values of total CO{sub 2} sequestered and methane produced are presented for multiple coal types and different operational designs. 30 refs., 11 figs., 1 tab.

  12. Used Fuel Disposition R&D Documents | Department of Energy

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

    Initiatives » Fuel Cycle Technologies » Used Fuel Disposition Research & Development » Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents September 22, 2015 Application of Generic Disposal System Models Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling; these are directly addressed in the Generic Disposal Systems Analysis (GDSA) work. This report describes specific GDSA activities during fiscal

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

    Energy Savers [EERE]

    Project | Department of Energy Site-Wide Waste Disposition Evaluation Project Portsmouth RI/FS Report for the Site-Wide Waste Disposition Evaluation Project This Remedial Investigation and Feasibility Study Report for the Site-Wide Waste Disposition Evaluation Project at the Portsmouth Gaseous Diffusion Plant, Piketon, Ohio, presents the information necessary to select a Site-wide disposal alternative for the waste generated under the Director's Final Findings and Orders (DFF&O) for

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

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

    for the Site-Wide Waste Disposition Evaluation Project at the Portsmouth Gaseous Diffusion Plant, Piketon, Ohio, presents the information necessary to select a Site-wide...

  15. Public Comment Period for Portsmouth Site D&D and Waste Disposition Decisions

    Broader source: Energy.gov [DOE]

    Public Comment Period for the Process Buildings and Complex Facilities Decontamination and Decommissioning and Site-Wide Waste Disposition Decisions at the Portsmouth Gaseous Diffusion Plant

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

    Office of Environmental Management (EM)

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

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

    Broader source: Energy.gov [DOE]

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

  18. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2002-01-31

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through September 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Fourth Quarter 2001 performing routine well work and reservoir surveillance on the Tar II-A post-steamflood and Tar V pilot steamflood projects. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. The project team ramped up well work activity from October 2000 through November 2001 to increase production and injection. In December, water injection well FW-88 was plug and abandoned and replaced by new well FW-295 into the ''D'' sands to accommodate the Port of Long Beach at their expense. Well workovers are planned for 2002 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The steamflood operation in the Tar V pilot project is mature and profitable. Recent production performance is below projections because of wellbore mechanical limitations that were being addressed in 2001. As the fluid production is hot, the pilot steamflood was converted to a hot waterflood project in June 2001.

  19. Digital field-bus mode SCADA is key to offshore efficiency. [Automation of offshore gas production platforms

    SciTech Connect (OSTI)

    Cuthbert, P. )

    1994-02-01

    An all-digital SCADA network has been installed in one of the North Sea's largest natural gas fields, controlling the delivery of gas from Shell UK Exploration and Production's souther-area fields to a British Gas Terminal at Bacton, UK. The innovative use of digital technology -- based on the industry-standard HART field protocol -- to complete a digital communications link stretching from the onshore SCADA host right out to the process variable transmitters on the platforms, is playing a key role in the automation of the monitoring and control system by allowing Shell UK Expro to run the majority of the platforms unmanned. The SCADA system is part of a major refit being carried out by Shell Expro on its Leman field. The refit is part of the company's long-term strategy to extend the lifetime of this established field, which started operations in the late 1960s. In order to meet this goal, the prime requirements are to reduce operational costs and risk exposure, and the key element in this area was to reduce the need for resident staff and all of their associated support and equipment costs, through the deployment of automation. The system will achieve the project's cost-cutting aims, but also break new ground in control and monitoring technology for the gas industry, through the use of a smart transmitter scheme as a digital field communications within the wide-area network, using the protocol's all-digital capability in preference to the commonly used 4-20mA-compatible mode, will allow real-time monitoring and control, plus maintenance and diagnostics, to take place remotely. This paper describes the design of this system.

  20. Used fuel disposition campaign international activities implementation plan.

    SciTech Connect (OSTI)

    Nutt, W. M. (Nuclear Engineering Division)

    2011-06-29

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

  1. Topic Index to the DOE Administrative Records Disposition Schedules

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

    5/21/07 TOPICINDEXTODOEADMINSCHEDULES Topic Index to the DOE Administrative Records Disposition Schedules (excluding the GRS Schedules) Topic Schedule Item [A] [B] [C] [D] [E] [F] [G] [H] [I] [J] [K] [L] [M] [N] [O] [P] [Q] [R] [S] [T] [U] [V] [W] [X] [Y] [Z] A Academic/Outreach Program 1 44 Access Request Files 18 6 Accountable Officers' Files 6 1 Accounting Administrative Files 6 5 Administrative Claims Files 6 10 Administrative Training Records 1 29.2 Administrative Issuances 16 1

  2. Plutonium_Disposition_Phase_2_TOR_082015_FINAL

    National Nuclear Security Administration (NNSA)

    AEROSPACE REPORT NO. TOR-2015-02671 Plutonium Disposition Study Options Independent Assessment Phase 2 Report August 20, 2015 Matthew J. Hart 1 , Nichols F. Brown 2 , Mark J. Rokey 1 , Harold J. Huslage 3 , J. Denise Castro-Bran 4 , Norman Y. Lao 5 , Roland J. Duphily 5 , Vincent M. Canales 2 , Joshua P. Davis 6 , Whitney L. Plumb-Starnes 7 , Jya-Syin W. Chien 5 1 Civil Applications Directorate, Civil and Commercial Programs Division 2 Schedule and Cost Analysis Department, Acquisition Analysis

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

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

    1999-09-29

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

  4. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2001-06-27

    The objective of this project is to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. The successful application of these technologies will result in expanding their implementation throughout the Wilmington Field and, through technology transfer, to other slope and basin clastic (SBC) reservoirs. The existing steamflood in the Tar zone of Fault Block II-A (Tar II-A) has been relatively inefficient because of several producibility problems which are common in SBC reservoirs: inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil and non-uniform distribution of the remaining oil. This has resulted in poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. A suite of advanced reservoir characterization and thermal production technologies are being applied during the project to improve oil recovery and reduce operating costs.

  5. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2001-11-01

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through June 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Third Quarter 2001 performing well work and reservoir surveillance on the Tar II-A post-steamflood project. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. The project team ramped up well work activity from October 2000 to September 2001 to increase production and injection. This work will continue through 2001 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being addressed in 2001.

  6. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2001-05-07

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through September 2000, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on improving core analysis techniques, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post steamflood projects. Work was discontinued on the stochastic geologic model and developing a 3-D stochastic thermal reservoir simulation model of the Tar II-A Zone so the project team could use the 3-D deterministic reservoir simulation model to provide alternatives for the Tar II-A post steamflood operations and shale compaction studies. The project team spent the fourth quarter 2000 performing well work and reservoir surveillance on the Tar II-A post-steamflood project and the Tar V horizontal well steamflood pilot. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being evaluated.

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

    SciTech Connect (OSTI)

    WEST LD

    2011-01-13

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

  8. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Unknown

    2001-08-08

    The objective of this project is to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California, through the testing and application of advanced reservoir characterization and thermal production technologies. The hope is that successful application of these technologies will result in their implementation throughout the Wilmington Field and, through technology transfer, will be extended to increase the recoverable oil reserves in other slope and basin clastic (SBC) reservoirs. The existing steamflood in the Tar zone of Fault Block II-A (Tar II-A) has been relatively inefficient because of several producibility problems which are common in SBC reservoirs: inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil and non-uniform distribution of the remaining oil. This has resulted in poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. A suite of advanced reservoir characterization and thermal production technologies are being applied during the project to improve oil recovery and reduce operating costs, including: (1) Development of three-dimensional (3-D) deterministic and stochastic reservoir simulation models--thermal or otherwise--to aid in reservoir management of the steamflood and post-steamflood phases and subsequent development work. (2) Development of computerized 3-D visualizations of the geologic and reservoir simulation models to aid reservoir surveillance and operations. (3) Perform detailed studies of the geochemical interactions between the steam and the formation rock and fluids. (4) Testing and proposed application of a novel alkaline-steam well completion technique for the containment of the unconsolidated formation sands and control of fluid entry and injection profiles. (5) Installation of a 2100 ft, 14 inch insulated, steam line beneath a harbor channel to supply steam to an island location. (6) Testing and proposed application of thermal recovery technologies to increase oil production and reserves: (a) Performing pilot tests of cyclic steam injection and production on new horizontal wells. (b) Performing pilot tests of hot water-alternating-steam (WAS) drive in the existing steam drive area to improve thermal efficiency. (7) Perform a pilot steamflood with the four horizontal injectors and producers using a pseudo steam-assisted gravity-drainage (SAGD) process. (8) Advanced reservoir management, through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring and evaluation.

  9. Production

    Broader source: Energy.gov [DOE]

    Algae production R&D focuses on exploring resource use and availability, algal biomass development and improvements, characterizing algal biomass components, and the ecology and engineering of...

  10. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2001-05-08

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through March 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Second Quarter 2001 performing well work and reservoir surveillance on the Tar II-A post-steamflood project. The Tar II-A steamflood reservoirs have been operated over fifteen months at relatively stable pressures, due in large part to the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase in January 1999. Starting in the Fourth Quarter 2000, the project team has ramped up activity to increase production and injection. This work will continue through 2001 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being addressed in 2001. Much of the second quarter was spent writing DOE annual and quarterly reports to stay current with contract requirements.

  11. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2000-02-18

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through March 1999, project work has been completed related to data preparation, basic reservoir engineering, developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model, and a rock-log model, well drilling and completions, and surface facilities. Work is continuing on the stochastic geologic model, developing a 3-D stochastic thermal reservoir simulation model of the Fault Block IIA Tar (Tar II-A) Zone, and operational work and research studies to prevent thermal-related formation compaction. Thermal-related formation compaction is a concern of the project team due to observed surface subsidence in the local area above the steamflood project. Last quarter on January 12, the steamflood project lost its inexpensive steam source from the Harbor Cogeneration Plant as a result of the recent deregulation of electrical power rates in California. An operational plan was developed and implemented to mitigate the effects of the two situations. Seven water injection wells were placed in service in November and December 1998 on the flanks of the Phase 1 steamflood area to pressure up the reservoir to fill up the existing steam chest. Intensive reservoir engineering and geomechanics studies are continuing to determine the best ways to shut down the steamflood operations in Fault Block II while minimizing any future surface subsidence. The new 3-D deterministic thermal reservoir simulator model is being used to provide sensitivity cases to optimize production, steam injection, future flank cold water injection and reservoir temperature and pressure. According to the model, reservoir fill up of the steam chest at the current injection rate of 28,000 BPD and gross and net oil production rates of 7,700 BPD and 750 BOPD (injection to production ratio of 4) will occur in October 1999. At that time, the reservoir should act more like a waterflood and production and cold water injection can be operated at lower net injection rates to be determined. Modeling runs developed this quarter found that varying individual well injection rates to meet added production and local pressure problems by sub-zone could reduce steam chest fill-up by up to one month.

  12. Production

    Broader source: Energy.gov [DOE]

    Algae production R&D focuses on exploring resource use and availability, algal biomass development and improvements, characterizing algal biomass components, and the ecology and engineering of cultivation systems.

  13. Increasing Heavy Oil Reserves in the Wilmington Oil Field through Advanced Reservoir Characterization and Thermal Production Technologies

    SciTech Connect (OSTI)

    City of Long Beach; David K.Davies and Associates; Tidelands Oil Production Company; University of Southern California

    1999-06-25

    The objective of this project is to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California. This is realized through the testing and application of advanced reservoir characterization and thermal production technologies. It is hoped that the successful application of these technologies will result in their implementation throughout the Wilmington Field and through technology transfer, will be extended to increase the recoverable oil reserves in other slope and basin clastic (SBC) reservoirs. The existing steamflood in the Tar zone of Fault Block (FB) II-A has been relatively insufficient because of several producability problems which are common in SBC reservoir; inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil and non-uniform distribution of the remaining oil. This has resulted in poor sweep efficiency, high steam-oil ratios, and early breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves.

