Sample records for uranium production industry

  1. Uranium industry annual 1996

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    The Uranium Industry Annual 1996 (UIA 1996) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1996 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. Data on uranium raw materials activities for 1987 through 1996 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2006, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. A feature article, The Role of Thorium in Nuclear Energy, is included. 24 figs., 56 tabs.

  2. Uranium Industry Annual, 1992

    SciTech Connect (OSTI)

    Not Available

    1993-10-28T23:59:59.000Z

    The Uranium Industry Annual provides current statistical data on the US uranium industry for the Congress, Federal and State agencies, the uranium and electric utility industries, and the public. The feature article, ``Decommissioning of US Conventional Uranium Production Centers,`` is included. Data on uranium raw materials activities including exploration activities and expenditures, resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities including domestic uranium purchases, commitments by utilities, procurement arrangements, uranium imports under purchase contracts and exports, deliveries to enrichment suppliers, inventories, secondary market activities, utility market requirements, and uranium for sale by domestic suppliers are presented in Chapter 2.

  3. Uranium industry annual 1998

    SciTech Connect (OSTI)

    NONE

    1999-04-22T23:59:59.000Z

    The Uranium Industry Annual 1998 (UIA 1998) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. It contains data for the period 1989 through 2008 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data provides a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Data on uranium raw materials activities for 1989 through 1998, including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment, are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2008, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, and uranium inventories, are shown in Chapter 2. The methodology used in the 1998 survey, including data edit and analysis, is described in Appendix A. The methodologies for estimation of resources and reserves are described in Appendix B. A list of respondents to the ``Uranium Industry Annual Survey`` is provided in Appendix C. The Form EIA-858 ``Uranium Industry Annual Survey`` is shown in Appendix D. For the readers convenience, metric versions of selected tables from Chapters 1 and 2 are presented in Appendix E along with the standard conversion factors used. A glossary of technical terms is at the end of the report. 24 figs., 56 tabs.

  4. Uranium industry annual 1994

    SciTech Connect (OSTI)

    NONE

    1995-07-05T23:59:59.000Z

    The Uranium Industry Annual 1994 (UIA 1994) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing during that survey year. The UIA 1994 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the 10-year period 1985 through 1994 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data collected on the ``Uranium Industry Annual Survey`` (UIAS) provide a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1994, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. A feature article, ``Comparison of Uranium Mill Tailings Reclamation in the United States and Canada,`` is included in the UIA 1994. Data on uranium raw materials activities including exploration activities and expenditures, EIA-estimated resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities, including purchases of uranium and enrichment services, and uranium inventories, enrichment feed deliveries (actual and projected), and unfilled market requirements are shown in Chapter 2.

  5. Uranium industry annual 1995

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    The Uranium Industry Annual 1995 (UIA 1995) provides current statistical data on the U.S. uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1995 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the period 1986 through 2005 as collected on the Form EIA-858, ``Uranium Industry Annual Survey``. Data collected on the ``Uranium Industry Annual Survey`` provide a comprehensive statistical characterization of the industry`s plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1995, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. Data on uranium raw materials activities for 1986 through 1995 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2005, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. The methodology used in the 1995 survey, including data edit and analysis, is described in Appendix A. The methodologies for estimation of resources and reserves are described in Appendix B. A list of respondents to the ``Uranium Industry Annual Survey`` is provided in Appendix C. For the reader`s convenience, metric versions of selected tables from Chapters 1 and 2 are presented in Appendix D along with the standard conversion factors used. A glossary of technical terms is at the end of the report. 14 figs., 56 tabs.

  6. Uranium industry annual 1997

    SciTech Connect (OSTI)

    NONE

    1998-04-01T23:59:59.000Z

    This report provides statistical data on the U.S. uranium industry`s activities relating to uranium raw materials and uranium marketing.

  7. Statistical data of the uranium industry

    SciTech Connect (OSTI)

    none,

    1982-01-01T23:59:59.000Z

    Statistical Data of the Uranium Industry is a compendium of information relating to US uranium reserves and potential resources and to exploration, mining, milling, and other activities of the uranium industry through 1981. The statistics are based primarily on data provided voluntarily by the uranium exploration, mining, and milling companies. The compendium has been published annually since 1968 and reflects the basic programs of the Grand Junction Area Office (GJAO) of the US Department of Energy. The production, reserves, and drilling information is reported in a manner which avoids disclosure of proprietary information.

  8. Uranium 2014 resources, production and demand

    E-Print Network [OSTI]

    Organisation for Economic Cooperation and Development. Paris

    2014-01-01T23:59:59.000Z

    Published every other year, Uranium Resources, Production, and Demand, or the "Red Book" as it is commonly known, is jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency. It is the recognised world reference on uranium and is based on official information received from 43 countries. It presents the results of a thorough review of world uranium supplies and demand and provides a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Long-term projections of nuclear generating capacity and reactor-related uranium requirements are provided as well as a discussion of long-term uranium supply and demand issues. This edition focuses on recent price and production increases that could signal major changes in the industry.

  9. Uranium 2005 resources, production and demand

    E-Print Network [OSTI]

    Organisation for Economic Cooperation and Development. Paris

    2006-01-01T23:59:59.000Z

    Published every other year, Uranium Resources, Production, and Demand, or the "Red Book" as it is commonly known, is jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency. It is the recognised world reference on uranium and is based on official information received from 43 countries. This 21st edition presents the results of a thorough review of world uranium supplies and demand as of 1st January 2005 and provides a statistical profile of the world uranium industry in the areas of exploration, resource estimates, production and reactor-related requirements. It provides substantial new information from all major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2025 are provided as well as a discussion of long-term uranium supply and demand issues. This edition focuses on recent price and production increases that could signal major c...

  10. Uranium 2007 resources, production and demand

    E-Print Network [OSTI]

    Organisation for Economic Cooperation and Development. Paris

    2008-01-01T23:59:59.000Z

    Based on official information received from 40 countries, Uranium 2007 provides a comprehensive review of world uranium supply and demand as of 1st January 2007, as well as data on global uranium exploration, resources, production and reactor-related requirements. It provides substantive new information from major uranium production centres in Africa, Australia, Central Asia, Eastern Europe and North America. Projections of nuclear generating capacity and reactor-related uranium requirements through 2030 are also featured, along with an analysis of long-term uranium supply and demand issues. It finds that with rising demand and declining inventories, uranium prices have increased dramatically in recent years. As a result, the uranium industry is undergoing a significant revival, bringing to an end a period of over 20 years of underinvestment.

  11. Uranium 2009 resources, production and demand

    E-Print Network [OSTI]

    Organisation for Economic Cooperation and Development. Paris

    2010-01-01T23:59:59.000Z

    With several countries currently building nuclear power plants and planning the construction of more to meet long-term increases in electricity demand, uranium resources, production and demand remain topics of notable interest. In response to the projected growth in demand for uranium and declining inventories, the uranium industry – the first critical link in the fuel supply chain for nuclear reactors – is boosting production and developing plans for further increases in the near future. Strong market conditions will, however, be necessary to trigger the investments required to meet projected demand. The "Red Book", jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, is a recognised world reference on uranium. It is based on information compiled in 40 countries, including those that are major producers and consumers of uranium. This 23rd edition provides a comprehensive review of world uranium supply and demand as of 1 January 2009, as well as data on global ur...

  12. 2013 Domestic Uranium Production Report

    E-Print Network [OSTI]

    Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA.S. Energy Information Administration | 2013 Domestic Uranium Production Report iii Preface The U.S. Energy://www.eia.doe.gov/glossary/. #12;U.S. Energy Information Administration | 2013 Domestic Uranium Production Report iv Contents

  13. Process for continuous production of metallic uranium and uranium alloys

    DOE Patents [OSTI]

    Hayden, H.W. Jr.; Horton, J.A.; Elliott, G.R.B.

    1995-06-06T23:59:59.000Z

    A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO{sub 3}), or any other substantially stable uranium oxide, to form the uranium dioxide (UO{sub 2}). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl{sub 4}), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product. The metal chloride formed during the uranium tetrachloride reduction step may then be reduced in an electrolysis cell to recover and recycle the metal back to the uranium tetrachloride reduction operation and the chlorine gas back to the uranium dioxide chlorination operation. 4 figs.

  14. Process for continuous production of metallic uranium and uranium alloys

    DOE Patents [OSTI]

    Hayden, Jr., Howard W. (Oakridge, TN); Horton, James A. (Livermore, CA); Elliott, Guy R. B. (Los Alamos, NM)

    1995-01-01T23:59:59.000Z

    A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO.sub.3), or any other substantially stable uranium oxide, to form the uranium dioxide (UO.sub.2). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl.sub.4), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product. The metal chloride formed during the uranium tetrachloride reduction step may then be reduced in an electrolysis cell to recover and recycle the metal back to the uranium tetrachloride reduction operation and the chlorine gas back to the uranium dioxide chlorination operation.

  15. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium Production

  16. Uranium 2011 resources, production and demand

    E-Print Network [OSTI]

    Organisation for Economic Cooperation and Development. Paris

    2012-01-01T23:59:59.000Z

    In the wake of the Fukushima Daiichi nuclear power plant accident, questions are being raised about the future of the uranium market, including as regards the number of reactors expected to be built in the coming years, the amount of uranium required to meet forward demand, the adequacy of identified uranium resources to meet that demand and the ability of the sector to meet reactor requirements in a challenging investment climate. This 24th edition of the “Red Book”, a recognised world reference on uranium jointly prepared by the OECD Nuclear Energy Agency and the International Atomic Energy Agency, provides analyses and information from 42 producing and consuming countries in order to address these and other questions. It offers a comprehensive review of world uranium supply and demand as well as data on global uranium exploration, resources, production and reactor-related requirements. It also provides substantive new information on established uranium production centres around the world and in countri...

  17. Decommissioning of U.S. uranium production facilities

    SciTech Connect (OSTI)

    Not Available

    1995-02-01T23:59:59.000Z

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

  18. EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth...

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

    60: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site Summary This...

  19. The Soviet uranium industry and exports of nuclear materials and services

    SciTech Connect (OSTI)

    Sagers, M.J.

    1990-08-01T23:59:59.000Z

    The USSR has been offering Western countries, through long-term contracts, services in the processing and enrichment of uranium for their nuclear power industries since 1973. Although known for some time from Western sources, this was confirmed by Boris Semyenov, First Deputy Chairman of the USSR State Committee for the Utilization of Atomic Energy, in 1989. Other sources state that the first service contract was signed in 1971, with initial deliveries beginning in 1973, and that altogether, there are now about 10-12 long-term contracts with firms in various Western European countries that extend to the year 2000 or in some cases to 2010. Although these services are said to remain the mainstay of business with the capitalist countries of the West, the export of enriched uranium materials produced from domestic ore began in 1988. Clients include firms in both the US and Western Europe. Evidently, the severe balance-of-payments problems in Soviet foreign trade operations in recent years have led the Soviets to push alternatives to oil exports as much as possible, notably metals and minerals and chemicals and fertilizers, and this has now extended to the Soviet uranium industry. The paper discusses the USSR uranium industry, uranium mining, uranium enrichment, and plutonium production.