  14. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2002-04-30

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through December 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. During the First Quarter 2002, the project team developed an accelerated oil recovery and reservoir cooling plan for the Tar II-A post-steamflood project and began implementing the associated well work in March. The Tar V pilot steamflood project will be converted to post-steamflood cold water injection in April 2002. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. Most of the 2001 well work resulted in maintaining oil and gross fluid production and water injection rates. Reservoir pressures in the ''T'' and ''D'' sands are at 88% and 91% hydrostatic levels, respectively. Well work during the first quarter and plans for 2002 are described in the Reservoir Management section. The steamflood operation in the Tar V pilot project is mature and profitable. Recent production performance has been below projections because of wellbore mechanical limitations that have been addressed during this quarter. As the fluid production temperatures were beginning to exceed 350 F, our self-imposed temperature limit, the pilot steamflood was converted to a hot waterflood project in June 2001 and will be converted to cold water injection next quarter.

  15. Analysis of disposition alternatives for radioactively contaminated scrap metal

    SciTech Connect (OSTI)

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

    1997-01-01

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

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

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

    1998-05-01

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

  17. Microsoft Word - Pu Disposition Red Team Report.docx

    National Nuclear Security Administration (NNSA)

    Final Report of the Plutonium Disposition Red Team Date: 13 August 2015 Oak Ridge, Tennessee Thom Mason, Chair This r eport w as p repared a s a n a ccount o f w ork s ponsored b y a n a gency o f t he U nited S tates Government. N either t he U nited S tates G overnment n or any a gency t hereof, n or a ny o f t heir employees, m akes a ny w arranty, e xpress o r i mplied, o r a ssumes a ny l egal l iability o r responsibility f or t he a ccuracy, c ompleteness, o r u sefulness o f a ny i

  18. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2003-09-04

    The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

  19. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2003-06-04

    The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

  20. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2004-03-05

    The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

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

    Energy Savers [EERE]

    ISGAN-Fact-Sheet.pdf ISGAN-Fact-Sheet.pdf PDF icon ISGAN-Fact-Sheet.pdf More Documents & Publications Clean Energy Ministerial Press Fact Sheet CEM_Metrics_and_Technical_Note_7_14_10.pdf Electricity Advisory Committee Meeting Presentations October 2012 - Tuesday, October 16, 2012

    ISMS/EMS Lessons Learned Disposition Projects at SRS ISMS/EMS Lessons Learned Disposition Projects at SRS August 2009 Presenter: Joan Bozzone, NNSA SRS Track 7-5 Topics Covered: Pu Disposition Projects US Surplus

  2. 2013-01 "Action in Analysis of Disposal Pathways for Disposition of 33 Shafts"

    Broader source: Energy.gov [DOE]

    Approved January 30, 2013 The intent of this Recommendation 2013‐01 remains the same as 2010‐01, namely to discourage inaction in addressing the permanent disposition of the 33 shafts.

  3. 105-N basin sediment disposition phase-two sampling and analysis plan

    SciTech Connect (OSTI)

    Smith, R. C.

    1997-03-14

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

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

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

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

  5. DOE Standard Integration Of Environment,Safety, and Health Into Facility Disposition Activities

    Broader source: Energy.gov [DOE]

    The original release of DOE-STD-1120-98 provided integrated safety management guidance for enhancing worker, public, and environmental protection during all facility disposition activities.

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

    Broader source: Energy.gov [DOE]

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

  7. U.S. Crude Oil Supply & Disposition

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

    Sep-15 Oct-15 Nov-15 Dec-15 Jan-16 Feb-16 View History Supply Field Production (Commercial) 283,587 290,737 279,856 286,616 284,582 264,739 1920-2016 Alaskan 14,173 15,408 15,686 16,191 15,987 14,715 1981-2016 Lower 48 States 269,414 275,330 264,171 270,426 268,595 250,025 1993-2016 Imports 216,669 220,747 221,117 244,915 237,910 229,402 1920-2016 Commercial 216,669 220,747 221,117 244,915 237,910 229,402 2001-2016 Strategic Petroleum Reserve (SPR) 1977-2009 Adjustments (Commercial) 212 9,345

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

    Energy Savers [EERE]

    Project | Department of Energy Proposed Plan for the Site-wide Waste Disposition Evaluation Project Portsmouth Proposed Plan for the Site-wide Waste Disposition Evaluation Project DOE has evaluated alternatives for managing waste that would be created by decomtamination and decommissioning of the buildings at the Portsmouth Site. Three remedial alternatives for management of anticipated Portsmouth waste were developed for consideration. This Proposed Plan describes the required no-action

  9. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

    Energy Savers [EERE]

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of

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

    Office of Environmental Management (EM)

    & ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN Why DOE-EM Did This Review Approximately two million pounds of mercury are unaccounted for at Y-12 and mercury contamination has been detected in both soils and groundwater. The IFDP will

  11. Chemical Disposition of Plutonium in Hanford Site Tank Wastes

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Jones, Susan A.

    2015-05-07

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

  12. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2002-11-08

    The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through June 2002, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V post-steamflood pilot and Tar II-A post-steamflood projects. During the Third Quarter 2002, the project team essentially completed implementing the accelerated oil recovery and reservoir cooling plan for the Tar II-A post-steamflood project developed in March 2002 and is proceeding with additional related work. The project team has completed developing laboratory research procedures to analyze the sand consolidation well completion technique and will initiate work in the fourth quarter. The Tar V pilot steamflood project terminated hot water injection and converted to post-steamflood cold water injection on April 19, 2002. Proposals have been approved to repair two sand consolidated horizontal wells that sanded up, Tar II-A well UP-955 and Tar V well J-205, with gravel-packed inner liner jobs to be performed next quarter. Other well work to be performed next quarter is to convert well L-337 to a Tar V water injector and to recomplete vertical well A-194 as a Tar V interior steamflood pattern producer. Plans have been approved to drill and complete well A-605 in Tar V in the first quarter 2003. Plans have been approved to update the Tar II-A 3-D deterministic reservoir simulation model and run sensitivity cases to evaluate the accelerated oil recovery and reservoir cooling plan. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. Well work related to the Tar II-A accelerated oil recovery and reservoir cooling plan began in March 2002 with oil production increasing from 1009 BOPD in the first quarter to 1145 BOPD in the third quarter. Reservoir pressures have been increased during the quarter from 88% to 91% hydrostatic levels in the ''T'' sands and from 91% to 94% hydrostatic levels in the ''D'' sands. Well work during the quarter is described in the Reservoir Management section. The post-steamflood production performance in the Tar V pilot project has been below projections because of wellbore mechanical limitations and the loss of a horizontal producer a second time to sand inflow that are being addressed in the fourth quarter. As the fluid production temperatures exceeded 350 F, our self-imposed temperature limit, the pilot steamflood was converted to a hot waterflood project in June 2001 and converted to cold water injection on April 19, 2002.

  13. 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 equipment in the Savannah River Technology Center would need to be removed to accommodate pellet fabrication. This work would also be in a contaminated area.

  14. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2000-12-06

    Through December 1999, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar (Tar II-A) Zone. Work is continuing on improving core analysis techniques, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post steamflood project. Work was discontinued on the stochastic geologic model and developing a 3-D stochastic thermal reservoir simulation model of the Tar II-A Zone in order to focus the remaining time on using the 3-D deterministic reservoir simulation model to provide alternatives for the Tar II-A post steamflood operations and shale compaction studies. Thermal-related formation compaction is a concern of the project team due to observed surface subsidence in the local area above the Tar II-A steamflood project. On January 12, 1999, the steamflood project lost its inexpensive steam source from the Harbor Cogeneration Plant as a result of the recent deregulation of electrical power rates in California. An operational plan was developed and implemented to mitigate the effects of the two situations by injecting cold water into the flanks of the steamflood. The purpose of flank injection has been to increase and subsequently maintain reservoir pressures at a level that would fill-up the steam chests in the ''T'' and ''D'' sands before they can collapse and cause formation compaction and to prevent the steam chests from reoccurring. A new 3-D deterministic thermal reservoir simulation model was used to provide operations with the necessary water injection rates and allowable production rates by well to minimize future surface subsidence and to accurately project reservoir steam chest fill-up by October 1999. A geomechanics study and a separate reservoir simulation study have been performed to determine the possible indicators of formation compaction, the temperatures at which specific indicators are affected and the projected temperature profiles in the over and underburden shales over a ten year period following steam injection. It was believed that once steam chest fill-up occurred, the reservoir would act more like a waterflood and production and cold water injection could be operated at lower Injection to production ratios (I/P) and net injection rates. In mid-September 1999, net water injection was reduced substantially in the ''D'' sands following steam chest fill-up. This caused reservoir pressures to plummet about 100 psi within six weeks. Starting in late-October 1999, net ''D'' sand injection was increased and reservoir pressures have slowly increased back to steam chest fill-up pressures as of the end of March 2000. When the ''T'' sands reached fill-up, net ''T'' sand injection was lowered only slightly and reservoir pressures stabilized. A more detailed discussion of the operational changes is in the Reservoir Management section of this report. A reservoir pressure monitoring program was developed as part of the poststeamflood reservoir management plan. This bi-monthly sonic fluid level program measures the static fluid levels in all idle wells an average of once a month. The fluid levels have been calibrated for liquid and gas density gradients by comparing a number of them with Amerada bomb pressures taken within a few days. This data allows engineering to respond quickly to rises or declines in reservoir pressure by either increasing injection or production or idling production. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current thermal operations in the Wilm

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

    Office of Environmental Management (EM)

    D D e e p p a a r r t t m m e e n n t t o o f f E E n n e e r r g g y y O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t ( ( E E M M ) ) E E n n g g i i n n e e e e r r i i n n g g a a n n d d T T e e c c h h n n o o l l o o g g y y External Technical Review (ETR) Report Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN AUGUST 1, 2008 Acknowledgement The External Technical Review of the

  16. Draft EA for the Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched

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

    EA for the Acceptance and Disposition of Spent Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany DOE/EA-1977 DRAFT ENVIRONMENTAL ASSESSMENT FOR THE ACCEPTANCE AND DISPOSITION OF SPENT NUCLEAR FUEL CONTAINING U.S.-ORIGIN HIGHLY ENRICHED URANIUM FROM THE FEDERAL REPUBLIC OF GERMANY January 2016 U.S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE AIKEN, SOUTH CAROLINA Draft EA for the Acceptance and Disposition of Spent Nuclear Fuel Containing

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

    SciTech Connect (OSTI)

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

    2002-02-26

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

  18. Water issues associated with heavy oil production.

    SciTech Connect (OSTI)

    Veil, J. A.; Quinn, J. J.; Environmental Science Division

    2008-11-28

    Crude oil occurs in many different forms throughout the world. An important characteristic of crude oil that affects the ease with which it can be produced is its density and viscosity. Lighter crude oil typically can be produced more easily and at lower cost than heavier crude oil. Historically, much of the nation's oil supply came from domestic or international light or medium crude oil sources. California's extensive heavy oil production for more than a century is a notable exception. Oil and gas companies are actively looking toward heavier crude oil sources to help meet demands and to take advantage of large heavy oil reserves located in North and South America. Heavy oil includes very viscous oil resources like those found in some fields in California and Venezuela, oil shale, and tar sands (called oil sands in Canada). These are described in more detail in the next chapter. Water is integrally associated with conventional oil production. Produced water is the largest byproduct associated with oil production. The cost of managing large volumes of produced water is an important component of the overall cost of producing oil. Most mature oil fields rely on injected water to maintain formation pressure during production. The processes involved with heavy oil production often require external water supplies for steam generation, washing, and other steps. While some heavy oil processes generate produced water, others generate different types of industrial wastewater. Management and disposition of the wastewater presents challenges and costs for the operators. This report describes water requirements relating to heavy oil production and potential sources for that water. The report also describes how water is used and the resulting water quality impacts associated with heavy oil production.

  19. Increased oil production and reserves from improved completion techniques in the Bluebell Field, Uinta Basin, Utah. Annual report, October 1, 1994--September 30, 1995

    SciTech Connect (OSTI)

    Allison, M.L.; Morgan, C.D.

    1996-05-01

    The Bluebell field produces from the Tertiary lower Green River and Wasatch Formations of the Uinta Basin, Utah. The productive interval consists of thousands of feet of interbedded fractured clastic and carbonate beds deposited in a fluvial-dominated deltaic lacustrine environment. Wells in the Bluebell field are typically completed by perforating 40 or more beds over 1,000 to 3,000 vertical feet (300-900 m), then applying an acid-fracture stimulation treatment to the entire interval. This completion technique is believed to leave many potentially productive beds damaged and/or untreated, while allowing water-bearing and low-pressure (thief) zones to communicate with the wellbore. Geologic and engineering characterization has been used to define improved completion techniques. The study identified reservoir characteristics of beds that have the greatest long-term production potential.

  20. EA-1488: Environmental Assessment for the U-233 Disposition,...

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

    Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National ... Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National ...

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

    SciTech Connect (OSTI)

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

    2010-12-15

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

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

    SciTech Connect (OSTI)

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

    2009-09-10

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

  3. Increased oil production and reserves from improved completion techniques in the Bluebell field, Uinta Basin, Utah. Annual report, October 1, 1995--September 30, 1996

    SciTech Connect (OSTI)

    Morgan, C.D.; Allison, M.L.

    1997-08-01

    The Bluebell field is productive from the Tertiary lower Green River and Wasatch Formations of the Uinta Basin, Utah. The productive interval consists of thousands of feet of interbedded fractured clastic and carbonate beds deposited in a fluvial-dominated lacustrine environment. Wells in the Bluebell field are typically completed by perforating 40 or more beds over 1,000 to 3,000 vertical feet (300-900 m), then stimulating the entire interval. This completion technique is believed to leave many potentially productive beds damaged and/or untreated, while allowing water-bearing and low-pressure (thief) zones to communicate with the wellbore. Geologic and engineering characterization has been used to define improved completion techniques. A two-year characterization study involved detailed examination of outcrop, core, well logs, surface and subsurface fractures, produced oil-field waters, engineering parameters of the two demonstration wells, and analysis of past completion techniques and effectiveness. The characterization study resulted in recommendations for improved completion techniques and a field-demonstration program to test those techniques. The results of the characterization study and the proposed demonstration program are discussed in the second annual technical progress report. The operator of the wells was unable to begin the field demonstration this project year (October 1, 1995 to September 20, 1996). Correlation and thickness mapping of individual beds in the Wasatch Formation was completed and resulted in a. series of maps of each of the individual beds. These data were used in constructing the reservoir models. Non-fractured and fractured geostatistical models and reservoir simulations were generated for a 20-square-mile (51.8-km{sup 2}) portion of the Bluebell field. The modeling provides insights into the effects of fracture porosity and permeability in the Green River and Wasatch reservoirs.

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

    SciTech Connect (OSTI)

    Walker, Stuart

    2013-07-01

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

  5. U.S. and Russia Sign Plan for Russian Plutonium Disposition | Department of

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

    Energy Sign Plan for Russian Plutonium Disposition U.S. and Russia Sign Plan for Russian Plutonium Disposition November 19, 2007 - 4:31pm Addthis Will Eliminate Enough Russian Plutonium for Thousands of Nuclear Weapons WASHINGTON, DC -U.S. Secretary of Energy Samuel W. Bodman and Russian Federal Atomic Energy Agency Director Sergey Kiriyenko have signed a joint statement outlining a plan to dispose of 34 metric tons of surplus plutonium from Russia's weapons program. Under the new plan, the

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

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

    Annual Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Supply",5,"Annual",2015,"6/30/1930" ,"Data 2","Disposition",5,"Annual",2015,"6/30/1930" ,"Release Date:","4/29/2016" ,"Next Release

  7. Horizontal Wells to Enhance Production in the Bottle Rock Field - Final Report - 09/30/2000 - 02/01/2001

    SciTech Connect (OSTI)

    Cohen, J. H.

    2001-02-26

    This report describes the work that was done to prepare the Phase II proposal for an enhanced geothermal system based on the use of horizontal well to increase production of reservoir fluids from geothermal wells.

  8. USING CABLE SUSPENDED SUBMERSIBLE PUMPS TO REDUCE PRODUCTION COSTS TO INCREASE ULTIMATE RECOVERY IN THE RED MOUNTAIN FIELD IN SAM JUAN BASIN REGION

    SciTech Connect (OSTI)

    Don L. Hanosh

    2004-08-01

    A joint venture between Enerdyne LLC, a small independent oil and gas producer, and Pumping Solutions Inc., developer of a low volume electric submersible pump, suspended from a cable, both based in Albuquerque, New Mexico, has re-established marginal oil production from the Red Mountain Oil Field, located in the San Juan Basin, New Mexico by working over 17 existing wells and installing submersible pumps.

  9. Plutonium_Disposition_Phase_2_TOR_082015_FINAL

    National Nuclear Security Administration (NNSA)

    ... Future, Report to the Secretary of Energy, January 2012. 14 "Preapplication Safety ... to early concept design of green-field facilities that were produced in the 1990's. ...

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

    SciTech Connect (OSTI)

    Brough, W.G.; Boerigter, S.T.

    1995-04-06

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

  11. Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01

    Broader source: Energy.gov [DOE]

    The Used Fuel Disposition Campaign (UFDC) conducts R&D activities related to storage, transportation and disposal of used nuclear fuel and high level nuclear waste (for existing and future fuels); deep geologic disposal R&D activities are outlined and prioritized on the basis of gaps in understanding and benefit derived from R&D to narrow such gaps.

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

    Broader source: Energy.gov [DOE]

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

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

    SciTech Connect (OSTI)

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

    2012-12-11

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

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

    SciTech Connect (OSTI)

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

    2012-12-20

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

  15. 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.

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

    SciTech Connect (OSTI)

    1994-04-30

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

  17. ARM - TCAP Field Campaign

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

    Value-Added Products PI Data Products Field Campaign Data Related Data Data Plots Data Policy Data Documentation Data Gathering and Delivery Data Quality Data Tools Data Archive...

  18. Rapid production of large-area deep sub-wavelength hybrid structures by femtosecond laser light-field tailoring

    SciTech Connect (OSTI)

    Wang, Lei; Chen, Qi-Dai E-mail: hbsun@jlu.edu.cn; Yang, Rui; Xu, Bin-Bin; Wang, Hai-Yu; Yang, Hai; Huo, Cheng-Song; Tu, Hai-Ling; Sun, Hong-Bo E-mail: hbsun@jlu.edu.cn

    2014-01-20

    The goal of creation of large-area deep sub-wavelength nanostructures by femtosecond laser irradiation onto various materials is being hindered by the limited coherence length. Here, we report solution of the problem by light field tailoring of the incident beam with a phase mask, which serves generation of wavelets. Direct interference between the wavelets, here the first-order diffracted beams, and interference between a wavelet and its induced waves such as surface plasmon polariton are responsible for creation of microgratings and superimposed nanogratings, respectively. The principle of wavelets interference enables extension of uniformly induced hybrid structures containing deep sub-wavelength nanofeatures to macro-dimension.

  19. AEO2011:Total Energy Supply, Disposition, and Price Summary ...

    Open Energy Info (EERE)

    case. The dataset uses quadrillion Btu and the U.S. Dollar. The data is broken down into production, imports, exports, consumption and price. Data and Resources AEO2011:Total...

  20. Measurements of actinide-fission product yields in Caliban and Prospero metallic core reactor fission neutron fields

    SciTech Connect (OSTI)

    Casoli, P.; Authier, N. [CEA, Centre de Valduc, 21120 Is-sur-Tille (France); Laurec, J.; Bauge, E.; Granier, T. [CEA, Centre DIF, 91297 Arpajon (France)

    2011-07-01

    In the 1970's and early 1980's, an experimental program was performed on the facilities of the CEA Valduc Research Center to measure several actinide-fission product yields. Experiments were, in particular, completed on the Caliban and Prospero metallic core reactors to study fission-neutron-induced reactions on {sup 233}U, {sup 235}U, and {sup 239}Pu. Thick actinide samples were irradiated and the number of nuclei of each fission product was determined by gamma spectrometry. Fission chambers were irradiated simultaneously to measure the numbers of fissions in thin deposits of the same actinides. The masses of the thick samples and the thin deposits were determined by mass spectrometry and alpha spectrometry. The results of these experiments will be fully presented in this paper for the first time. A description of the Caliban and Prospero reactors, their characteristics and performances, and explanations about the experimental approach will also be given in the article. A recent work has been completed to analyze and reinterpret these measurements and particularly to evaluate the associated uncertainties. In this context, calculations have also been carried out with the Monte Carlo transport code Tripoli-4, using the published benchmarked Caliban description and a three-dimensional model of Prospero, to determine the average neutron energy causing fission. Simulation results will be discussed in this paper. Finally, new fission yield measurements will be proposed on Caliban and Prospero reactors to strengthen the results of the first experiments. (authors)

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

    SciTech Connect (OSTI)

    Nutt, W. M.

    2010-10-01

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

  2. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2000-12-06

    Through March 2000, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar (Tar II-A) Zone. Work is continuing on improving core analysis techniques, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post steamflood project. Work was discontinued on the stochastic geologic model and developing a 3-D stochastic thermal reservoir simulation model of the Tar II-A Zone so the project team could use the 3-D deterministic reservoir simulation model to provide alternatives for the Tar II-A post steamflood operations and shale compaction studies. The project team spent the second quarter 2000 writing the 1997-2000 Annual Report, completing research for the project on the subjects mentioned above, and operating the Tar II-A post-steamflood project and the Tar V horizontal well steamflood pilot. Thermal-related formation compaction is a concern of the project team due to observed surface subsidence in the local area above the Tar II-A steamflood project. On January 12, 1999, the steamflood project lost its inexpensive steam source from the Harbor Cogeneration Plant as a result of the recent deregulation of electrical power rates in California. An operational plan was developed and implemented to mitigate the effects of the two situations by injecting cold water into the flanks of the steamflood. The purpose of flank injection has been to increase and subsequently maintain reservoir pressures at a level that would fill-up the steam chests in the ''T'' and ''D'' sands before they can collapse and cause formation compaction and to prevent the steam chests from reoccurring. A new 3-D deterministic thermal reservoir simulation model was used to provide operations with the necessary water injection rates and allowable production rates by well to minimize future surface subsidence and to accurately project reservoir steam chest fill-up by October 1999. A geomechanics study and a separate reservoir simulation study have been performed to determine the possible indicators of formation compaction, the temperatures at which specific indicators are affected and the projected temperature profiles in the over and underburden shales over a ten year period following steam injection. Further geomechanics work should be conducted. It was believed that once steam chest fill-up occurred, the reservoir would act more like a waterflood and production and cold water injection could be operated at lower Injection to production ratios (I/P) and net injection rates. In mid-September 1999, net water injection was reduced substantially in the ''D'' sands following steam chest fill-up. This caused reservoir pressures to plummet about 100 psi within six weeks. Starting in late-October 1999, net ''D'' sand injection was increased and reservoir pressures have slowly increased back to steam chest fill-up pressures as of the end of March 2000. When the ''T'' sands reached fill-up, net ''T'' sand injection remained at a high rate and reservoir pressures stabilized. A more detailed discussion of the operational changes is in the Reservoir Management section of this report. A reservoir pressure monitoring program was developed as part of the poststeamflood reservoir management plan. This bi-monthly sonic fluid level program measures the static fluid levels in all idle wells an average of once a month. The fluid levels have been calibrated for liquid and gas density gradients by comparing a number of them with Amerada bomb pressures taken within a few days. This data allows engineering to respond quickly to rises or declines in reservoir pressure by either increasing injection or production or idling production. Expanding thermal recovery oper

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

    SciTech Connect (OSTI)

    Gray, L.W.; Kan, T.; McKibben, J.M.