  20. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium

  1. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium9 2014

  2. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium9

  3. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium911 2014

  4. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium911

  5. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium9117 2014

  6. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium9117 20145

  7. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic Uranium9117

  8. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomesticDomestic Uranium

  9. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97.10. Uranium

  10. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97.10. Uranium9.

  11. Uranium Mining, Conversion, and Enrichment Industries

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

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

  12. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and1. Total production

  13. Proceedings of Workshop on Uranium Production Environmental Restoration: An exchange between the United States and Germany

    SciTech Connect (OSTI)

    Not Available

    1993-12-31T23:59:59.000Z

    Scientists, engineers, elected officials, and industry regulators from the United, States and Germany met in Albuquerque, New Mexico, August 16--20, 1993, in the first joint international workshop to discuss uranium tailings remediation. Entitled ``Workshop on Uranium Production Environmental Restoration: An Exchange between the US and Germany,`` the meeting was hosted by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The goal of the workshop was to further understanding and communication on the uranium tailings cleanup projects in the US and Germany. Many communities around the world are faced with an environmental legacy -- enormous quantities of hazardous and low-level radioactive materials from the production of uranium used for energy and nuclear weapons. In 1978, the US Congress passed the Uranium Mill Tailings Radiation Control Act. Title I of the law established a program to assess the tailings at inactive uranium processing sites and provide a means for joint federal and state funding of the cleanup efforts at sites where all or substantially all of the uranium was produced for sale to a federal agency. The UMTRA Project is responsible for the cleanup of 24 sites in 10 states. Germany is facing nearly identical uranium cleanup problems and has established a cleanup project. At the workshop, participants had an opportunity to interact with a broad cross section of the environmental restoration and waste disposal community, discuss common concerns and problems, and develop a broader understanding of the issues. Abstracts are catalogued individually for the data base.

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

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

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

  15. Creating Value Wood Products Industry

    E-Print Network [OSTI]

    Louisiana Forest Products Development Center #12;2 Louisiana is blessed with quality timberland for the Wood Products Industry The forest industry contributes more than 50 percent of the total value of all for quality information, research and education in forest products in Louisiana, recognized regionally

  16. 1.0 MAJOR STUDIES SUPPORTING THIS SCOPING RISK The most important period of past U.S. uranium production spanned from approximately 1948

    E-Print Network [OSTI]

    plants (U.S. DOE/EIA 2003a, 2003b, 2006). Uranium exploration, mining, and ore processing left a legacy.S. uranium production spanned from approximately 1948 to the early 1980s (U.S. DOE/EIA 1992). Through 2005 the industry had generated over 420,000 metric tons (MTs) of uranium for nuclear weapons and commercial power

  17. CHAPTER 6. BIBLIOGRAPHY AAPG 2005--American Association of Petroleum Geologists. Recent Uranium Industry Developments,

    E-Print Network [OSTI]

    Industry Developments, Exploration, Mining and Environmental Programs in the U.S. and Overseas. Uranium6-1 CHAPTER 6. BIBLIOGRAPHY AAPG 2005--American Association of Petroleum Geologists. Recent Uranium Committee, Energy Minerals Division. Tulsa, OK: March 25, 2005. http://emd.aapg.org/technical areas/uranium

  18. Reclamation and groundwater restoration in the uranium milling industry: An assessment of UMTRCA, title II

    SciTech Connect (OSTI)

    Collins, J.D.

    1996-12-31T23:59:59.000Z

    In 1978, Congress passed the Uranium Mill Tailings Radiation Control Act (UMTRCA) to regulate the disposal and reclamation of uranium mill tailings.This article examines the implementation of this legislation through eight cases of uranium mills in New Mexico, Wyoming, and Utah now being reclaimed. The eight cases examined here make up an important part of the total reclamation picture in the uranium milling industry.

  19. An Overview of Process Monitoring Related to the Production of Uranium Ore Concentrate

    SciTech Connect (OSTI)

    McGinnis, Brent [Innovative Solutions Unlimited, LLC

    2014-04-01T23:59:59.000Z

    Uranium ore concentrate (UOC) in various chemical forms, is a high-value commodity in the commercial nuclear market, is a potential target for illicit acquisition, by both State and non-State actors. With the global expansion of uranium production capacity, control of UOC is emerging as a potentially weak link in the nuclear supply chain. Its protection, control and management thus pose a key challenge for the international community, including States, regulatory authorities and industry. This report evaluates current process monitoring practice and makes recommendations for utilization of existing or new techniques for managing the inventory and tracking this material.

  20. Agricultural productivity and industrialization: A reformulation

    E-Print Network [OSTI]

    Bandyopadhyay, Antar

    Agricultural productivity and industrialization: A reformulation Debasis Mondal Sept 20, 2014 Abstract In this paper we examine the role of agricultural productivity on the process of industrialization industrialization by releasing labor from agriculture to industry. In fact, when agriculture is highly productive

  1. Method for the production of uranium chloride salt

    DOE Patents [OSTI]

    Westphal, Brian R.; Mariani, Robert D.

    2013-07-02T23:59:59.000Z

    A method for the production of UCl.sub.3 salt without the use of hazardous chemicals or multiple apparatuses for synthesis and purification is provided. Uranium metal is combined in a reaction vessel with a metal chloride and a eutectic salt- and heated to a first temperature under vacuum conditions to promote reaction of the uranium metal with the metal chloride for the production of a UCl.sub.3 salt. After the reaction has run substantially to completion, the furnace is heated to a second temperature under vacuum conditions. The second temperature is sufficiently high to selectively vaporize the chloride salts and distill them into a condenser region.

  2. Hierarchical production scheduling in the process industry

    E-Print Network [OSTI]

    Hierarchical production scheduling in the process industry Anna Lindholm Nils-Petter Nytz are handled. The activities are are denoted production scheduling (PS) and detailed production scheduling (DPS. The focus is on production scheduling for chemical process industries with continuous production

  3. FINLAND SOURCES 2007 -Forest industry production Authorities

    E-Print Network [OSTI]

    FINLAND SOURCES 2007 - Forest industry production Print Home Finland Government Authorities Local » Turnover » Profit » Energy Year 2006 » Shipping Business services Infrastructure Economy Education strategy of the EU's Forest-Based Industries Technology Platform provides a good basis for preparing

  4. Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications 

    E-Print Network [OSTI]

    Garnetti, David J.

    2010-07-14T23:59:59.000Z

    The research in this thesis covers the design and implementation of a depleted uranium (DU) powder production system and the initial results of a DU-Zr-Mg alloy alpha phase sintering experiment where the Mg is a surrogate ...

  5. Colorado Statewide Forest Products Industry Profile

    E-Print Network [OSTI]

    Colorado Statewide Forest Products Industry Profile Economic Sustainability and Ecological and Comparisons · Production and Processing · Sales and Markets · Economic and Ecological Contributions Sawmills · 1/4 for Roundwood (post and pole, vigas, house logs), furniture, excelsior etc. ­ Sawmill

  6. Method for making a uranium chloride salt product

    DOE Patents [OSTI]

    Miller, William E. (Naperville, IL); Tomczuk, Zygmunt (Lockport, IL)

    2004-10-05T23:59:59.000Z

    The subject apparatus provides a means to produce UCl.sub.3 in large quantities without incurring corrosion of the containment vessel or associated apparatus. Gaseous Cl is injected into a lower layer of Cd where CdCl.sub.2 is formed. Due to is lower density, the CdCl.sub.2 rises through the Cd layer into a layer of molten LiCl--KCL salt where a rotatable basket containing uranium ingots is suspended. The CdCl.sub.2 reacts with the uranium to form UCl.sub.3 and Cd. Due to density differences, the Cd sinks down to the liquid Cd layer and is reused. The UCl.sub.3 combines with the molten salt. During production the temperature is maintained at about 600.degree. C. while after the uranium has been depleted the salt temperature is lowered, the molten salt is pressure siphoned from the vessel, and the salt product LiCl--KCl-30 mol % UCl.sub.3 is solidified.

  7. 1st Quarter 2015 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. Total production of uranium

  8. 1st Quarter 2015 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. Total production of uranium2.

  9. 1st Quarter 2015 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. Total production of uranium2.3.

  10. 1st Quarter 2015 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. Total production of uranium2.3.4.

  11. Uranium production in Eastern Europe and its environmental impact: A literature survey

    SciTech Connect (OSTI)

    Norman, R.E.

    1993-04-01T23:59:59.000Z

    A survey of the unclassified literature was made to determine the location, technology, throughput, and environmental status of the uranium mines and mills that have historically made up uranium production capability in Eastern Europe. Included in that survey were the following countries: the former German Democratic Republic (GDR), now part of a reunited Germany, Czechoslovakia, Romania, Bulgaria, Hungary, and Poland. Until recently, uranium was being produced in five of these six countries (Poland stopped production 20 years ago). The production began directly after World War II in support of weapons production in the Soviet Union. Eastern Europe has produced about two-thirds of the total Soviet uranium inventory historically, or about 330,000 metric tonnes of uranium (NM) [730 million pounds of uranium (MlbU)l out of a total of about 490,000 MTU (1090 NlbU).

  12. Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel

    DOE Patents [OSTI]

    Herrmann, Steven Douglas

    2014-05-27T23:59:59.000Z

    Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the used fuel. The remaining radioactivity from the noble metal fission products in the detoxified fuel is primarily limited to soft beta emitters. The extracted transuranic and reactive fission products are amenable to existing technologies for group uranium/transuranic product recovery and fission product immobilization in engineered waste forms.

  13. A Blueprint for Forest Products Industry

    E-Print Network [OSTI]

    Major Model Components - Resource Assessment - Industry Structure - Product/Market Strategy - Economic Impacts Workforce Training Network Formation Resource Assessment Government Support Financing Economic Development Technology Profitability Resource Assessment Current & projected Commercial species Lesser-used species

  14. Industrial and Agricultural Production Efficiency Program

    Broader source: Energy.gov [DOE]

    Energy Trust of Oregon offers the Industrial and Agricultural Production Efficiency Program to customers of Portland General Electric, Pacific Power, NW Natural and Cascade Natural Gas. In order to...

  15. High grade uranium resources in the United States : an overview

    E-Print Network [OSTI]

    Graves, Richard E.