    1996-03-15

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

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

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

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

    SciTech Connect (OSTI)

    1995-05-01

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

  6. INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES

    SciTech Connect (OSTI)

    Scott Hara

    2000-12-14

    Through June 2000, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar (Tar II-A) Zone. Work is continuing on improving core analysis techniques, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post steamflood project. Work was discontinued on the stochastic geologic model and developing a 3-D stochastic thermal reservoir simulation model of the Tar II-A Zone so the project team could use the 3-D deterministic reservoir simulation model to provide alternatives for the Tar II-A post steamflood operations and shale compaction studies. The project team spent the third quarter 2000 revising the draft 1997-2000 Annual Report submitted last quarter, writing final reports on the research projects mentioned above, and operating the Tar II-A post-steamflood project and the Tar V horizontal well steamflood pilot. Thermal-related formation compaction is a concern of the project team due to observed surface subsidence in the local area above the Tar II-A steamflood project. On January 12, 1999, the steamflood project lost its inexpensive steam source from the Harbor Cogeneration Plant as a result of the recent deregulation of electrical power rates in California. An operational plan was developed and implemented to mitigate the effects of the two situations by injecting cold water into the flanks of the steamflood. The purpose of flank injection has been to increase and subsequently maintain reservoir pressures at a level that would fill-up the steam chests in the ''T'' and ''D'' sands before they can collapse and cause formation compaction and to prevent the steam chests from reoccurring. A new 3-D deterministic thermal reservoir simulation model was used to provide operations with the necessary water injection rates and allowable production rates by well to minimize future surface subsidence and to accurately project reservoir steam chest fill-up by October 1999. A geomechanics study and a separate reservoir simulation study have been performed to determine the possible indicators of formation compaction, the temperatures at which specific indicators are affected and the projected temperature profiles in the over and underburden shales over a ten year period following steam injection. Further geomechanics work should be conducted. It was believed that once steam chest fill-up occurred, the reservoir would act more like a waterflood and production and cold water injection could be operated at lower Injection to production ratios (I/P) and net injection rates. In mid-September 1999, net water injection was reduced substantially in the ''D'' sands following steam chest fill-up. This caused reservoir pressures to plummet about 100 psi within six weeks. Starting in late-October 1999, net ''D'' sand injection was increased and reservoir pressures increased back to steam chest fill-up pressures of 90% hydrostatic pressure by March 2000 and have been maintained through September 2000. When the ''T'' sands reached fill-up in October 1999, net ''T'' sand injection remained at a high rate through April 2000 and reservoir pressures stabilized at 98% hydrostatic pressure. The objective is to lower ''T'' sand pressure slowly to 90% hydrostatic. Net injection was reduced and ''T'' sand reservoir pressure was at 97% hydrostatic in September 2000. A more detailed discussion of the operational changes is in the Reservoir Management section of this report. A reservoir pressure monitoring program was developed as part of the poststeamflood reservoir management plan. This bi-monthly sonic fluid level program measures the static fluid levels in all idle wells an average of once a month.

  7. DOE-STD-1120-2005; Integration of Environment, Safety, and Health into Facility Disposition Activities

    Office of Environmental Management (EM)

    120-2005 Volume 2 of 2 DOE STANDARD INTEGRATION OF ENVIRONMENT, SAFETY, AND HEALTH INTO FACILITY DISPOSITION ACTIVITIES Volume 2 of 2: Appendices U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak

  8. DOE SEEKS CONTRACTOR TO DISPOSITION WASTE AT THE ADVANCED MIXED WASTE

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

    TREATMENT PROJECT (AMWTP) SEEKS CONTRACTOR TO DISPOSITION WASTE AT THE ADVANCED MIXED WASTE TREATMENT PROJECT (AMWTP) Inside the AMWTP facility The AMWTP facility Idaho Falls - The U.S. Department of Energy, Idaho Operations Office, in coordination with the Office of Environmental Management today released a Final �Request for Proposal� to obtain a contractor to perform waste processing at the Advanced Mixed Waste Treatment Project at the Department�s Idaho Site near Idaho Falls,

  9. LANL's Role in the U.S. Fissile Material Disposition Program

    SciTech Connect (OSTI)

    Whitworth, Julia; Kay, Virginia

    2015-02-18

    The process of Fissile Material Disposition is in part a result of the Advanced Recovery and Integrated Extraction System (ARIES), which is an agreement between the U.S. and Russia to dispose of excess plutonium used to make weapons. LANL is one sight that aides in the process of dismantling, storage and repurposing of the plutonium gathered from dismantled weapons. Some uses for the repurposed plutonium is fuel for commercial nuclear reactors which will provide energy for citizens.

  10. RECOMMENDATION FOR DISPOSITION OF REMOTE-HANDLED WASTE BURIED IN 33 SHAFTS AT TA-54

    Office of Environmental Management (EM)

    0-01 Approved by the NNMCAB on January 27, 2010 NORTHERN NEW MEXICO CITIZENS' ADVISORY BOARD (NNMCAB) Waste Management Committee Recommendation to the Department of Energy No. 2010-01 Recommendation for Disposition of Remote-handled Waste Buried in 33 Shafts at Technical Area 54 (TA-54) Background The Consent Order between the State of New Mexico, the Department of Energy/National Nuclear Safety Administration (DOE/NNSA) and Los Alamos National Security (LANS) requires that TA-54 Material

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

    SciTech Connect (OSTI)

    Bunch, Kyle J.; Jones, Anthony M.; Ramuhalli, Pradeep; Benz, Jacob M.; Denlinger, Laura Schmidt

    2014-05-04

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

  12. The effect of chlorine substitution on the disposition of polychlorinated biphenyls following dermal administration

    SciTech Connect (OSTI)

    Garner, C. Edwin . E-mail: cegarner@rti.org; Demeter, Jennifer; Matthews, H.B.

    2006-10-01

    The fate of selected polychlorobiphenyls (PCBs) was investigated following single dermal administration (0.4 mg/kg) to determine the effects of chlorine content and position on the disposition of PCBs following dermal absorption. Single dermal doses of {sup 14}C-labeled mono-, di-, tetra- and hexachlorobiphenyls were administered to 1 cm{sup 2} areas on the backs of F-344 male rats. Distribution of radioactivity in selected tissues and excreta was determined by serial sacrifice at time points up to 2 weeks. Unabsorbed radioactivity was removed from the dose site at either sacrifice or 48 h post-dose. The time course of radioactivity in the tissues showed a dependence on rate and extent of absorption. The most rapidly absorbed PCBs reached peak tissue concentrations at early times and were cleared from the tissues rapidly. The higher chlorinated PCBs were slowly absorbed and tended to accumulate in the adipose and skin after removal of unabsorbed dose. Excretion of absorbed radioactivity varied with chlorine content ranging from 27% to ca. 100% at 2 weeks post-dose. Excretion profiles following dermal doses tended to differ from profiles following equivalent IV doses, as did the metabolite profiles in excreta. Skin slice incubation experiments suggested that first pass metabolism in the dermal dose site was responsible for metabolism and disposition differences between routes of administration. The data further suggest that the rate of absorption, and therefore the disposition of PCBs following dermal administration may be mediated, either in part or fully, by transdermal metabolism.

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

    SciTech Connect (OSTI)

    Williams, K.A.

    1999-10-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

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

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

    SciTech Connect (OSTI)

    1998-05-01

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

  16. DRAFT EM SSAB Chair's Meeting Waste Disposition Strategies Update

    Office of Environmental Management (EM)

    Fiscal Year 2016 Budget Genna Hackett Budget Analyst Environmental Management Los Alamos Field Office January 27, 2016 Northern New Mexico Citizens' Advisory Board Meeting www.energy.gov/EM 2 LOS ALAMOS (EM-LA) Agenda EM-HQ FY 2016 Funding Request EM-LA FY 2016 Appropriation FY 2016 Key Planned Scope FY 2016 In-Progress Summary www.energy.gov/EM 3 LOS ALAMOS (EM-LA) EM FY 2016 Funding Request Radioactive Liquid Tank Waste $ 2,297M / 39% Site Services** $ 413M /7% Soil and

  17. Class III Mid-Term Project, "Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies"

    SciTech Connect (OSTI)

    Scott Hara

    2007-03-31

    The overall objective of this project was to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involved improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective has been to transfer technology that can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The first budget period addressed several producibility problems in the Tar II-A and Tar V thermal recovery operations that are common in SBC reservoirs. A few of the advanced technologies developed include a three-dimensional (3-D) deterministic geologic model, a 3-D deterministic thermal reservoir simulation model to aid in reservoir management and subsequent post-steamflood development work, and a detailed study on the geochemical interactions between the steam and the formation rocks and fluids. State of the art operational work included drilling and performing a pilot steam injection and production project via four new horizontal wells (2 producers and 2 injectors), implementing a hot water alternating steam (WAS) drive pilot in the existing steamflood area to improve thermal efficiency, installing a 2400-foot insulated, subsurface harbor channel crossing to supply steam to an island location, testing a novel alkaline steam completion technique to control well sanding problems, and starting on an advanced reservoir management system through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation. The second budget period phase (BP2) continued to implement state-of-the-art operational work to optimize thermal recovery processes, improve well drilling and completion practices, and evaluate the geomechanical characteristics of the producing formations. The objectives were to further improve reservoir characterization of the heterogeneous turbidite sands, test the proficiency of the three-dimensional geologic and thermal reservoir simulation models, identify the high permeability thief zones to reduce water breakthrough and cycling, and analyze the nonuniform distribution of the remaining oil in place. This work resulted in the redevelopment of the Tar II-A and Tar V post-steamflood projects by drilling several new wells and converting idle wells to improve injection sweep efficiency and more effectively drain the remaining oil reserves. Reservoir management work included reducing water cuts, maintaining or increasing oil production, and evaluating and minimizing further thermal-related formation compaction. The BP2 project utilized all the tools and knowledge gained throughout the DOE project to maximize recovery of the oil in place.

  18. A Study of Production/Injection Data from Slim Holes and Large-Diameter Wells at the Okuaizu Geothermal Field, Tohoku, Japan

    SciTech Connect (OSTI)

    Renner, Joel Lawrence; Garg, Sabodh K.; Combs, Jim

    2002-06-01

    Discharge from the Okuaizu boreholes is accompanied by in situ boiling. Analysis of cold-water injection and discharge data from the Okuaizu boreholes indicates that the two-phase productivity index is about an order of magnitude smaller than the injectivity index. The latter conclusion is in agreement with analyses of similar data from Oguni, Sumikawa, and Kirishima geothermal fields. A wellbore simulator was used to examine the effect of borehole diameter on the discharge capacity of geothermal boreholes with two-phase feedzones. Based on these analyses, it appears that it should be possible to deduce the discharge characteristics of largediameter wells using test data from slim holes with two-phase feeds.

  19. Linking Legacies: Connecting the Cold War Nuclear Weapons Production

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

    Processes to Their Environmental Consequences | Department of Energy Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences This report described each step in the cycle of nuclear weapons production and defined for the first time a planned disposition path for all waste streams generated prior to 1992 as a result of

  20. table06.chp:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Ending Production Production of Entry a Crude Oil b Receipts ...

  1. table04.chp:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Ending Production Production of Entry a Crude Oil b Receipts ...

  2. TABLE11.CHP:Corel VENTURA

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

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Production Production of Entry a Crude Oil b Receipts Change ...

  3. table07.chp:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Production Production of Entry a Crude Oil b Receipts Change ...

  4. table03.chp:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Unaccounted Field Refinery For Crude Stock Crude Refinery Products Production Production Imports Oil a Change b Losses Inputs Exports Supplied c Energy ...

  5. table08.chp:Corel VENTURA

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

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Ending Production Production of Entry a Crude Oil b Receipts ...

  6. TABLE12.CHP:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Ending Production Production of Entry a Crude Oil b Receipts ...

  7. table10.chp:Corel VENTURA

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

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Ending Production Production of Entry a Crude Oil b Receipts ...

  8. table09.chp:Corel VENTURA

    Gasoline and Diesel Fuel Update (EIA)

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Production Production of Entry a Crude Oil b Receipts Change ...

  9. table02.chp:Corel VENTURA

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

    ... Supply Disposition Commodity Unaccounted Field Refinery For Crude Stock Crude Refinery Products Ending Production Production Imports Oil a Change b Losses Inputs Exports Supplied c ...

  10. table05.chp:Corel VENTURA

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

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Production Production of Entry a Crude Oil b Receipts Change ...

  11. TABLE13.CHP:Corel VENTURA

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

    ... Supply Disposition Commodity Imports by Unac- PAD counted Field Refinery District For Net Stock Crude Refinery Products Production Production of Entry a Crude Oil b Receipts Change ...

  12. Petroleum Supply Monthly

    Gasoline and Diesel Fuel Update (EIA)

    Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, September 2005 (Thousand Barrels) Field Production Refinery and Blender Net Production...