    1974-01-01T23:59:59.000Z

    A time analysis of uranium exploration, production and known reserves in the United States is employed to reveal industry trends. The

  16. TrendSetter Solar Products Inc aka Trendsetter Industries formerly...

    Open Energy Info (EERE)

    TrendSetter Solar Products Inc aka Trendsetter Industries formerly Six River Solar Jump to: navigation, search Name: TrendSetter Solar Products Inc (aka Trendsetter Industries,...

  17. Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications

    E-Print Network [OSTI]

    Garnetti, David J.

    2010-07-14T23:59:59.000Z

    The research in this thesis covers the design and implementation of a depleted uranium (DU) powder production system and the initial results of a DU-Zr-Mg alloy alpha phase sintering experiment where the Mg is a surrogate for Pu and Am. The powder...

  18. Forest Products Industry of the Future

    SciTech Connect (OSTI)

    Los Alamos Technical Associates, Inc

    2002-05-01T23:59:59.000Z

    Los Alamos Technical Associates, Inc (LATA) conducted an evaluation of the potential impact and value of a portion of the current portfolio of r&d projects supported by the Office of Industrial Technology and the Forest Products Industry of the Future. The mission of the evaluation was to (a) assess the potential impact of the projects to meet the critical goals of the industry as identified in the vision and roadmapping documents. (b) Evaluate the relationship between the current portfolio of projects and the Agenda 202 Implementation Plan. In addition, evaluate the relationship between the portfolio and the newly revised draft technology strategy being created by the industry. (c) Identify areas where current efforts are making significant progress towards meeting industry goals and identify areas where additional work my be required to meet these goals. (d) Make recommendations to the DOE and the Forest Products Industry on possible improvements in the portfolio and in the current methodology that DOE uses to assess potential impacts on its R&D activities.

  19. U.S. uranium production industry employment, 1993-2011

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Department Home >Area:DepartmentSecurity

  20. The uranium industry in the former eastern block countries-present status and new challenges associated with remediation work

    SciTech Connect (OSTI)

    Vels, B.Dr.; Ruhrmann, G.Dr. [Uranerzbergbau-GmbH, Wesseling (Germany)

    1994-12-31T23:59:59.000Z

    The main uranium producing countries and the individual production centres are briefly described, including their production status. In particular, an analysis of their present situation is given. The challenge of required remediation work lies in the successful handling of the complex transformation from the old to the new socio-economic environment within a tight financial framework.

  1. Continuing investigations for technology assessment of /sup 99/Mo production from LEU (low enriched Uranium) targets

    SciTech Connect (OSTI)

    Vandergrift, G.F.; Kwok, J.D.; Marshall, S.L.; Vissers, D.R.; Matos, J.E.

    1987-01-01T23:59:59.000Z

    Currently much of the world's supply of /sup 99m/Tc for medical purposes is produced from /sup 99/Mo derived from the fissioning of high enriched uranium (HEU). The need for /sup 99m/Tc is continuing to grow, especially in developing countries, where needs and national priorities call for internal production of /sup 99/Mo. This paper presents the results of our continuing studies on the effects of substituting low enriched Uranium (LEU) for HEU in targets for the production of fission product /sup 99/Mo. Improvements in the electrodeposition of thin films of uranium metal are reported. These improvements continue to increase the appeal for the substitution of LEU metal for HEU oxide films in cylindrical targets. The process is effective for targets fabricated from stainless steel or hastaloy. A cost estimate for setting up the necessary equipment to electrodeposit uranium metal on cylindrical targets is reported. Further investigations on the effect of LEU substitution on processing of these targets are also reported. Substitution of uranium silicides for the uranium-aluminum alloy or uranium aluminide dispersed fuel used in other current target designs will allow the substitution of LEU for HEU in these targets with equivalent /sup 99/Mo-yield per target and no change in target geometries. However, this substitution will require modifications in current processing steps due to (1) the insolubility of uranium silicides in alkaline solutions and (2) the presence of significant quantities of silicate in solution. Results to date suggest that both concerns can be handled and that substitution of LEU for HEU can be achieved.

  2. Safeguards by design - industry engagement for new uranium enrichment facilities in the United States

    SciTech Connect (OSTI)

    Demuth, Scott F [Los Alamos National Laboratory; Grice, Thomas [NRC; Lockwood, Dunbar [DOE/NA-243

    2010-01-01T23:59:59.000Z

    The United States Department of Energy's (DOE's) Office of Nonproliferation and International Security (NA-24) has initiated a Safeguards by Design (SBD) effort to encourage the incorporation of international (IAEA) safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign or retrofit the facility at a later date. The main goals of Safeguards by Design are to (1) make the implementation of international safeguards at new civil nuclear facilities more effective and efficient, (2) avoid costly and time-consuming re-design work or retrofits at such facilities and (3) design such facilities in a way that makes proliferation as technically difficult, as time-consuming, and as detectable as possible. The U.S. Nuclear Regulatory Commission (NRC) has recently hosted efforts to facilitate the use of Safeguards by Design for new uranium enrichment facilities currently being planned for construction in the U.S. While SBD is not a NRC requirement, the NRC is aiding the implementation of SBD by coordinating discussions between DOE's NA-24 and industry's facility design teams. More specifically, during their normal course of licensing discussions the NRC has offered industry the opportunity to engage with NA-24 regarding SBD.

  3. Chemical production from industrial by-product gases: Final report

    SciTech Connect (OSTI)

    Lyke, S.E.; Moore, R.H.

    1981-04-01T23:59:59.000Z

    The potential for conservation of natural gas is studied and the technical and economic feasibility and the implementation of ventures to produce such chemicals using carbon monoxide and hydrogen from byproduct gases are determined. A survey was performed of potential chemical products and byproduct gas sources. Byproduct gases from the elemental phosphorus and the iron and steel industries were selected for detailed study. Gas sampling, preliminary design, market surveys, and economic analyses were performed for specific sources in the selected industries. The study showed that production of methanol or ammonia from byproduct gas at the sites studied in the elemental phosphorus and the iron and steel industries is technically feasible but not economically viable under current conditions. Several other applications are identified as having the potential for better economics. The survey performed identified a need for an improved method of recovering carbon monoxide from dilute gases. A modest experimental program was directed toward the development of a permselective membrane to fulfill that need. A practical membrane was not developed but further investigation along the same lines is recommended. (MCW)

  4. S. 2415: Title I may be cited as the Uranium Enrichment Act of 1990; Title II may be cited as the Uranium Security and Tailings Reclamation Act of 1989; and Title III may be cited as The Solar, Wind, Waste, and Geothermal Power Production Incentives Act of 1990, introduced in the Senate, One Hundred First Congress, Second Session, April 4, 1990

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    S. 2415 (which started out as a bill to encourage solar and geothermal power generation) now would amend the Atomic Energy Act of 1954 to redirect uranium enrichment enterprises to further the national interest, respond to competitive market forces, and to ensure the nation's common defense and security. It would establish a United States Enrichment Corporation for the following purposes: to acquire feed materials, enriched uranium, and enrichment facilities; to operate these facilities; to market enriched uranium for governmental purposes and qualified domestic and foreign persons; to conduct research into uranium enrichment; and to operate as a profitable, self-financing, reliable corporation and in a manner consistent with the health and safety of the public. The bill describes powers and duties of the corporation; the organization, finance, and management; decontamination and decommissioning. The second part of the bill would ensure an adequate supply of domestic uranium for defense and power production; provide assistance to the domestic uranium industry; and establish, facilitate, and expedite a comprehensive system for financing reclamation and remedial action at active uranium and thorium processing sites. The third part of the bill would remove the size limitations on power production facilities now part of the Public Utility Regulatory Policies Act of 1978. Solar, wind, waste, or geothermal power facilities would no longer have to be less than 80 MW to qualify as a small power production facility.

  5. Supply chain network optimization : low volume industrial chemical product

    E-Print Network [OSTI]

    Dacha, Fred (Frederick Omondi)

    2013-01-01T23:59:59.000Z

    The chemical industry is a highly competitive and low margin industry. Chemical transportation faces stringent safety regulations meaning that Cost-To-Serve (C2S), costs associated with products net flow from manufacturers ...

  6. Uranium concentrate production in the United States, 2004-13

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrinceton PlasmaAfternoon4. Uranium purchased by...Recovery

  7. Industry

    E-Print Network [OSTI]

    Bernstein, Lenny

    2008-01-01T23:59:59.000Z

    oil, starch and corn refining, since these can be a source of fuel products. The sugar cane industry

  8. Rehabilitation of contaminated territories while liquidating enterprises of uranium mining industry of the CIS

    SciTech Connect (OSTI)

    Karamushka, V.P.; Ostroborodov, V.V. [VNIPIPROMTECHNOLOGII, Moscow (Russian Federation)

    1993-12-31T23:59:59.000Z

    Uranium mining in the Russian Federation has caused contamination of the environment with solid, liquid and gaseous wastes. Radioactive materials are being leached from residual uranium ores and mill tailings piles. These contaminated areas are being decontaminated and recultivated. Ensuring radiation safety in remediating is of prime importance.

  9. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31T23:59:59.000Z

    The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

  10. Training Needs in Louisiana's Value-Added Forest Products Industry

    E-Print Network [OSTI]

    Training Needs in Louisiana's Value-Added Forest Products Industry Richard VloskyRichard Vlosky-Added Training in Other States · The Need for Training in Louisiana-Past Research #12;Industry Development & Adding Value #12;Value-Added Industry Development is Multi-Faceted Marketing Workforce Training Strategic

  11. Variety and industrial production : the case of housing

    E-Print Network [OSTI]

    Chimits-Cazaux, Catherine

    1984-01-01T23:59:59.000Z

    Industrial processes have addressed with various degrees of success the question of housing production. If assembly-line methods have proven their efficiency in the production and distribution of low-cost housing, they ...

  12. Scope for industrial applications of production scheduling models and

    E-Print Network [OSTI]

    Grossmann, Ignacio E.

    ERP Level 4 MES / CPM Production & Control Level 3 Control systems/sensors (DCS, PLC, SCADA, BMS management, planning, scheduling, quality control, recipe management, setpoint definition, integrationScope for industrial applications of production scheduling models and solution methods Iiro

  13. Uranium deposits of Brazil

    SciTech Connect (OSTI)

    NONE

    1991-09-01T23:59:59.000Z

    Brazil is a country of vast natural resources, including numerous uranium deposits. In support of the country`s nuclear power program, Brazil has developed the most active uranium industry in South America. Brazil has one operating reactor (Angra 1, a 626-MWe PWR), and two under construction. The country`s economic challenges have slowed the progress of its nuclear program. At present, the Pocos de Caldas district is the only active uranium production. In 1990, the Cercado open-pit mine produced approximately 45 metric tons (MT) U{sub 3}O{sub 8} (100 thousand pounds). Brazil`s state-owned uranium production and processing company, Uranio do Brasil, announced it has decided to begin shifting its production from the high-cost and nearly depleted deposits at Pocos de Caldas, to lower-cost reserves at Lagoa Real. Production at Lagoa Real is schedules to begin by 1993. In addition to these two districts, Brazil has many other known uranium deposits, and as a whole, it is estimated that Brazil has over 275,000 MT U{sub 3}O{sub 8} (600 million pounds U{sub 3}O{sub 8}) in reserves.