  13. Trade study for the disposition of cesium and strontium capsules

    SciTech Connect (OSTI)

    Claghorn, R.D.

    1996-03-01

    This trade study analyzes alternatives for the eventual disposal of cesium and strontium capsules currently stored at the Waste Encapsulation and Storage Facility as by-product. However, for purposes of this study, it is assumed that at some time in the future, the capsules will be declared high-level waste and therefore will require disposal at an offsite geologic repository. The study considered numerous alternatives and selected three for detailed analysis: (1) overpack and storage at high-level waste canister storage building, (2) overpack at the high-level waste vitrification facility followed by storage at a high-level waste canister storage building, and (3) blend capsule contents with other high-level waste feed streams and vitrify at the high-level waste vitrification facility.

  14. Verification and Validation Strategy for Implementation of Hybrid Potts-Phase Field Hydride Modeling Capability in MBM

    SciTech Connect (OSTI)

    Jason D. Hales; Veena Tikare

    2014-04-01

    The Used Fuel Disposition (UFD) program has initiated a project to develop a hydride formation modeling tool using a hybrid Pottsphase field approach. The Potts model is incorporated in the SPPARKS code from Sandia National Laboratories. The phase field model is provided through MARMOT from Idaho National Laboratory.

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

    SciTech Connect (OSTI)

    Birkholzer, J.T.

    2011-06-01

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

  16. 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.

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

    Energy Savers [EERE]

    5 (06-93) 05-90 Edition May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION OMB Control No. 1910-1700 OMB Burden Disclosure Statement on Back 1. Control Number 2a. Organizational Unit and Routing Symbol 2b. Departmental Organization Contractor Organization 3a. Volume On Hand (Cu. Ft.) 3b. Volume Accumulated Annually (Estimate Cu. Ft.) 4. Record Dates (From/To) 5. Identification of Filing Unit (Include type of record, function performed, security

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

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

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

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

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

  20. Used Fuel Disposition Campaign Phase I Ring Compression Testing of High

    Energy Savers [EERE]

    Burnup Cladding | Department of Energy Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression testing is to generate data to support the development of the technical basis for extended storage and transportation of high-burnup fuel. This report highlights the results of completed Phase I testing of high-burnup M5® cladding and the revised three-year test plan. The goal

  1. DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced

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

    Mixed Waste Treatment Project Media Contact: Brad Bugger (208) 526-0833 For Immediate Release: Friday, May 27, 2011 DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project Contract will continue cleanup and waste operations at the Idaho Site Idaho Falls � In order to further meet the U.S. Department of Energy�s commitments to the citizens of the state of Idaho, the DOE today announced that it has selected Idaho Treatment Group, LLC (ITG)

  2. DOE issues Finding of No Significant Impact on the Disposition of Five

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

    Signature Properties at Idaho National Laboratory September 22, 2014 NEWS MEDIA CONTACT: DOE-Idaho - Tim Jackson, (208) 526-8484 DOE issues Finding of No Significant Impact on the Disposition of Five Signature Properties at Idaho National Laboratory The U.S. Department of Energy (DOE) has determined that tearing down four World War II-era historic structures and part of another structure at Idaho National Laboratory's Central Facilities Area that remain from when the area served as the U.S.

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

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26

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

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

    SciTech Connect (OSTI)

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

    1996-09-01

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

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

    SciTech Connect (OSTI)

    Wyrwas, R. B.

    2015-09-30

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

  6. Final report for 105-N Basin sediment disposition task, phase 2 -- samples BOMPC8 and BOMPC9

    SciTech Connect (OSTI)

    Esch, R.A.

    1998-02-05

    This document is the final report deliverable for Phase 2 analytical work for the 105-N Basin Sediment Disposition Task. On December 23, 1997, ten samples were received at the 222-S Laboratory as follows: two (2) bottles of potable water, six (6) samples for process control testing and two (2) samples for characterization. Analyses were performed in accordance with the Letter of Instruction for Phase 2 Analytical Work for the 105-N Basin Sediment Disposition Task (Logan and Kessner, 1997) (Attachment 7) and 105-N Basin Sediment Disposition Phase-Two Sampling and Analysis Plan (SAP) (Smith, 1997). The analytical results are included in Table 1. This document provides the values of X/Qs for the onsite and offsite receptors, taking into account the building wake and the atmospheric stability effects. X/Qs values for the potential fire accident were also calculated. In addition, the unit dose were calculated for the mixtures of isotopes.

  7. USING 3D COMPUTER MODELING, BOREHOLE GEOPHYSICS, AND HIGH CAPACITY PUMPS TO RESTORE PRODUCTION TO MARGINAL WELLS IN THE EAST TEXAS FIELD

    SciTech Connect (OSTI)

    R.L. Bassett

    2003-06-09

    Methods for extending the productive life of marginal wells in the East Texas Field were investigated using advanced computer imaging technology, geophysical tools, and selective perforation of existing wells. Funding was provided by the Department of Energy, TENECO Energy and Schlumberger Wireline and Testing. Drillers' logs for more than 100 wells in proximity to the project lease were acquired, converted to digital format using a numerical scheme, and the data were used to create a 3 Dimensional geological image of the project site. Using the descriptive drillers' logs in numerical format yielded useful cross sections identifying the Woodbine Austin Chalk contact and continuity of sand zones between wells. The geological data provided information about reservoir continuity, but not the amount of remaining oil, this was obtained using selective modern logs. Schlumberger logged the wells through 2 3/8 inch tubing with a new slimhole Reservoir Saturation Tool (RST) which can measure the oil and water content of the existing porosity, using neutron scattering and a gamma ray spectrometer (GST). The tool provided direct measurements of elemental content yielding interpretations of porosity, lithology, and oil and water content, confirming that significant oil saturation still exists, up to 50% in the upper Woodbine sand. Well testing was then begun and at the end of the project new oil was being produced from zones abandoned or bypassed more than 25 years ago.

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

    SciTech Connect (OSTI)

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

    2002-02-26

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

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

    SciTech Connect (OSTI)

    1998-05-01

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

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

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

    SciTech Connect (OSTI)

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

    2010-09-01

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

  12. 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.

  13. 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.

  14. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

  15. 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.

  16. DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.

  17. DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)

    Office of Environmental Management (EM)

    651 Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee U. S. Department of Energy Oak Ridge Office Oak Ridge, Tennessee January 2010 FINDING OF NO SIGNIFICANT IMPACT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the

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

    SciTech Connect (OSTI)

    1997-01-01

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

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

    SciTech Connect (OSTI)

    Duncan, A.

    2007-12-31

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

  20. Increased oil production and reserves from improved completion techniques in the Bluebell Field, Uinta Basin, Utah. Quarterly technical progress report, April 1, 1996--June 30, 1996, 11th Quarter of the project

    SciTech Connect (OSTI)

    Allison, E.; Morgan, C.D.

    1996-07-30

    The objective of this project is to increase oil production and reserves in the Uinta Basin by demonstrating improved completion techniques. Low productivity of Uinta Basin wells is caused by gross production intervals of several thousand feet that contain perforated thief zones, water-bearing zones, and unperforated oil-bearing intervals. Geologic and engineering characterization and computer simulation of the Green River and Wasatch formations in the Bluebell field will determine reservoir heterogeneities related to fractures and depositional trends. This will be followed by drilling and recompletion of several wells to demonstrate improved completion techniques based on the reservoir characterization. Transfer of the project results will be an ongoing component of the project.

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

    SciTech Connect (OSTI)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-02-26

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

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

    SciTech Connect (OSTI)

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

    2015-01-13

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

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

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze; Dr. Koji Shirai

    2012-07-01

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

  4. Field-to-Fuel Performance Testing of Various Biomass Feedstocks: Production and Catalytic Upgrading of Bio-Oil to Refinery Blendstocks (Presentation)

    SciTech Connect (OSTI)

    Carpenter, D.; Westover, T.; Howe, D.; Evans, R.; French, R.; Kutnyakov, I.

    2014-09-01

    Large-scale, cost-competitive deployment of thermochemical technologies to replace petroleum oil with domestic biofuels will require inclusion of high volumes of low-cost, diverse biomass types into the supply chain. However, a comprehensive understanding of the impacts of feedstock thermo-physical and chemical variability, particularly inorganic matter (ash), on the yield and product distribution

  5. Experiences in the design of CRA`s for erosion/corrosion control in the production facilities of eastern Venezuela oil fields

    SciTech Connect (OSTI)

    Romero, N.; Palacios, C.A.

    1997-08-01

    It is a well known fact that CRA`s are used in the oil industry as one way to control erosion/corrosion effects. Many fields in the eastern region of Venezuela are considered corrosive due to the presence of CO{sub 2} (5 to 20%), H{sub 2}S (up to 5 ppm), and water (50% water cut) contained in the produced hydrocarbons (condensated). For some areas, the hydrocarbon is accompanied by sand, making them erosive as well. These conditions and frequent failures experienced in the field, led to the use of CRA`s. For the wells, 13% Cr and bimetallic (carbon steel/13% Cr) tubing was used for 51 condensate wells containing 5 to 20% CO{sub 2}. For the surface equipment (valves, reducers, expanders and other types of fittings) tungsten carbide hard facing were used, for some of the valves, a epoxi-phenolic coating was used. This article describes the different design criteria used for the installation of the tubing, the logistics involved during field inspections and handling tips to avoid galling during workovers. It also, presents results from the bi-metallic tubing and the hard facings used for the surface equipment.

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

    SciTech Connect (OSTI)

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

    2013-08-08

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

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

    SciTech Connect (OSTI)

    Barber, James; Buckley, James

    2003-02-23

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

  8. Natural Gas Receipts Across U.S. Borders (Annual Supply & Disposition)

    Gasoline and Diesel Fuel Update (EIA)

    Productive Capacity for the Lower-48 States 1985 - 2003 EIA Home > Natural Gas > Natural Gas Analysis Publications Natural Gas Productive Capacity for the Lower-48 States 1985 - 2003 Printer-Friendly Version gascapdata.xls ratiodata.xls wellcountdata.xls Executive Summary This analysis examines the availability of effective productive capacity to meet the projected wellhead demand for natural gas through 2003. Effective productive capacity is defined as the maximum production available

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

    SciTech Connect (OSTI)

    Rodriguez, M.

    2010-12-17

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

  10. Kansas City Field Office Mark Holecek Assoc. Admin. & Dep.

    National Nuclear Security Administration (NNSA)

    Nevada Field Office Steven Lawrence NNSA Production Office Geoffrey Beausoleil Sandia Field Office Jeffrey P. Harrell Savannah River Field Office Douglas Dearolph Chief of Staff ...

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

    SciTech Connect (OSTI)

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

    2004-10-03

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

  12. Validation Study for Crediting Chlorine in Criticality Analyses for US Spent Nuclear Fuel Disposition

    SciTech Connect (OSTI)

    Sobes, Vladimir; Scaglione, John M.; Wagner, John C.; Dunn, Michael E.

    2015-01-01

    Spent nuclear fuel (SNF) management practices in the United States rely on dry storage systems that include both canister- and cask-based systems. The United States Department of Energy Used Fuel Disposition Campaign is examining the feasibility of direct disposal of dual-purpose (storage and transportation) canisters (DPCs) in a geological repository. One of the major technical challenges for direct disposal is the ability to demonstrate the subcriticality of the DPCs loaded with SNF for the repository performance period (e.g., 10,000 years or more) as the DPCs may undergo degradation over time. Specifically, groundwater ingress into the DPC (i.e., flooding) could allow the system to achieve criticality in scenarios where the neutron absorber plates in the DPC basket have degraded. However, as was shown by Banerjee et al., some aqueous species in the groundwater provide noticeable reactivity reduction for these systems. For certain amounts of particular aqueous species (e.g., chlorine, lithium) in the groundwater, subcriticality can be demonstrated even for DPCs with complete degradation of the neutron absorber plates or a degraded fuel basket configuration. It has been demonstrated that chlorine is the leading impurity, as indicated by significant neutron absorption in the water that is available in reasonable quantities for the deep geological repository media under consideration. This paper presents the results of an investigation of the available integral experiments worldwide that could be used to validate DPC disposal criticality evaluations, including credit for chlorine. Due to the small number of applicable critical configurations, validation through traditional trending analysis was not possible. The bias in the eigenvalue of the application systems due only to the chlorine was calculated using TSURFER analysis and found to be on the order of 100 percent mille (1 pcm = 10-5 keff). This study investigated the design of a series of critical configurations with varying amounts of chlorine to address validation gaps. Such integral experiments would support the crediting of the chlorine neutron-absorption properties in groundwater and the demonstration of subcriticality for DPCs in deep geologic repositories with sufficient chlorine availability.