  14. Global product development in semiconductor industry : Intel -- Tick-Tock product development cadence

    E-Print Network [OSTI]

    Park, Cheolmin, S.M. Massachusetts Institute of Technology

    2008-01-01T23:59:59.000Z

    This thesis investigates on changes in semiconductor industry's product development methodology by following Intel's product development from year 2000. Intel was challenged by customer's preference change, competitors new ...

  15. Dupoly process for treatment of depleted uranium and production of beneficial end products

    DOE Patents [OSTI]

    Kalb, Paul D. (Wading River, NY); Adams, Jay W. (Stony Brook, NY); Lageraaen, Paul R. (Seaford, NY); Cooley, Carl R. (Gaithersburg, MD)

    2000-02-29T23:59:59.000Z

    The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

  16. EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site

    Broader source: Energy.gov [DOE]

    This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three alternative locations within the Paducah site; transportation of all cylinders (DUF6, enriched, and empty) currently stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Portsmouth; construction of a new cylinder storage yard at Portsmouth (if required) for ETTP cylinders; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride (HF) produced as a conversion coproduct; and neutralization of HF to calcium fluoride and its sale or disposal in the event that the HF product is not sold.

  17. Industrialization and manufacturing steps within the Global Product Lifecycle context

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    steps within the Product Life cycle Management (PLM) context. Initially, PLM was focused almost. In the same time, the industrialization and the production are not sufficiently integrated into the PLM solutions. Currently, there is much to be gained by extending the coverage of PLM to production step

  18. DEPARTMENT OF ENERGY Excess Uranium Management: Effects of DOE...

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

    Excess Uranium Management: Effects of DOE Transfers of Excess Uranium on Domestic Uranium Mining, Conversion, and Enrichment Industries; Request for Information AGENCY: Office of...

  19. Recent International R&D Activities in the Extraction of Uranium from Seawater

    E-Print Network [OSTI]

    Rao, Linfeng

    2011-01-01T23:59:59.000Z

    Uranium and Rare Earth Elements Using Biomass of Algae, Bioinorganic ChemistryRecovery of uranium from sea water. Chemistry & Industry (uranium recovery from seawater. Industrial & Engineering Chemistry

  20. An Overview of the Louisiana Primary Solid Wood Products Industry

    E-Print Network [OSTI]

    goal of this second study is to profile the primary solid wood products industry. In addition (including pulp and paper) and secondary manufacturing establishments (Jacob et al. 1987). The forest

  1. Microorganisms In Industry And Environment From Scientific and Industrial Research to Consumer Products

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Products Proceedings of the III International Conference on Environmental, Industrial and Applied and Bioinformatics Unit, Medical Biotechnology Department, Biotechnology Research Center, Pasteur Institute of Iran Biotechnology Department, Biotechnology Research Center, Pasteur Institute of Iran, #69 Pasteur Ave., Tehran

  2. Productivity benefits of industrial energy efficiency measures

    E-Print Network [OSTI]

    Worrell, Ernst

    2011-01-01T23:59:59.000Z

    linkage between energy efficiency and productivity. Energyand increased energy efficiency in integrated paper andand Office of Energy Efficiency and Renewable Energy, 1997.

  3. Productivity benefits of industrial energy efficiency measures

    E-Print Network [OSTI]

    Worrell, Ernst

    2011-01-01T23:59:59.000Z

    the linkage between energy efficiency and productivity.and increased energy efficiency in integrated paper andand Office of Energy Efficiency and Renewable Energy, 1997.

  4. Productivity benefits of industrial energy efficiency measures

    E-Print Network [OSTI]

    Worrell, Ernst

    2011-01-01T23:59:59.000Z

    facility reliability Reduced wear and tear on equipment/equipment performance Shorter process cycle times Improved product quality/purity Increased reliability

  5. Production design for plate products in the steel industry

    E-Print Network [OSTI]

    We describe an optimization tool for a multistage production process for ... plates. The problem we solve yields a production design (or plan) for rectangular plate.

  6. Industrialization and manufacturing steps within the Global Product Lifecycle context

    E-Print Network [OSTI]

    Boyer, Edmond

    steps within the Product Life cycle Management (PLM) context. Initially, PLM was focused almost. In the same time, the industrialization and the manufacturing are not sufficiently integrated into the PLM solutions. Actually, there is much to be gained by extending the coverage of PLM to production stage

  7. Production design for plate products in the steel industry

    E-Print Network [OSTI]

    Sanjeeb Dash

    2007-04-05T23:59:59.000Z

    Apr 5, 2007 ... Abstract: We describe an optimization tool for a multistage production process for rectangular steel plates. The problem we solve yields a ...

  8. Occupational exposures to uranium: processes, hazards, and regulations

    SciTech Connect (OSTI)

    Stoetzel, G.A.; Fisher, D.R.; McCormack, W.D.; Hoenes, G.R.; Marks, S.; Moore, R.H.; Quilici, D.G.; Breitenstein, B.D.

    1981-04-01T23:59:59.000Z

    The United States Uranium Registry (USUR) was formed in 1978 to investigate potential hazards from occupational exposure to uranium and to assess the need for special health-related studies of uranium workers. This report provides a summary of Registry work done to date. The history of the uranium industry is outlined first, and the current commercial uranium industry (mining, milling, conversion, enrichment, and fuel fabrication) is described. This description includes information on basic processes and areas of greatest potential radiological exposure. In addition, inactive commercial facilities and other uranium operations are discussed. Regulation of the commercial production industry for uranium fuel is reported, including the historic development of regulations and the current regulatory agencies and procedures for each phase of the industry. A review of radiological health practices in the industry - facility monitoring, exposure control, exposure evaluation, and record-keeping - is presented. A discussion of the nonradiological hazards of the industry is provided, and the final section describes the tissue program developed as part of the Registry.

  9. Industry

    E-Print Network [OSTI]

    Bernstein, Lenny

    2008-01-01T23:59:59.000Z

    iron and steel production. IEA Greenhouse Gas R&D Programme,tempera- ture range. IEA/Caddet, Sittard, The Netherlands.industry. Cheltenham, UK, IEA Greenhouse Gas R&D Programme,

  10. Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity

    ScienceCinema (OSTI)

    Selldorff, John; Atwell, Monte

    2014-12-03T23:59:59.000Z

    Industrial efficiency and low-cost energy resources are key components to increasing U.S. energy productivity and makes the U.S. manufacturing sector more competitive. Companies find a competitive advantage in implementing efficiency technologies and practices, and technologies developed and manufactured in the U.S. enable greater competitiveness economy-wide.

  11. Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity

    SciTech Connect (OSTI)

    Selldorff, John; Atwell, Monte

    2014-09-23T23:59:59.000Z

    Industrial efficiency and low-cost energy resources are key components to increasing U.S. energy productivity and makes the U.S. manufacturing sector more competitive. Companies find a competitive advantage in implementing efficiency technologies and practices, and technologies developed and manufactured in the U.S. enable greater competitiveness economy-wide.

  12. CALENDAR YEAR 2012 SCHEDULE Workshops to Improve Industrial Productivity by

    E-Print Network [OSTI]

    compressor control types. Learn how to achieve cost savings through more effective production and use determine system efficiency, identify degraded fans, collect data for trending system operation://www.eere.energy.gov/industry/bestpractices/fan_systems.html Motor Systems Management Motor Systems Management training is designed to help facility personnel reduce

  13. Method for converting uranium oxides to uranium metal

    DOE Patents [OSTI]

    Duerksen, Walter K. (Norris, TN)

    1988-01-01T23:59:59.000Z

    A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixture is then cooled to a temperature less than -100.degree. C. in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

  14. India's pulp and paper industry: Productivity and energy efficiency

    SciTech Connect (OSTI)

    Schumacher, Katja

    1999-07-01T23:59:59.000Z

    Historical estimates of productivity growth in India's pulp and paper sector vary from indicating an improvement to a decline in the sector's productivity. The variance may be traced to the time period of study, source of data for analysis, and type of indices and econometric specifications used for reporting productivity growth. The authors derive both statistical and econometric estimates of productivity growth for this sector. Their results show that productivity declined over the observed period from 1973-74 to 1993-94 by 1.1% p.a. Using a translog specification the econometric analysis reveals that technical progress in India's pulp and paper sector has been biased towards the use of energy and material, while it has been capital and labor saving. The decline in productivity was caused largely by the protection afforded by high tariffs on imported paper products and other policies, which allowed inefficient, small plants to enter the market and flourish. Will these trends continue into the future, particularly where energy use is concerned? The authors examine the current changes in structure and energy efficiency undergoing in the sector. Their analysis shows that with liberalization of the sector, and tighter environmental controls, the industry is moving towards higher efficiency and productivity. However, the analysis also shows that because these improvements are being hampered by significant financial and other barriers the industry might have a long way to go.

  15. Determination of Young's modulus, shear modulus and mechanical damping as a function of temperature and microstructure for Uranium-2wt% Molybdenum using the PUCOT

    E-Print Network [OSTI]

    Varughese, Joseph Verghese

    1988-01-01T23:59:59.000Z

    Verghese Varughese, B. S. , Texas A&M University Chairman of Advisory Committee: Dr. Alan Wolfenden A research program has been completed at Texas A&M University in which dynamic Young's and shear modulus measurements were made for depleted Uranium-2wt... INTRODUCTION The need for mankind to utilize his abundant natural resources has led him to numerous research programs with depleted uranium. Depleted uranium ( U-238 ) is a by-product of the nuclear industry. Natural uranium contains about 0. 7...

  16. Study of Reasons for the Adoption of Lean Production in the Automobile Industry: Questions for the AEC Industries

    E-Print Network [OSTI]

    Tommelein, Iris D.