  13. Field Guide

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

    Field Facilities Contacts for Printing and Mail Field Facilities Contacts for Printing and Mail This is the list of DOE field facilities contacts for Printing and Mail as of April 27, 2011. Go to Mail Services Go to Printing Services PDF icon Field_Facilities_Contacts_Print-Mail.pdf More Documents & Publications Director's Perspective by George Miller Tenant Education and Training Fire Safety Committee Membership List

    Ecologist for a Day Field Guide Program supported by: ©2011, Savannah

  14. U.S. Department of Energy National Nuclear Security Administration Los Alamos Field Office Overview Presentation to: Name Title

    Office of Environmental Management (EM)

    Environmental Management Los Alamos Field Office Legacy Cleanup Completion Project WELCOME Northern New Mexico Citizens' Advisory Board November 12, 2015 Doug Hintze EM-LA Manager History of Work Completed  Environmental Management Accomplishments at LANL * Soil and Groundwater * Legacy Waste Disposition * Demolition & Decommissioning 2 Soil and Groundwater 3 Mercury-contaminated soil being excavated Preparing mercury-contaminated soil for shipment Restoration of work at TA-32 Soil and

  15. DOE/EIS-0287-SA-01: Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (June 2005)

    Office of Environmental Management (EM)

    7 -SA-Ol SUPPLEMENT ANALYSIS For The Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement June 2005 United States Department of Energy Idaho Operations Office 1.0 2.0 3.0 4.0 5.0 6.0 DOEÆIS-0287 -SA-O 1 TABLE OF CONTENTS Introduction......................................................................................................................... 4

  16. 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.

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

    SciTech Connect (OSTI)

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

    2013-09-19

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

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

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09

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

  19. Petroleum Supply Annual 2005, Volume 1

    Gasoline and Diesel Fuel Update (EIA)

    Table 2. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2005 (Thousand Barrels per Day) Field Production Refinery and Blender Net Production Imports...

  20. Daniel Hoag Named NNSA Production Office Deputy Manager | National...

    National Nuclear Security Administration (NNSA)

    Home Field Offices Welcome to the NNSA Production Office NPO News Releases Daniel Hoag Named NNSA Production Office Deputy Manager Daniel Hoag Named NNSA Production...

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

    Broader source: Energy.gov [DOE]

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

  2. Published New Reservoir Proved Revision Revision New Field Discoveries

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

    Proved Revision Revision New Field Discoveries Estimated Proved Reserves Adjustments Increases Decreases Sales Acquisitions Extensions Discoveries in Old Fields Production Reserves ...

  3. Sinocome Solar aka Perfect Field Investment | Open Energy Information

    Open Energy Info (EERE)

    Solar aka Perfect Field Investment Jump to: navigation, search Name: Sinocome Solar (aka Perfect Field Investment) Place: China Product: Chinese manufacturer of amorphous silicon...

  4. Calyxo USA Solar Fields LLC | Open Energy Information

    Open Energy Info (EERE)

    USA Solar Fields LLC Jump to: navigation, search Name: Calyxo USA (Solar Fields LLC) Place: Perrysburg, Ohio Zip: 43551 Sector: Solar Product: Producer of cadmium telluride...

  5. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    SciTech Connect (OSTI)

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

    1996-01-15

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

  6. 221-U Facility concrete and reinforcing steel evaluations specification for the canyon disposition initiative (CDI)

    SciTech Connect (OSTI)

    Baxter, J.T.

    1998-05-28

    This describes a test program to establish the in-situ material properties of the reinforced concrete in Building 221-U for comparison to the original design specifications. Field sampling and laboratory testing of concrete and reinforcing steel structural materials in Building 221-U for design verification will be undertaken. Forty seven samples are to be taken from radiologically clean exterior walls of the canyon. Laboratory testing program includes unconfined compressive strength of concrete cores, tensile strength of reinforcing steel, and petrographic examinations of concrete cores taken from walls below existing grade.

  7. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

    Office of Environmental Management (EM)

    WIPP Recovery Progress Waste Isolation Pilot Plant Recovery Update J.R. Stroble DOE Carlsbad Field Office Northern New Mexico Citizens Advisory Board March 25, 2015 www.energy.gov/EM 2 Waste Isolation Pilot Plant Quick Facts: * Opened: March 26, 1999 * 11,894 shipments received * 90,983 cubic meters of waste disposed * 171,064 containers disposed in the underground www.energy.gov/EM 3 February 5th Truck Fire: * All operations at the repository ceased following salt haul truck fire in the WIPP

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

    SciTech Connect (OSTI)

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

    2011-06-27

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

  9. EIS-0402: Remediation of Area IV of the Santa Susana Field Laboratory, California

    Broader source: Energy.gov [DOE]

    DOE is preparing an EIS for cleanup of Area IV, including the Energy Technology Engineering Center (ETEC), as well as the Northern Buffer Zone of the Santa Susana Field Laboratory (SSFL) in eastern Ventura County, California, approximately 29 miles north of downtown Los Angeles. (DOE’s operations bordered the Northern Buffer Zone. DOE is responsible for soil cleanup in Area IV and the Northern Buffer Zone.) In the EIS, DOE will evaluate reasonable alternatives for disposition of radiological facilities and support buildings, remediation of contaminated soil and groundwater, and disposal of all resulting waste at permitted facilities.

  10. Report to the Congress on the storage of refined petroleum products and on regional supply interruptions

    SciTech Connect (OSTI)

    Not Available

    1991-06-01

    This report describes petroleum and petroleum products storage and supply disruption. Information is presented under the following topics: Historical Perspective; Current Patterns of Supply and Disposition of Petroleum Products in the Primary Distribution System; PADD I Clean Products Supply/Demand; 1990 Regional Petroleum Reserve Annual Computation; Market Infrastructure and Commercial Practices in the California Motor Gasoline Market, as Related to Potential Refined Petroleum Product Reserve Structures and Sales Procedures; Infrastructure and Commercial Practices in the Northeast Distillate Market, as Related to Potential Refined Petroleum Product Reserve Structures and Sales Procedures; Storage Stability Characteristics of Petroleum Products and Crude Oil; Effect of 1990 Clean Air Act Amendments on Demand for Petroleum Product Storage Capacity; and Environmental Regulations on Tanks.

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  12. Evaluation of Settler Tank Thermal Stability during Solidification and Disposition to ERDF

    SciTech Connect (OSTI)

    Stephenson, David E.; Delegard, Calvin H.; Schmidt, Andrew J.

    2015-03-30

    Ten 16-foot-long and 20-inch diameter horizontal tanks currently reside in a stacked 2×5 (high) array in the ~20,000-gallon water-filled Weasel Pit of the 105-KW Fuel Storage Basin on the US-DOE Hanford Site. These ten tanks are part of the Integrated Water Treatment System used to manage water quality in the KW Basin and are called “settler” tanks because of their application in removing particles from the KW Basin waters. Based on process knowledge, the settler tanks are estimated to contain about 124 kilograms of finely divided uranium metal, 22 kg of uranium dioxide, and another 55 kg of other radioactive sludge. The Sludge Treatment Project (STP), managed by CH2MHill Plateau Remediation Company (CHPRC) is charged with managing the settler tanks and arranging for their ultimate disposal by burial in ERDF. The presence of finely divided uranium metal in the sludge is of concern because of the potential for thermal runaway reaction of the uranium metal with water and the formation of flammable hydrogen gas as a product of the uranium-water reaction. Thermal runaway can be instigated by external heating. The STP commissioned a formal Decision Support Board (DSB) to consider options and provide recommendations to manage and dispose of the settler tanks and their contents. Decision criteria included consideration of the project schedule and longer-term deactivation, decontamination, decommissioning, and demolition (D4) of the KW Basin. The DSB compared the alternatives and recommended in-situ grouting, size-reduction, and ERDF disposal as the best of six candidate options for settler tank treatment and disposal. It is important to note that most grouts contain a complement of Portland cement as the binding agent and that Portland cement curing reactions generate heat. Therefore, concern is raised that the grouting of the settler tank contents may produce heating sufficient to instigate thermal runaway reactions in the contained uranium metal sludge.

  13. Mixed oxide fuels testing in the advanced test reactor to support plutonium disposition

    SciTech Connect (OSTI)

    Ryskamp, J.M.; Sterbentz, J.W.; Chang, G.S.

    1995-09-01

    An intense worldwide effort is now under way to find means of reducing the stockpile of weapons-grade plutonium. One of the most attractive solutions would be to use WGPu as fuel in existing light water reactors (LWRs) in the form of mixed oxide (MOX) fuel - i.e., plutonia (PUO{sub 2}) mixed with urania (UO{sub 2}). Before U.S. reactors could be used for this purpose, their operating licenses would have to be amended. Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the use of MOX fuel. These issues include the following: (1) MOX fuel fabrication process verification, (2) Whether and how to use burnable poisons to depress MOX fuel initial reactivity, which is higher than that of urania, (3) The effects of WGPu isotopic composition, (4) The feasibility of loading MOX fuel with plutonia content up to 7% by weight, (5) The effects of americium and gallium in WGPu, (6) Fission gas release from MOX fuel pellets made from WGPu, (7) Fuel/cladding gap closure, (8) The effects of power cycling and off-normal events on fuel integrity, (9) Development of radial distributions of burnup and fission products, (10) Power spiking near the interfaces of MOX and urania fuel assemblies, and (11) Fuel performance code validation. We have performed calculations to show that the use of hafnium shrouds can produce spectrum adjustments that will bring the flux spectrum in ATR test loops into a good approximation to the spectrum anticipated in a commercial LWR containing MOX fuel while allowing operation of the test fuel assemblies near their optimum values of linear heat generation rate. The ATR would be a nearly ideal test bed for developing data needed to support applications to license LWRs for operation with MOX fuel made from weapons-grade plutonium. The requirements for planning and implementing a test program in the ATR have been identified.

  14. Opportunities for mixed oxide fuel testing in the advanced test reactor to support plutonium disposition

    SciTech Connect (OSTI)

    Terry, W.K.; Ryskamp, J.M.; Sterbentz, J.W.

    1995-08-01

    Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the use of MOX fuel. These issues include the following: (1) MOX fuel fabrication process verification; (2) Whether and how to use burnable poisons to depress MOX fuel initial reactivity, which is higher than that of urania; (3) The effects of WGPu isotopic composition; (4) The feasibility of loading MOX fuel with plutonia content up to 7% by weight; (5) The effects of americium and gallium in WGPu; (6) Fission gas release from MOX fuel pellets made from WGPu; (7) Fuel/cladding gap closure; (8) The effects of power cycling and off-normal events on fuel integrity; (9) Development of radial distributions of burnup and fission products; (10) Power spiking near the interfaces of MOX and urania fuel assemblies; and (11) Fuel performance code validation. The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory possesses many advantages for performing tests to resolve most of the issues identified above. We have performed calculations to show that the use of hafnium shrouds can produce spectrum adjustments that will bring the flux spectrum in ATR test loops into a good approximation to the spectrum anticipated in a commercial LWR containing MOX fuel while allowing operation of the test fuel assemblies near their optimum values of linear heat generation rate. The ATR would be a nearly ideal test bed for developing data needed to support applications to license LWRs for operation with MOX fuel made from weapons-grade plutonium. The requirements for planning and implementing a test program in the ATR have been identified. The facilities at Argonne National Laboratory-West can meet all potential needs for pre- and post-irradiation examination that might arise in a MOX fuel qualification program.