    Study of Reasons for the Adoption of Lean Production in the Automobile Industry: Questions IN THE AUTOMOBILE INDUSTRY: QUESTIONS FOR THE AEC INDUSTRIES Scott Featherston1 ABSTRACT The primary intent in opting for an alternative? Were there pressures that gave automobile producers no option but to alter

  17. Opportunities for UPC Product and Service Suppliers: The Wood Products Industry

    E-Print Network [OSTI]

    Wu, Qinglin

    product and service suppliers. #12;4 UPC Suppliers To The Wood Products Industry Twenty-seven companies.3 percent of all corporate sales for these 27 respondent companies. An additional 15 companies indicated, from the largest timbers to small lengths of wood moulding are complying with customer requirements

  18. Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

    SciTech Connect (OSTI)

    Croff, A.G.

    2001-01-11T23:59:59.000Z

    The purpose of this report is to review and document the capability of potential products of depleted UF{sub 6} conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report.

  19. Sponsors of CIEEDAC: Natural Resources Canada, Canadian Industry Program for Energy Conservation, Aluminium Industry Association, Canadian Petroleum Products Institute, Canadian Portland Cement Association, Canadian Pulp

    E-Print Network [OSTI]

    , Aluminium Industry Association, Canadian Petroleum Products Institute, Canadian Portland Cement Association

  20. The Influence of Product Markets on Industrial Relations

    E-Print Network [OSTI]

    Brown, William

    ; Lace Finishing, or whatever. As recently as 1961, the Ministry of Labour’s official Industrial Relations Handbook could say: ‘When the agreement is made by a number of different employers or, as is often the case, by an employers’ association acting... of product markets is also reflected in the changing impact of collective bargaining. In a review of the micro-economic effects of trade unions, Metcalf notes that several studies in the 1980s had reported a negative association between union presence...

  1. Uranium Processing Facility Site Readiness Subproject Completed...

    National Nuclear Security Administration (NNSA)

    Field Offices Welcome to the NNSA Production Office NPO News Releases Uranium Processing Facility Site Readiness Subproject Completed ... Uranium Processing Facility Site...

  2. Method for the recovery of uranium values from uranium tetrafluoride

    DOE Patents [OSTI]

    Kreuzmann, Alvin B. (Cincinnati, OH)

    1983-01-01T23:59:59.000Z

    The invention is a novel method for the recovery of uranium from dry, particulate uranium tetrafluoride. In one aspect, the invention comprises reacting particulate uranium tetrafluoride and calcium oxide in the presence of gaseous oxygen to effect formation of the corresponding alkaline earth metal uranate and alkaline earth metal fluoride. The product uranate is highly soluble in various acidic solutions wherein the product fluoride is virtually insoluble therein. The product mixture of uranate and alkaline earth metal fluoride is contacted with a suitable acid to provide a uranium-containing solution, from which the uranium is recovered. The invention can achieve quantitative recovery of uranium in highly pure form.

  3. Method for the recovery of uranium values from uranium tetrafluoride

    DOE Patents [OSTI]

    Kreuzmann, A.B.

    1982-10-27T23:59:59.000Z

    The invention is a novel method for the recovery of uranium from dry, particulate uranium tetrafluoride. In one aspect, the invention comprises reacting particulate uranium tetrafluoride and calcium oxide in the presence of gaseous oxygen to effect formation of the corresponding alkaline earth metal uranate and alkaline earth metal fluoride. The product uranate is highly soluble in various acidic solutions whereas the product fluoride is virtually insoluble therein. The product mixture of uranate and alkaline earth metal fluoride is contacted with a suitable acid to provide a uranium-containing solution, from which the uranium is recovered. The invention can achieve quantitative recovery of uranium in highly pure form.

  4. WISE Uranium Project - Fact Sheet

    E-Print Network [OSTI]

    Hazards From Depleted

    t in the depleted uranium. For this purpose, we first need to calculate the mass balance of the enrichment process. We then calculate the inhalation doses from the depleted uranium and compare the dose contributions from the nuclides of interest. Mass balance for uranium enrichment at Paducah [DOE_1984, p.35] Feed Product Tails Other Mass [st] 758002 124718 621894 11390 Mass fraction 100.00% 16.45% 82.04% 1.50% Concentration of plutonium in tails (depleted uranium) from enrichment of reprocessed uranium, assuming that all plutonium were transfered to the tails: Concentration of neptunium in tails from enrichment of reprocessed uranium uranium, assuming that all neptunium were transfered to the tails: - 2 - Schematic of historic uranium enrichment process at Paducah [DOE_1999b] - -7 For comparison, we first calculate the inhalation dose from depleted uranium produced from natural uranium. We assume that the short-lived decay products have reached secular equilibrium with th

  5. Industry

    SciTech Connect (OSTI)

    Bernstein, Lenny; Roy, Joyashree; Delhotal, K. Casey; Harnisch, Jochen; Matsuhashi, Ryuji; Price, Lynn; Tanaka, Kanako; Worrell, Ernst; Yamba, Francis; Fengqi, Zhou; de la Rue du Can, Stephane; Gielen, Dolf; Joosen, Suzanne; Konar, Manaswita; Matysek, Anna; Miner, Reid; Okazaki, Teruo; Sanders, Johan; Sheinbaum Parado, Claudia

    2007-12-01T23:59:59.000Z

    This chapter addresses past, ongoing, and short (to 2010) and medium-term (to 2030) future actions that can be taken to mitigate GHG emissions from the manufacturing and process industries. Globally, and in most countries, CO{sub 2} accounts for more than 90% of CO{sub 2}-eq GHG emissions from the industrial sector (Price et al., 2006; US EPA, 2006b). These CO{sub 2} emissions arise from three sources: (1) the use of fossil fuels for energy, either directly by industry for heat and power generation or indirectly in the generation of purchased electricity and steam; (2) non-energy uses of fossil fuels in chemical processing and metal smelting; and (3) non-fossil fuel sources, for example cement and lime manufacture. Industrial processes also emit other GHGs, e.g.: (1) Nitrous oxide (N{sub 2}O) is emitted as a byproduct of adipic acid, nitric acid and caprolactam production; (2) HFC-23 is emitted as a byproduct of HCFC-22 production, a refrigerant, and also used in fluoroplastics manufacture; (3) Perfluorocarbons (PFCs) are emitted as byproducts of aluminium smelting and in semiconductor manufacture; (4) Sulphur hexafluoride (SF{sub 6}) is emitted in the manufacture, use and, decommissioning of gas insulated electrical switchgear, during the production of flat screen panels and semiconductors, from magnesium die casting and other industrial applications; (5) Methane (CH{sub 4}) is emitted as a byproduct of some chemical processes; and (6) CH{sub 4} and N{sub 2}O can be emitted by food industry waste streams. Many GHG emission mitigation options have been developed for the industrial sector. They fall into three categories: operating procedures, sector-wide technologies and process-specific technologies. A sampling of these options is discussed in Sections 7.2-7.4. The short- and medium-term potential for and cost of all classes of options are discussed in Section 7.5, barriers to the application of these options are addressed in Section 7.6 and the implication of industrial mitigation for sustainable development is discussed in Section 7.7. Section 7.8 discusses the sector's vulnerability to climate change and options for adaptation. A number of policies have been designed either to encourage voluntary GHG emission reductions from the industrial sector or to mandate such reductions. Section 7.9 describes these policies and the experience gained to date. Co-benefits of reducing GHG emissions from the industrial sector are discussed in Section 7.10. Development of new technology is key to the cost-effective control of industrial GHG emissions. Section 7.11 discusses research, development, deployment and diffusion in the industrial sector and Section 7.12, the long-term (post-2030) technologies for GHG emissions reduction from the industrial sector. Section 7.13 summarizes gaps in knowledge.

  6. Managing novelty at the interfaces between concept and product : case studies for the automotive industry

    E-Print Network [OSTI]

    Zarewych, Lara Daniv, 1972-

    2005-01-01T23:59:59.000Z

    Appearance of the product is a discerning factor for the consumers purchase decisions. Time from concept to product creation is a critical factor in the competitive automotive industry. The period to develop a product is ...

  7. Aggregate Production Planning for Process Industries under Competition

    E-Print Network [OSTI]

    Karmarkar, U. S.; Rajaram, K.

    2008-01-01T23:59:59.000Z

    such as the oil refining and steel industries, there arerefining industry appears to be a particularly egregious example of jockeying by crude oil

  8. Uranium hexafluoride liquid thermal expansion, elusive eutectic with hydrogen fluoride, and very first production using chlorine trifluoride

    SciTech Connect (OSTI)

    Rutledge, G.P. [Central Environmental, Inc., Anchorage, AK (United States)

    1991-12-31T23:59:59.000Z

    Three unusual incidents and case histories involving uranium hexafluoride in the enrichment facilities of the USA in the late 1940`s and early 1950`s are presented. The history of the measurements of the thermal expansion of liquids containing fluorine atoms within the molecule is reviewed with special emphasis upon uranium hexafluoride. A comparison is made between fluorinated esters, fluorocarbons, and uranium hexafluoride. The quantitative relationship between the thermal expansion coefficient, a, of liquids and the critical temperature, T{sub c} is presented. Uranium hexafluoride has an a that is very high in a temperature range that is used by laboratory and production workers - much higher than any other liquid measured. This physical property of UF{sub 6} has resulted in accidents involving filling the UF{sub 6} containers too full and then heating with a resulting rupture of the container. Such an incident at a uranium gaseous diffusion plant is presented. Production workers seldom {open_quotes}see{close_quotes} uranium hexafluoride. The movement of UF{sub 6} from one container to another is usually trailed by weight, not sight. Even laboratory scientists seldom {open_quotes}see{close_quotes} solid or liquid UF{sub 6} and this can be a problem at times. This inability to {open_quotes}see{close_quotes} the UF{sub 6}-HF mixtures in the 61.2{degrees}C to 101{degrees}C temperature range caused a delay in the understanding of the phase diagram of UF{sub 6}-HF which has a liquid - liquid immiscible region that made the eutectic composition somewhat elusive. Transparent fluorothene tubes solved the problem both for the UF{sub 6}-HF phase diagram as well as the UF{sub 6}-HF-CIF{sub 3} phase diagram with a miscibility gap starting at 53{degrees}C. The historical background leading to the first use of CIF{sub 3} to produce UF{sub 6} in both the laboratory and plant at K-25 is presented.

  9. Standard test method for gamma energy emission from fission products in uranium hexafluoride and uranyl nitrate solution

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2005-01-01T23:59:59.000Z

    1.1 This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C 787 and C 996 and uranyl nitrate specification C 788. 1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background. 1.3 The nuclides to be measured are106Ru/ 106Rh, 103Ru,137Cs, 144Ce, 144Pr, 141Ce, 95Zr, 95Nb, and 125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its us...