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

    SciTech Connect (OSTI)

    D. K. Morton

    2012-08-01

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

  16. Field O

    Office of Legacy Management (LM)

    -- ! Department of Energy Field O ffice, O s k Ridge P.O . Box 2001 Oak Ridge, Tennessee 37031- 0723 April 20. 1993 Dr. Robert Kulikowskf Director, Bureau of Radiation Control New York City Department of Health 111 Livingston Street Brooklyn, New York 11201 Dear Dr. Kulfkowskf: BAKER AN0 W ILLIAM W AREHOUSES SITE - CORPLETION O F CLEANUP ACTIVITIES The purpose of this notice is to inform you about further scheduled c leanup activities to be conducted by the Department of Energy (WE) at 513-519

  17. Air Products & Chemicals, Inc.

    Office of Energy Efficiency and Renewable Energy (EERE)

    Air Products is partnering with Denbury Green Pipeline – Texas, LLC to capture and sequester one million tons of carbon dioxide per year from two existing steam-methane reformers at Air Products’ hydrogen-production facility in Port Arthur, Texas. The captured CO2 is transported by pipeline to oil fields in eastern Texas for enhanced oil recovery. The total award value of the project is $431 million, with $284 million comprising DOE’s 66 percent share.

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

    SciTech Connect (OSTI)

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

    1996-01-15

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

  19. Geothermal Energy Production with Co-produced and Geopressured...

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

    The American Recovery and Reinvestment Act of 2009 expanded GTP's demonstration work into geopressured fields and geothermal co-production from oil and natural gas fields. GTP ...

  20. Drilling Productivity Report

    Reports and Publications (EIA)

    2016-01-01

    Energy Information Administration’s (EIA) new Drilling Productivity Report (DPR) takes a fresh look at oil and natural gas production, starting with an assessment of how and where drilling for hydrocarbons is taking place. The DPR uses recent data on the total number of drilling rigs in operation along with estimates of drilling productivity and estimated changes in production from existing oil and natural gas wells to provide estimated changes in oil and natural gas production for six key fields. EIA's approach does not distinguish between oil-directed rigs and gas-directed rigs because once a well is completed it may produce both oil and gas; more than half of the wells produce both.

  1. Petroleum Supply Annual

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

    Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 248,959 - - - - 235,269 8,443 10,330 474,643 7,698 0

  2. Petroleum Supply Annual

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

    0.PDF Table 10. PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 573 - - - - 309

  3. Petroleum Supply Annual

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

    1.PDF Table 11. PAD District 5 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 35,538 -

  4. Petroleum Supply Annual

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

    2.PDF Table 12. PAD District 5 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,146 - - - -

  5. Petroleum Supply Annual

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

    .PDF Table 2. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 8,031 - - - - 7,589 272 333 15,311 248 0 Natural Gas Plant

  6. Petroleum Supply Annual

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

    .PDF Table 3. PAD District 1 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,408 - -

  7. Petroleum Supply Annual

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

    TABLE4.PDF Table 4. PAD District 1 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 45 - - - -

  8. Petroleum Supply Annual

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

    TABLE5.PDF Table 5. PAD District 2 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil .............................................................

  9. Petroleum Supply Annual

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

    TABLE6.PDF Table 6. PAD District 2 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,529 - - -

  10. Petroleum Supply Annual

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

    TABLE7.PDF Table 7. PAD District 3 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................

  11. Petroleum Supply Annual

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

    TABLE8.PDF Table 8. PAD District 3 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 4,737 - - -

  12. Petroleum Supply Annual

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

    TABLE9.PDF Table 9. PAD District 4 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil .............................................................

  13. Petroleum Supply Annual 2014, Volume 1

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

    Table 2. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 8,719 - - - - 7,344 222 86 15,848 351 0 Natural Gas Plant Liquids and

  14. Petroleum Supply Annual 2014, Volume 2

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

    .PDF 1. TABLE1.PDF Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 248,959 - - - - 235,269 8,443 10,330

  15. Petroleum Supply Annual 1997, Volume 1

    Gasoline and Diesel Fuel Update (EIA)

    Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 248,959 - - - - 235,269 8,443 10,330 474,643 7,698 0

  16. Petroleum Supply Monthly

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

    January 2016 Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 264,739 - - - - 229,402 -3,032 19,621

  17. Petroleum Supply Monthly

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

    6 January 2016 Table 10. PAD District 2 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  18. Petroleum Supply Monthly

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

    7 January 2016 Table 11. PAD District 2 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,756

  19. Petroleum Supply Monthly

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

    8 January 2016 Table 12. PAD District 2 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  20. Petroleum Supply Monthly

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

    19 January 2016 Table 13. PAD District 3 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  1. Petroleum Supply Monthly

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

    20 January 2016 Table 14. PAD District 3 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  2. Petroleum Supply Monthly

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

    1 January 2016 Table 15. PAD District 3 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 5,567

  3. Petroleum Supply Monthly

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

    2 January 2016 Table 16. PAD District 3 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  4. Petroleum Supply Monthly

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

    3 January 2016 Table 17. PAD District 4 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  5. Petroleum Supply Monthly

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

    4 January 2016 Table 18. PAD District 4 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  6. Petroleum Supply Monthly

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

    5 January 2016 Table 19. PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 686 -

  7. Petroleum Supply Monthly

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

    January 2016 Table 2. U.S. Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 549,322 - - - - 467,312

  8. Petroleum Supply Monthly

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

    6 January 2016 Table 20. PAD District 4 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  9. Petroleum Supply Monthly

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

    7 January 2016 Table 21. PAD District 5 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  10. Petroleum Supply Monthly

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

    8 January 2016 Table 22. PAD District 5 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  11. Petroleum Supply Monthly

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

    29 January 2016 Table 23. PAD District 5 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,074

  12. Petroleum Supply Monthly

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

    30 January 2016 Table 24. PAD District 5 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  13. Petroleum Supply Monthly

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

    January 2016 Table 3. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 9,129 - - - - 7,910 -105 677 15,884 374 0 Natural

  14. Petroleum Supply Monthly

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

    January 2016 Table 4. U.S. Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 9,155 - - - - 7,789 4 639

  15. Petroleum Supply Monthly

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

    January 2016 Table 5. PAD District 1 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................

  16. Petroleum Supply Monthly

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

    January 2016 Table 6. PAD District 1 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  17. Petroleum Supply Monthly

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

    3 January 2016 Table 7. PAD District 1 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 47 - -

  18. Petroleum Supply Monthly

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

    January 2016 Table 8. PAD District 1 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-February 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  19. Petroleum Supply Monthly

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

    5 January 2016 Table 9. PAD District 2 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, February 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  20. untitled

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

    PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 661 - - - - 300 -309 -59 1 581 11 0

  1. untitled

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

    PAD District 5 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 404,548 - - - - 401,772 58,943

  2. untitled

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

    PAD District 5 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,108 - - - - 1,101 161 37 3 2,402 3 0

  3. untitled

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

    U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 8,719 - - - - 7,344 222 86 15,848 351 0 Natural Gas Plant Liquids and Liquefied

  4. untitled

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

    3. PAD District 1 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 19,144 - - - - 218,698

  5. untitled

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

    PAD District 1 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 52 - - - - 599 412 89 13 1,087 52 0

  6. untitled

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

    PAD District 2 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 617,116 - - - - 755,224

  7. untitled

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

    PAD District 2 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,691 - - - - 2,069 -299 156 1 3,523 94

  8. untitled

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

    PAD District 3 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 1,900,521 - - - - 1,195,569

  9. untitled

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

    PAD District 3 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 5,207 - - - - 3,276 34 -2 69 8,255 192

  10. untitled

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

    PAD District 4 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 241,254 - - - - 109,363

  11. Methane Hydrate Field Studies | Department of Energy

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

    Field Studies Methane Hydrate Field Studies Arctic/Alaska North Slope Field Studies Since 2001, DOE has conducted field trials of exploration and production technology in the Alaska North Slope. Although Alaska methane hydrate resources are smaller than marine deposits and currently lack outlets to commercial markets, Alaska provides an excellent laboratory to study E&P technology. The research also has implications for various Alaska resources, including potential gas hydrate resources for

  12. USED FUEL DISPOSITION CAMPAIGN

    Energy Savers [EERE]

    DEVELOPMENT ORGANIZATIONS | Department of Energy USE OF VOLUNTARY CONSENSUS STANDARDS AND INTERACTION WITH STANDARDS DEVELOPMENT ORGANIZATIONS USE OF VOLUNTARY CONSENSUS STANDARDS AND INTERACTION WITH STANDARDS DEVELOPMENT ORGANIZATIONS Purpose This procedure identifies the process by which DOE adopts Voluntary Consensus Standards (VCSs) and provides guidance for the interaction of DOE and contractor employees with Standards Development Organizations (SDOs). PDF icon Use of Voluntary

  13. Facility Disposition Projects

    Office of Environmental Management (EM)

    6 NE Budget Request Presentation FY16 NE Budget Request Presentation PDF icon Office of Nuclear Energy FY16 Budget Request Presentation More Documents & Publications FY17 NE Budget Request Presentation Office of Nuclear Energy Fiscal Year 2014 Budget Request FY 2016 Budget Justification

    7 NE Budget Request Presentation FY17 NE Budget Request Presentation PDF icon FY17 NE Budget Request Presentation More Documents & Publications FY16 NE Budget Request Presentation Office of

  14. Integrated Facilities Disposition Program

    Office of Environmental Management (EM)

    Examples of IFDP legacy materials * RTG inventory - Sr activity - 700,000 Ci Sr-90 RTG - 5' x 5' x 4' * Melton Valley inventory - Size and weight - Concrete vault - 9' x 9' x 9' - ...

  15. Nuclear Material Disposition

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

    2015-12-18

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

  16. Fission Product Yields of {sup 233}U, {sup 235}U, {sup 238}U and {sup 239}Pu in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons

    SciTech Connect (OSTI)

    Laurec, J.; Adam, A.; Bruyne, T. de [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Bauge, E., E-mail: eric.bauge@cea.f [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Granier, T.; Aupiais, J.; Bersillon, O.; Le Petit, G. [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Authier, N.; Casoli, P. [Commissariat a l'Energie Atomique, Centre de Valduc, 21120 Is-sur-Tille (France)

    2010-12-15

    The yields of more than fifteen fission products have been carefully measured using radiochemical techniques, for {sup 235}U(n,f), {sup 239}Pu(n,f) in a thermal spectrum, for {sup 233}U(n,f), {sup 235}U(n,f), and {sup 239}Pu(n,f) reactions in a fission neutron spectrum, and for {sup 233}U(n,f), {sup 235}U(n,f), {sup 238}U(n,f), and {sup 239}Pu(n,f) for 14.7 MeV monoenergetic neutrons. Irradiations were performed at the EL3 reactor, at the Caliban and Prospero critical assemblies, and at the Lancelot electrostatic accelerator in CEA-Valduc. Fissions were counted in thin deposits using fission ionization chambers. The number of fission products of each species were measured by gamma spectrometry of co-located thick deposits.

  17. Internal split field generator

    DOE Patents [OSTI]

    Thundat; Thomas George (Knoxville, TN); Van Neste, Charles W. (Kingston, TN); Vass, Arpad Alexander (Oak Ridge, TN)

    2012-01-03

    A generator includes a coil of conductive material. A stationary magnetic field source applies a stationary magnetic field to the coil. An internal magnetic field source is disposed within a cavity of the coil to apply a moving magnetic field to the coil. The stationary magnetic field interacts with the moving magnetic field to generate an electrical energy in the coil.

  18. U.S. Dry Natural Gas Production (Billion Cubic Feet)

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

    to avoid disclosure of individual company data. Release Date: 12312015 Next Release Date: 01292016 Referring Pages: U.S. Natural Gas Monthly Supply and Disposition Balance...

  19. Hydrogen Production

    SciTech Connect (OSTI)

    2014-09-01

    This 2-page fact sheet provides a brief introduction to hydrogen production technologies. Intended for a non-technical audience, it explains how different resources and processes can be used to produce hydrogen. It includes an overview of research goals as well as “quick facts” about hydrogen energy resources and production technologies.

  20. BLENDING STUDY FOR SRR SALT DISPOSITION INTEGRATION: TANK 50H SCALE-MODELING AND COMPUTER-MODELING FOR BLENDING PUMP DESIGN, PHASE 2

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Fowley, M.