  10. INDUSTRIELL HYGIEN OCH PRODUKTSKERHET KMB030 Industrial Hygiene and Product Safety

    E-Print Network [OSTI]

    INDUSTRIELL HYGIEN OCH PRODUKTSÄKERHET KMB030 Industrial Hygiene and Product Safety Poäng: 5 omfattar hygien, aseptik, Rena Rum, process design, rengöring (kemiskt/termiska förfaranden

  11. International Journal of Industrial Ergonomics Measuring consumer perceptions for the development of product

    E-Print Network [OSTI]

    Boyer, Edmond

    International Journal of Industrial Ergonomics Measuring consumer perceptions for the development in "International Journal of Industrial Ergonomics 33, 6 (2004) 507-525" DOI : 10.1016/j.ergon.2003.12.004 #12;2 International Journal of Industrial Ergonomics Abstract Product semantics, the "study of the symbolic qualities

  12. Crossing innovation & product projects management: A comparative analysis in automotive industry

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Crossing innovation & product projects management: A comparative analysis in automotive industry in automotive industry INTRODUCTION Projectification and platform approaches have been two main transformation in the automotive industry. This sector provides an interesting empirical opportunity to study this question, since

  13. A CONTROL SYSTEM FOR TOBACCO SHRED PRODUCTION LINE BASED ON INDUSTRIAL

    E-Print Network [OSTI]

    quality insurance (Sun Xin, 2007). The Rockwell Automation Company introduced a new industrial EthernetA CONTROL SYSTEM FOR TOBACCO SHRED PRODUCTION LINE BASED ON INDUSTRIAL ETHERNET Li Zhang1 , Guang Industrial Corporation, Nanyang, He Nan, China, 473000 * Corresponding author, Address: College

  14. Aligning product and supply chain strategies in the mobile phone industry

    E-Print Network [OSTI]

    Scanlon, Robert (Robert Curtis)

    2009-01-01T23:59:59.000Z

    Designing and managing the supply chain of a company in the mobile phone industry is particularly challenging. Short product lifecycles, rapidly evolving technology, globally linked distribution networks, increasing product ...

  15. Services and the Business Models of Product Firms: An Empirical Analysis of the Software Industry

    E-Print Network [OSTI]

    Suarez, Fernando F.

    Some product firms increasingly rely on service revenues as part of their business models. One possible explanation is that they turn to services to generate additional profits when their product industries mature and ...

  16. Ergonomic Solutions for the Secondary Wood Products Industry On October 17th

    E-Print Network [OSTI]

    Gazo, Rado

    Ergonomic Solutions for the Secondary Wood Products Industry On October 17th and 18th , 2001, you are invited to a conference entitled: Ergonomic Solutions for the Secondary Wood Products Industry. This seminar will be held at Executive Inn, in Louisville, Kentucky. Hear the latest developments in ergonomics

  17. eBusiness in the Forest Products Industry: A Comparison of the United States & Canada

    E-Print Network [OSTI]

    eBusiness in the Forest Products Industry: A Comparison of the United States & Canada Olivian Pitis products industry in the United States and Canada. Both solid and pulp/paper companies were surveyed the United States & Canada. Objectives #12;All Respondents Results #12;1 company .05% of respondents North

  18. Using E-Commerce in the Forest Products Industry Chapter 1.2.

    E-Print Network [OSTI]

    Using E-Commerce in the Forest Products Industry Chapter 1.2. Using E-Commerce in the Forest The forest products industry is rapidly adopting e-commerce solutions as it advances in the information age. In this chapter, the unique e-commerce needs of this sector's small businesses are discussed. Current experience

  19. Aggregate Production Planning for Process Industries under Competition

    E-Print Network [OSTI]

    Karmarkar, U. S.; Rajaram, K.

    2008-01-01T23:59:59.000Z

    as petro- refining, petrochemicals, basic chemicals, cement,the context of the petrochemical industry, these producerscorrespond to the ten major petrochemical refining companies

  20. Production of small uranium dioxide microspheres for cermet nuclear fuel using the internal gelation process

    SciTech Connect (OSTI)

    Collins, Robert T [ORNL] [ORNL; Collins, Jack Lee [ORNL] [ORNL; Hunt, Rodney Dale [ORNL] [ORNL; Ladd-Lively, Jennifer L [ORNL] [ORNL; Patton, Kaara K [ORNL] [ORNL; Hickman, Robert [NASA Marshall Space Flight Center, Huntsville, AL] [NASA Marshall Space Flight Center, Huntsville, AL

    2014-01-01T23:59:59.000Z

    The U.S. National Aeronautics and Space Administration (NASA) is developing a uranium dioxide (UO2)/tungsten cermet fuel for potential use as the nuclear cryogenic propulsion stage (NCPS). The first generation NCPS is expected to be made from dense UO2 microspheres with diameters between 75 and 150 m. Previously, the internal gelation process and a hood-scale apparatus with a vibrating nozzle were used to form gel spheres, which became UO2 kernels with diameters between 350 and 850 m. For the NASA spheres, the vibrating nozzle was replaced with a custom designed, two-fluid nozzle to produce gel spheres in the desired smaller size range. This paper describes the operational methodology used to make 3 kg of uranium oxide microspheres.

  1. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors

    DOE Patents [OSTI]

    McLean, W. II; Miller, P.E.

    1997-12-16T23:59:59.000Z

    A method is described for purifying metallic alloys of uranium for use as nuclear reactor fuels in which the metal alloy is first converted to an oxide and then dissolved in nitric acid. Initial removal of metal oxide impurities not soluble in nitric acid is accomplished by filtration or other physical means. Further purification can be accomplished by carbonate leaching of uranyl ions from the partially purified solution or using traditional methods such as solvent extraction. 3 figs.

  2. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors

    DOE Patents [OSTI]

    McLean, II, William (Oakland, CA); Miller, Philip E. (Livermore, CA)

    1997-01-01T23:59:59.000Z

    A method for purifying metallic alloys of uranium for use as nuclear reactor fuels in which the metal alloy is first converted to an oxide and then dissolved in nitric acid. Initial removal of metal oxide impurities not soluble in nitric acid is accomplished by filtration or other physical means. Further purification can be accomplished by carbonate leaching of uranyl ions from the partially purified solution or using traditional methods such as solvent extraction.

  3. Fabrication options for depleted uranium components in shielded containers

    SciTech Connect (OSTI)

    Derrington, S.B.; Thompson, J.E.; Coates, C.W.

    1994-01-27T23:59:59.000Z

    Depleted uranium (DU) is an attractive material for the gamma-shielding components in containers designed for the storage, transport, and disposal of high-level radioactive wastes or spent nuclear fuel. The size and weight of these components present fabrication challenges. A broad range of technical expertise, capabilities, and facilities for uranium manufacturing and technology development exist at the Department of Energy laboratories and production facilities and within commercial industry. Several cast and wrought processes are available to fabricate the DU components. Integration of the DU fabrication capabilities and physical limitations for handling the DU components into the early design phase will ensure a fabricable product.

  4. Method for fabricating .sup.99 Mo production targets using low enriched uranium, .sup.99 Mo production targets comprising low enriched uranium

    DOE Patents [OSTI]

    Wiencek, Thomas C. (Orland Park, IL); Matos, James E. (Oak Park, IL); Hofman, Gerard L. (Downers Grove, IL)

    2000-12-12T23:59:59.000Z

    A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith. The method for fabricating a primary target for the production of fission products comprises preparing a first substrate to receive a foil of fissionable material so as to allow for later removal of the foil from the first substrate, preparing a second substrate to receive the foil so as to allow for later removal of the foil from the second substrate; attaching the first substrate to the second substrate such that the foil is sandwiched between the first substrate and second substrate to prevent foil exposure to ambient atmosphere, and compressing the exposed surfaces of the first and second substrate to assure snug mechanical contact between the foil, the first substrate and the second substrate.

  5. Method for fabricating .sup.99 Mo production targets using low enriched uranium, .sup.99 Mo production targets comprising low enriched uranium

    DOE Patents [OSTI]

    Wiencek, Thomas C. (Orland Park, IL); Matos, James E. (Oak Park, IL); Hofman, Gerard L. (Downers Grove, IL)

    1997-01-01T23:59:59.000Z

    A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith. The method for fabricating a primary target for the production of fission products comprises preparing a first substrate to receive a foil of fissionable material so as to allow for later removal of the foil from the first substrate, preparing a second substrate to receive the foil so as to allow for later removal of the foil from the second substrate; attaching the first substrate to the second substrate such that the foil is sandwiched between the first substrate and second substrate to prevent foil exposure to ambient atmosphere, and compressing the exposed surfaces of the first and second substrate to assure snug mechanical contact between the foil, the first substrate and the second substrate.

  6. Method for fabricating {sup 99}Mo production targets using low enriched uranium, {sup 99}Mo production targets comprising low enriched uranium

    DOE Patents [OSTI]

    Wiencek, T.C.; Matos, J.E.; Hofman, G.L.

    1997-03-25T23:59:59.000Z

    A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith. The method for fabricating a primary target for the production of fission products comprises preparing a first substrate to receive a foil of fissionable material so as to allow for later removal of the foil from the first substrate, preparing a second substrate to receive the foil so as to allow for later removal of the foil from the second substrate; attaching the first substrate to the second substrate such that the foil is sandwiched between the first substrate and second substrate to prevent foil exposure to ambient atmosphere, and compressing the exposed surfaces of the first and second substrate to assure snug mechanical contact between the foil, the first substrate and the second substrate. 3 figs.

  7. Industry

    E-Print Network [OSTI]

    Bernstein, Lenny

    2008-01-01T23:59:59.000Z

    SHIP - Solar heat for industrial processes. Internationalsolar power could be used to provide process heat for

  8. Practical Training in Microalgae Utilization with Key Industry Engineering Group Key Industry Engineering Group s.r.o. has developed a biotechnology for the production of an animal

    E-Print Network [OSTI]

    Practical Training in Microalgae Utilization with Key Industry Engineering Group Key Industry on a suspension of Planktochlorella microalgae. The product consists of a suspension of algae in the growing

  9. 300 AREA URANIUM CONTAMINATION

    SciTech Connect (OSTI)

    BORGHESE JV

    2009-07-02T23:59:59.000Z

    {sm_bullet} Uranium fuel production {sm_bullet} Test reactor and separations experiments {sm_bullet} Animal and radiobiology experiments conducted at the. 331 Laboratory Complex {sm_bullet} .Deactivation, decontamination, decommissioning,. and demolition of 300 Area facilities

  10. Conversion and Blending Facility highly enriched uranium to low enriched uranium as oxide. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-07-05T23:59:59.000Z

    This Conversion and Blending Facility (CBF) will have two missions: (1) convert HEU materials into pure HEU oxide and (2) blend the pure HEU oxide with depleted and natural uranium oxide to produce an LWR grade LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. To the extent practical, the chemical and isotopic concentrations of blended LEU product will be held within the specifications required for LWR fuel. Such blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry. Otherwise, blended LEU will be produced as a waste suitable for storage or disposal.

  11. Strategic change and the coevolution of industry-university relationships : evidence from the forest products industry

    E-Print Network [OSTI]

    Pertuzé Salas, Julio Alberto

    2014-01-01T23:59:59.000Z

    In this thesis we present an analysis of the dynamics of industry-university relationships tracing the origin of the relationship and its changes over time as the firm's strategies evolve. We analyze the strategic trajectories ...

  12. Industrial recovered-materials-utilization targets for the metals and metal-products industry

    SciTech Connect (OSTI)

    None

    1980-03-01T23:59:59.000Z

    The National Energy Conservation Policy Act of 1978 directs DOE to set targets for increased utilization of energy-saving recovered materials for certain industries. These targets are to be established at levels representing the maximum feasible increase in utilization of recovered materials that can be achieved progressively by January 1, 1987 and is consistent with technical and economic factors. A benefit to be derived from the increased use of recoverable materials is in energy savings, as state in the Act. Therefore, emhasis on different industries in the metals sector has been related to their energy consumption. The ferrous industry (iron and steel, ferrour foundries and ferralloys), as defined here, accounts for approximately 3%, and all others for the remaining 3%. Energy consumed in the lead and zinc segments is less than 1% each. Emphasis is placed on the ferrous scrap users, followed by the aluminum and copper industries. A bibliography with 209 citations is included.

  13. Residual Nuclide Production by Proton-Induced Reactions on Uranium for Energies between 20 and 70 MeV

    SciTech Connect (OSTI)

    Uosif, M.A.M. [Center for Radiation Protection and Radioecology, University Hannover (Germany); Physics Department, Al-Azhar University, Faculty of Science, Assiut (Egypt); Michel, R. [Center for Radiation Protection and Radioecology, University Hannover (Germany); Herpers, U. [Dept. for Nuclear Chemistry, University of Cologne (Germany); Kubik, P.-W. [Institute for Particle Physics, ETH Hoenggerberg, Zurich (Switzerland); Duijvestijn, M.; Koning, A. [Nuclear Research and Consultancy Group, Petten (Netherlands)

    2005-05-24T23:59:59.000Z

    Within the HINDAS project, proton-irradiation experiments were performed at the injector cyclotron of the Paul Scherrer Institute at Villigen/Switzerland in order to investigate the production of residual nuclides from natural uranium. The stacked-foil technique was used to cover proton energies between 20 MeV and 70 MeV. Copper targets were used for monitoring the proton beam using the reaction 65Cu (p,n)65Zn. Residual radionuclides were measured by off-line {gamma}-spectrometry. Excitation functions were obtained for the production of 91Y, 95Zr, 95mNb, 99Mo, 103Ru, 112Pd, 115Cd, 124Sb, 126Sb, 127Sb, 132Te, 131I, 134Cs, 136Cs, 137Cs, 140Ba, 141Ce, 144Ce, 147Nd, and 238Np. The experimental data are compared to the sparse results of earlier measurements and with theoretical excitation functions calculated by the newly developed TALYS code. Good agreement between theory and experiment was obtained for product masses up to 115. For higher-mass fission products and for 238Np, there are still systematic deviations between theory and experiment. These deviations are discussed as deficits of the fission model in the heavy part of the fission product distribution.

  14. Industrial recovery capability. Final report. [Claus alumina catalyst for sulfur production

    SciTech Connect (OSTI)

    Gregg, D.W.

    1984-12-01T23:59:59.000Z

    This report provides an evaluation of the vulnerability - to a nuclear strike, terrorist attack, or natural disaster - of our national capacity to produce chlorine, beryllium, and a particular specialty alumina catalyst required for the production of sulfur. All of these industries are of critical importance to the United States economy. Other industries that were examined and found not to be particularly vulnerable are medicinal drugs and silicon wafers for electronics. Thus, only the three more vulnerable industries are addressed in this report.

  15. Establishment of a Graduate Certificate Program in Biobased Industrial Products – Final Technical Report

    SciTech Connect (OSTI)

    John R. Schlup

    2005-11-04T23:59:59.000Z

    A certificate of graduate studies in Biobased Industrial Products is to be established at Kansas State University (KSU) along with the development of a similar program at Pittsburg State University, Pittsburg, KS. At KSU, the program of study will be coordinated through the steering committee of the Agricultural Products Utilization Forum (APUF); the certificate of graduate studies will be awarded through the Graduate School of Kansas State University. This certificate will establish an interdisciplinary program of study that will: (1) ensure participating students receive a broad education in several disciplines related to Biobased Industrial Products, (2) provide a documented course of study for students preferring a freestanding certificate program, and (3) provide a paradigm shift in student awareness away from petroleum-based feedstocks to the utilization of renewable resources for fuels and chemical feedstocks. The academic program described herein will accomplish this goal by: (1) providing exposure to several academic disciplines key to Biobased Industrial Products; (2) improving university/industry collaboration through an external advisory board, distance learning opportunities, and student internships; (3) expanding the disciplines represented on the students' supervisory committee; (4) establishing a seminar series on Biobased Industrial Products that draws upon expert speakers representing several disciplines; and (5) increasing collaboration between disciplines. Numerous research programs emphasizing Biobased Industrial Products currently exist at KSU and PSU. The certificate of graduate studies, the emphasis on interdisciplinary collaboration within the students? thesis research, the proposed seminar series, and formation of an industrial advisory board will: (1) provide an interdisciplinary academic experience that spans several departments, four colleges, four research centers, and two universities; (2) tangibly promote collaboration between KSU and PSU; (3) catalyze involvement of plant geneticists with researchers active in the development and utilization of biobased industrial products; and, (4) promote university/industry collaboration.

  16. Covered Product Category: Industrial Luminaires (High/Low Bay)

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance and Federal efficiency requirements for Industrial Luminaires (High/Low Bay). Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  17. GLOBAL OPTIMIZATION OF ENERGY AND PRODUCTION IN PROCESS INDUSTRIES: A

    E-Print Network [OSTI]

    Neumaier, Arnold

    ) The task of the auxiliary boiler, together with the recovery boiler, is to produce high-pressure steam (HPS, . . . , n) units, and delivers the raw material to department i + 1, working at rate ui+1 units; bj,i+1 · ui+1 units are consumed from buffer j for 1 Partially financed by JNICT/PRAXIS XXI program. Industrial

  18. Moving Toward Product Line Engineering in a Nuclear Industry Consortium

    E-Print Network [OSTI]

    Boyer, Edmond

    power have special institutions overseeing and regulating nuclear safety. Nuclear industry projects must conform to na- tional safety institutions and international regulations. In many cases, regulatory sophisticated and complex energy systems ever designed. Nuclear safety Permission to make digital or hard copies

  19. Understanding the link between aggregated industrial production and the carbon price

    E-Print Network [OSTI]

    Boyer, Edmond

    the link between aggregated industrial production and the carbon price. In The Economics of Green Energy Association (Boston), the BC3 Low Carbon Programme Workshop on "The Economics of Green Energy and Efficiency

  20. The Power of Integrality: Linkages between Product Architecture, Innovation, and Industry Structure

    E-Print Network [OSTI]

    Fixson, Sebastian K.

    2008-04-30T23:59:59.000Z

    A substantial literature stream suggests that many products are becoming more modular over time, and that this development is often associated with a change in industry structure towards higher degrees of specialization. ...

  1. Highlights of Industrial Energy Audits with Application in Paper Product Manufacturing

    E-Print Network [OSTI]

    Hart, M. N.; Bond, S. K.

    1979-01-01T23:59:59.000Z

    Experience in executing comprehensive energy audits in varied industrial plants has resulted in a basic audit methodology and has revealed several interesting energy conservation opportunities applicable to paper products manufacturing. The most...

  2. India's Worsening Uranium Shortage

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2007-01-15T23:59:59.000Z

    As a result of NSG restrictions, India cannot import the natural uranium required to fuel its Pressurized Heavy Water Reactors (PHWRs); consequently, it is forced to rely on the expediency of domestic uranium production. However, domestic production from mines and byproduct sources has not kept pace with demand from commercial reactors. This shortage has been officially confirmed by the Indian Planning Commission’s Mid-Term Appraisal of the country’s current Five Year Plan. The report stresses that as a result of the uranium shortage, Indian PHWR load factors have been continually decreasing. The Uranium Corporation of India Ltd (UCIL) operates a number of underground mines in the Singhbhum Shear Zone of Jharkhand, and it is all processed at a single mill in Jaduguda. UCIL is attempting to aggrandize operations by establishing new mines and mills in other states, but the requisite permit-gathering and development time will defer production until at least 2009. A significant portion of India’s uranium comes from byproduct sources, but a number of these are derived from accumulated stores that are nearing exhaustion. A current maximum estimate of indigenous uranium production is 430t/yr (230t from mines and 200t from byproduct sources); whereas, the current uranium requirement for Indian PHWRs is 455t/yr (depending on plant capacity factor). This deficit is exacerbated by the additional requirements of the Indian weapons program. Present power generation capacity of Indian nuclear plants is 4350 MWe. The power generation target set by the Indian Department of Atomic Energy (DAE) is 20,000 MWe by the year 2020. It is expected that around half of this total will be provided by PHWRs using indigenously supplied uranium with the bulk of the remainder provided by breeder reactors or pressurized water reactors using imported low-enriched uranium.

  3. Conversion and Blending Facility Highly enriched uranium to low enriched uranium as uranium hexafluoride. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-07-05T23:59:59.000Z

    This report describes the Conversion and Blending Facility (CBF) which will have two missions: (1) convert surplus HEU materials to pure HEU UF{sub 6} and a (2) blend the pure HEU UF{sub 6} with diluent UF{sub 6} to produce LWR grade LEU-UF{sub 6}. The primary emphasis of this blending be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The chemical and isotopic concentrations of the blended LEU product will be held within the specifications required for LWR fuel. The blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry.

  4. Control of structure and reactivity by ligand design : applications to small molecule activation by low-valent uranium complexes

    E-Print Network [OSTI]

    Lam, Oanh Phi

    2010-01-01T23:59:59.000Z

    coordination chemistry is depleted uranium, a by-product innuclear reactors. Depleted uranium Figure 1-1. The periodic

  5. Uranium immobilization and nuclear waste

    SciTech Connect (OSTI)

    Duffy, C.J.; Ogard, A.E.