    2011-05-26

    The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where 300,000-800,000 gallons of salt solution will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. Blending requires the miscible salt solutions from potentially multiple source tanks per batch to be well mixed without disturbing settled sludge solids that may be present in a Blend Tank. Disturbing solids may be problematic both from a feed quality perspective as well as from a process safety perspective where hydrogen release from the sludge is a potential flammability concern. To develop the necessary technical basis for the design and operation of blending equipment, Savannah River National Laboratory (SRNL) completed scaled blending and transfer pump tests and computational fluid dynamics (CFD) modeling. A 94 inch diameter pilot-scale blending tank, including tank internals such as the blending pump, transfer pump, removable cooling coils, and center column, were used in this research. The test tank represents a 1/10.85 scaled version of an 85 foot diameter, Type IIIA, nuclear waste tank that may be typical of Blend Tanks used in SDI. Specifically, Tank 50 was selected as the tank to be modeled per the SRR, Project Engineering Manager. SRNL blending tests investigated various fixed position, non-rotating, dual nozzle pump designs, including a blending pump model provided by the blend pump vendor, Curtiss Wright (CW). Primary research goals were to assess blending times and to evaluate incipient sludge disturbance for waste tanks. Incipient sludge disturbance was defined by SRR and SRNL as minor blending of settled sludge from the tank bottom into suspension due to blending pump operation, where the sludge level was shown to remain constant. To experimentally model the sludge layer, a very thin, pourable, sludge simulant was conservatively used for all testing. To experimentally model the liquid, supernate layer above the sludge in waste tanks, two salt solution simulants were used, which provided a bounding range of supernate properties. One solution was water (H{sub 2}O + NaOH), and the other was an inhibited, more viscous salt solution. The research performed and data obtained significantly advances the understanding of fluid mechanics, mixing theory and CFD modeling for nuclear waste tanks by benchmarking CFD results to actual experimental data. This research significantly bridges the gap between previous CFD models and actual field experiences in real waste tanks. A finding of the 2009, DOE, Slurry Retrieval, Pipeline Transport and Plugging, and Mixing Workshop was that CFD models were inadequate to assess blending processes in nuclear waste tanks. One recommendation from that Workshop was that a validation, or bench marking program be performed for CFD modeling versus experiment. This research provided experimental data to validate and correct CFD models as they apply to mixing and blending in nuclear waste tanks. Extensive SDI research was a significant step toward bench marking and applying CFD modeling. This research showed that CFD models not only agreed with experiment, but demonstrated that the large variance in actual experimental data accounts for misunderstood discrepancies between CFD models and experiments. Having documented this finding, SRNL was able to provide correction factors to be used with CFD models to statistically bound full scale CFD results. Through the use of pilot scale tests performed for both types of pumps and available engineering literature, SRNL demonstrated how to effectively apply CFD results to salt batch mixing in full scale waste tanks. In other words, CFD models were in error prior to development of experimental correction factors determined during this research, which provided a technique to use CFD models for salt batch mixing and transfer pump operations. This major scientific advance in mixing technology resulted in multi-million dollar cost savings to SRR. New techniques were developed for both experiment and analysis to complete this research. Supporting this success, research findings are summarized in the Conclusions section of this report, and technical recommendations for design and operation are included in this section of the report.

  1. Isotopes Products

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

    Isotopes Products Isotopes Products Isotopes produced at Los Alamos National Laboratory are saving lives, advancing cutting-edge research and keeping the U.S. safe. Products stress and rest Stress and rest Rb-82 PET images in a patient with dipyridamole stress-inducible lateral wall and apical ischemia. (http://www.fac.org.ar/scvc/llave/image/machac/machaci.htm#f2,3,4) Strontium-82 is supplied to our customers for use in Sr-82/Rb-82 generator technologies. The generators in turn are supplied to

  2. Multifunctional landscapes: Site characterization and field-scale...

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

    Multifunctional landscapes: Site characterization and field-scale design to incorporate biomass production into an agricultural system Title Multifunctional landscapes: Site...

  3. Isotopes Products

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

    are saving lives, advancing cutting-edge research and keeping the U.S. safe. Products stress and rest Stress and rest Rb-82 PET images in a patient with dipyridamole...

  4. Hydrogen Production

    Fuel Cell Technologies Publication and Product Library (EERE)

    This 2-page fact sheet provides a brief introduction to hydrogen production technologies. Intended for a non-technical audience, it explains how different resources and processes can be used to produ

  5. Thermodynamic States in Explosion Fields

    SciTech Connect (OSTI)

    Kuhl, A L

    2009-10-16

    Here we investigate the thermodynamic states occurring in explosion fields from the detonation of condensed explosives in air. In typical applications, the pressure of expanded detonation products gases is modeled by a Jones-Wilkins-Lee (JWL) function: P{sub JWL} = f(v,s{sub CJ}); constants in that function are fit to cylinder test data. This function provides a specification of pressure as a function of specific volume, v, along the expansion isentrope (s = constant = s{sub CJ}) starting at the Chapman-Jouguet (CJ) state. However, the JWL function is not a fundamental equation of thermodynamics, and therefore gives an incomplete specification of states. For example, explosions inherently involve shock reflections from surfaces; this changes the entropy of the products, and in such situations the JWL function provides no information on the products states. In addition, most explosives are not oxygen balanced, so if hot detonation products mix with air, they after-burn, releasing the heat of reaction via a turbulent combustion process. This raises the temperature of explosion products cloud to the adiabatic flame temperature ({approx}3,000K). Again, the JWL function provides no information on the combustion products states.

  6. livermore field office

    National Nuclear Security Administration (NNSA)

    donation to those in need.

    Livermore Field Office sets core values as part of continuous improvement process http:nnsa.energy.govbloglivermore-field-office-sets-cor...

  7. External split field generator

    DOE Patents [OSTI]

    Thundat, Thomas George (Knoxville, TN); Van Neste, Charles W. (Kingston, TN); Vass, Arpad Alexander (Oak Ridge, TN)

    2012-02-21

    A generator includes a coil disposed about a core. A first stationary magnetic field source may be disposed on a first end portion of the core and a second stationary magnetic field source may be disposed on a second end portion of core. The first and second stationary magnetic field sources apply a stationary magnetic field to the coil. An external magnetic field source may be disposed outside the coil to apply a moving magnetic field to the coil. Electrical energy is generated in response to an interaction between the coil, the moving magnetic field, and the stationary magnetic field.

  8. Bottom production

    SciTech Connect (OSTI)

    Baines, J.; Baranov, S.P.; Bartalini, P.; Bay, A.; Bouhova, E.; Cacciari, M.; Caner, A.; Coadou, Y.; Corti, G.; Damet, J.; Dell-Orso, R.; De Mello Neto, J.R.T.; Domenech, J.L.; Drollinger, V.; Eerola, P.; Ellis, N.; Epp, B.; Frixione, S.; Gadomski, S.; Gavrilenko, I.; Gennai, S.; George, S.; Ghete, V.M.; Guy, L.; Hasegawa, Y.; Iengo, P.; Jacholkowska, A.; Jones, R.; Kharchilava, A.; Kneringer, E.; Koppenburg, P.; Korsmo, H.; Kramer, M.; Labanca, N.; Lehto, M.; Maltoni, F.; Mangano, M.L.; Mele, S.; Nairz, A.M.; Nakada, T.; Nikitin, N.; Nisati, A.; Norrbin, E.; Palla, F.; Rizatdinova, F.; Robins, S.; Rousseau, D.; Sanchis-Lozano, M.A.; Shapiro, M.; Sherwood, P.; Smirnova, L.; Smizanska, M.; Starodumov, A.; Stepanov, N.; Vogt, R.

    2000-03-15

    In the context of the LHC experiments, the physics of bottom flavoured hadrons enters in different contexts. It can be used for QCD tests, it affects the possibilities of B decays studies, and it is an important source of background for several processes of interest. The physics of b production at hadron colliders has a rather long story, dating back to its first observation in the UA1 experiment. Subsequently, b production has been studied at the Tevatron. Besides the transverse momentum spectrum of a single b, it has also become possible, in recent time, to study correlations in the production characteristics of the b and the b. At the LHC new opportunities will be offered by the high statistics and the high energy reach. One expects to be able to study the transverse momentum spectrum at higher transverse momenta, and also to exploit the large statistics to perform more accurate studies of correlations.

  9. FRACTIONATING COLUMN PRODUCT COLLECTOR CONTROL

    DOE Patents [OSTI]

    Paxson, G.D. Jr.

    1964-03-10

    Means for detecting minute fluid products from a chemical separation column and for advancing a collector tube rack in order to automatically separate and collect successive fractionated products are described. A charge is imposed on the forming drops at the column orifice to create an electric field as the drop falls in the vicinity of a sensing plate. The field is detected by an electrometer tube coupled to the plate causing an output signal to actuate rotation of a collector turntable rack, thereby positioning new collectors under the orifice. The invention provides reliable automatic collection independent of drop size, rate of fall, or chemical composition. (AEC)

  10. Oil Production

    Energy Science and Technology Software Center (OSTI)

    1989-07-01

    A horizontal and slanted well model was developed and incorporated into BOAST, a black oil simulator, to predict the potential production rates for such wells. The HORIZONTAL/SLANTED WELL MODEL can be used to calculate the productivity index, based on the length and location of the wellbore within the block, for each reservoir grid block penetrated by the horizontal/slanted wellbore. The well model can be run under either pressure or rate constraints in which wellbore pressuresmore » can be calculated as an option of infinite-conductivity. The model can simulate the performance of multiple horizontal/slanted wells in any geometric combination within reservoirs.« less

  11. Product separator

    DOE Patents [OSTI]

    Welsh, Robert A.; Deurbrouck, Albert W.

    1976-01-20

    A secondary light sensitive photoelectric product separator for use with a primary product separator that concentrates a material so that it is visually distinguishable from adjacent materials. The concentrate separation is accomplished first by feeding the material onto a vibratory inclined surface with a liquid flow, such as a wet concentrating table. Vibrations generally perpendicular to the stream direction of flow cause the concentrate to separate from its mixture according to its color. When the concentrate and its surrounding stream reach the recovery end of the table, a detecting device notes the line of color demarcation and triggers a signal if it differs from a normal condition. If no difference is noted nothing moves on the second separator. However, if a difference is detected in the constant monitoring of the color line's location, a product splitter and recovery unit normally positioned near the color line at the recovery end, moves to a new position. In this manner the selected separated concentrate is recovered at a maximum rate regardless of variations in the flow stream or other conditions present.

  12. LANL PDMLink Product Structure Implementation

    SciTech Connect (OSTI)

    Scully, Christopher J.

    2012-08-29

    Over the past 2 and a half years LANL has done both functionality exploration as well as production implementations of PDMLink Product Structure to control the configuration of many of the LANL Design Agency Products. Based on this experience LANL has been recommending for over a year that future product structure implementation in PDMLink do not use the two digit suffix in the number field of enterprise parts (or WTParts). The suffix will be part of one of the attributes for Part Number. Per the TBP's the two digit suffix represents a change in form, fit, or function in a part or a change in the production agency or a number of other conditions. It also denotes backward compatibility with earlier suffixed parts (see TBP 402 section 3.1).

  13. Disposition of Uranium -233 (sup 233U) in Plutonium Metal and Oxide at the Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Freiboth, Cameron J.; Gibbs, Frank E.

    2000-03-01

    This report documents the position that the concentration of Uranium-233 ({sup 233}U) in plutonium metal and oxide currently stored at the DOE Rocky Flats Environmental Technology Site (RFETS) is well below the maximum permissible stabilization, packaging, shipping and storage limits. The {sup 233}U stabilization, packaging and storage limit is 0.5 weight percent (wt%), which is also the shipping limit maximum. These two plutonium products (metal and oxide) are scheduled for processing through the Building 371 Plutonium Stabilization and Packaging System (PuSPS). This justification is supported by written technical reports, personnel interviews, and nuclear material inventories, as compiled in the ''History of Uranium-233 ({sup 233}U) Processing at the Rocky Flats Plant In Support of the RFETS Acceptable Knowledge Program'' RS-090-056, April 1, 1999. Relevant data from this report is summarized for application to the PuSPS metal and oxide processing campaigns.

  14. Nevada Field Office

    National Nuclear Security Administration (NNSA)

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