    1982-02-01T23:59:59.000Z

    Considerable information useful in nuclear waste storage can be gained by studying the conditions of uranium ore deposit formation. Further information can be gained by comparing the chemistry of uranium to nuclear fission products and other radionuclides of concern to nuclear waste disposal. Redox state appears to be the most important variable in controlling uranium solubility, especially at near neutral pH, which is characteristic of most ground water. This is probably also true of neptunium, plutonium, and technetium. Further, redox conditions that immobilize uranium should immobilize these elements. The mechanisms that have produced uranium ore bodies in the Earth's crust are somewhat less clear. At the temperatures of hydrothermal uranium deposits, equilibrium models are probably adequate, aqueous uranium (VI) being reduced and precipitated by interaction with ferrous-iron-bearing oxides and silicates. In lower temperature roll-type uranium deposits, overall equilibrium may not have been achieved. The involvement of sulfate-reducing bacteria in ore-body formation has been postulated, but is uncertain. Reduced sulfur species do, however, appear to be involved in much of the low temperature uranium precipitation. Assessment of the possibility of uranium transport in natural ground water is complicated because the system is generally not in overall equilibrium. For this reason, Eh measurements are of limited value. If a ground water is to be capable of reducing uranium, it must contain ions capable of reducing uranium both thermodynamically and kinetically. At present, the best candidates are reduced sulfur species.

  6. Production of Biogas from Wastewaters of Food Processing Industries

    E-Print Network [OSTI]

    Sax, R. I.; Holtz, M.; Pette, K. C.

    1980-01-01T23:59:59.000Z

    volume per day could be treated with the upflow process with a purification efficiency of order 90%. CSM APPLICATION Although the initial work at Wageningen was with potato starch wastewater, the first industrial scale application with this process... was carried out by Centrale Suiker Maatschappij (CSM) , the largest privately-owned beet sugar company in Holland. Their factories had been treating wastewater with oxidation ponds which carried the serious drawbacks of large energy consumption...

  7. Depleted uranium management alternatives

    SciTech Connect (OSTI)

    Hertzler, T.J.; Nishimoto, D.D.

    1994-08-01T23:59:59.000Z

    This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process.

  8. Assessing and reducing product portfolio complexity in the pharmaceutical industry

    E-Print Network [OSTI]

    Leiter, Kevin M. (Kevin Michael)

    2011-01-01T23:59:59.000Z

    Overly complex product portfolios lead to inefficient use of resources and limit an organization's ability to react quickly to changing market dynamics. The challenges of reducing portfolio complexity are defining excess ...

  9. Aggregate Production Planning for Process Industries under Competition

    E-Print Network [OSTI]

    Karmarkar, U. S.; Rajaram, K.

    2008-01-01T23:59:59.000Z

    occurs in oil production, where the supply of crude is oftenproduction quantities and profits for refiners and the crude oilproduction quantities and profits for refiners and the crude oil

  10. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Paducah Gaseous Diffusion Plant site

    SciTech Connect (OSTI)

    Marmer, G.J.; Dunn, C.P.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Yuen, C.R.; Cleland, J.H. (ed.)

    1991-09-01T23:59:59.000Z

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. The U-235 atoms are ionized when precisely tuned laser light -- of appropriate power, spectral, and temporal characteristics -- illuminates the uranium vapor and selectively photoionizes the U-235 isotope. A programmatic document for use in screening DOE site to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the PGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. 65 refs., 15 tabs.

  11. Industry

    E-Print Network [OSTI]

    Bernstein, Lenny

    2008-01-01T23:59:59.000Z

    of its electricity requirements in the USA (US DOE, 2002)USA, where motor-driven systems account for 63% of industrial electricity

  12. Organizational Assessment Of Integrating CAD And Product Data Management Tools In The Furniture Industry

    E-Print Network [OSTI]

    Industry Furniture Manufacturing and Management Center Technical Report 1996-1997 Eric N. Wiebe Jennifer J of issues faced by furniture companies are given. The literature review closes by focusing on additional in manufacturing and design has popularized the concept of the virtual product database. Product Data Management

  13. Recent International R&D Activities in the Extraction of Uranium from Seawater

    E-Print Network [OSTI]

    Rao, Linfeng

    2011-01-01T23:59:59.000Z

    Uranium and Rare Earth Elements Using Biomass of Algae, Bioinorganic Chemistry andRecovery of uranium from sea water. Chemistry & Industry (of uranium from seawater. Turkish Journal of Chemistry, 17 (

  14. Production of bioenergy and biochemicals from industrial and

    E-Print Network [OSTI]

    Angenent, Lars T.

    and agricultural wastewater, includ- ing methanogenic anaerobic digestion, biological hydro- gen production on wastewater treatment from pollution control to resource exploitation. Many bioprocesses can provide bioenergy. Recovery of energy and valuable materials might reduce the cost of wastewater treatment, and somewhat

  15. Lost Opportunities in Industrial Energy Efficiency: New Production Lean Manufacturing and Lean Energy

    E-Print Network [OSTI]

    Seryak, J.; Epstein, G.; D'Antonio, M.

    2006-01-01T23:59:59.000Z

    companies regularly increase production by adding additional manufacturing equipment, or increasing operating hours. This approach can add large new energy loads to the electrical grid and gas distribution networks. Alternately, increasing production...Lost Opportunities in Industrial Energy Efficiency: New Production, Lean Manufacturing and Lean Energy John Seryak Gary Epstein Mark D’Antonio Engineer jseryak@ers-inc.com President gepstein@ers-inc.com Vice President mdantonio...

  16. Structure of Cow-Calf Industry Beef production in Texas is a $7 billion industry,

    E-Print Network [OSTI]

    , carcass evaluation, record-keeping, and organic and natural beef production. For more than a half century Cattle Short Course. Economic Benefit The economic benefit of the Beef Cattle Short Course was measured with these practices range from $8 to $25 per animal, resulting in a total economic benefit of $350,000 in 2011

  17. Development of a New Extended Motor Product Label for Industrial Energy Efficiency

    E-Print Network [OSTI]

    Rogers, E.; Boteler, R.; Elliot, R. N.

    2014-01-01T23:59:59.000Z

    opportunities ESL-IE-14-05-11 Proceedings of the Thrity-Sixth Industrial Energy Technology Conference New Orleans, LA. May 20-23, 2014 Prescriptive Rebate Programs Provides a rebate for specific products that have been determined to be more efficient... of the Thrity-Sixth Industrial Energy Technology Conference New Orleans, LA. May 20-23, 2014 Example: Prescriptive Rebates Example: NEMA Premium ® • Label identifies highest efficiency motors • Label is acceptable documentation for efficiency programs...

  18. Industry

    E-Print Network [OSTI]

    Bernstein, Lenny

    2008-01-01T23:59:59.000Z

    process residual like bagasse are now available (Cornland etsugar in- dustry uses bagasse and the edible oils industrySection 7.4.7. ). The use of bagasse for energy is likely to

  19. Process for alloying uranium and niobium

    SciTech Connect (OSTI)

    Holcombe, C.E.; Northcutt, W.G.; Masters, D.R.; Chapman, L.R.

    1990-12-31T23:59:59.000Z

    Alloys such as U-6Nb are prepared by forming a stacked sandwich array of uranium sheets and niobium powder disposed in layers between the sheets, heating the array in a vacuum induction melting furnace to a temperature such as to melt the uranium, holding the resulting mixture at a temperature above the melting point of uranium until the niobium dissolves in the uranium, and casting the uranium-niobium solution. Compositional uniformity in the alloy product is enabled by use of the sandwich structure of uranium sheets and niobium powder.

  20. Process for alloying uranium and niobium

    SciTech Connect (OSTI)

    Holcombe, C.E.; Northcutt, W.G.; Masters, D.R.; Chapman, L.R.

    1991-04-09T23:59:59.000Z

    This patent describes alloys such as U-6Nb prepared by forming a stacked sandwich array of uranium sheets and niobium powder disposed in layers between the sheets, heating the array in a vacuum induction melting furnace to a temperature such as to melt the uranium, holding the resulting mixture at a temperature above the melting point of uranium until the niobium dissolves in the uranium, and casting the uranium-niobium solution. Compositional uniformity in the alloy product is enabled by use of the sandwich structure of uranium sheets and niobium powder.

  1. URANIUM METAL POWDER PRODUCTION, PARTICLE DISTRIBUTION ANALYSIS, AND REACTION RATE STUDIES OF A HYDRIDE-DEHYDRIDE PROCESS 

    E-Print Network [OSTI]

    Sames, William

    2011-08-08T23:59:59.000Z

    Work was done to study a hydride-dehydride method for producing uranium metal powder. Particle distribution analysis was conducted using digital microscopy and grayscale image analysis software. The particle size was found to be predominantly...

  2. URANIUM METAL POWDER PRODUCTION, PARTICLE DISTRIBUTION ANALYSIS, AND REACTION RATE STUDIES OF A HYDRIDE-DEHYDRIDE PROCESS

    E-Print Network [OSTI]

    Sames, William

    2011-08-08T23:59:59.000Z

    -12 plant in Oak Ridge, Tennessee for providing the depleted uranium used in this project. vi NOMENCLATURE ? Reaction Fraction ACV Atmosphere Containment Vessel AFCI Advanced Fuel Cycle Initiative FCML Fuel Cycle and Materials Laboratory...

  3. Evaluation of selected detector systems for products formed in the atmospheric hydrolysis of uranium hexafluoride

    SciTech Connect (OSTI)

    Bostick, W.D.; Bostick, D.T.

    1987-03-01T23:59:59.000Z

    Sensitive detection of UF/sub 6/ hydrolysis products, either by discontinuous sampling or by continuous or near real-time monitoring, is an important safety consideration for DOE contractors handling large quantities of UF/sub 6/. Automated continuous or rapid intermittent remote sensing of these reaction products can provide an alarm signal when a preselected threshold value has been exceeded (absolute response) or when a significant emission excursion has occurred (rate of change of response). This report evaluates the performance of selected devices for the detection of airborne materials formed in the release of liquid UF/sub 6/ (approx. =1.3 g) into an enclosed volume of 6 m/sup 3/; these experiments were initiated on October 23, 1986. The detection principles investigated are: photometric, gas detector tubes, and electrochemical sensor.

  4. Martn G. Marchetta, Frdrique Mayer, Raymundo Q. Forradellas, A reference framework following a proactive-product approach for Product Lifecycle Management, Computers in Industry 62 (2011) 672683

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    2011-01-01T23:59:59.000Z

    a proactive-product approach for Product Lifecycle Management, Computers in Industry 62 (2011) 672­683 A reference framework following a proactive-product approach for Product Lifecycle Management Martín G Lorraine, 8 rue Bastien Lepage, BP 90647 (54010) Nancy Cedex, France Abstract Product Lifecycle Management

  5. Influence of combustion parameters on NOx production in an industrial boiler

    E-Print Network [OSTI]

    Aldajani, Mansour A.

    Influence of combustion parameters on NOx production in an industrial boiler M.A. Habib a,*, M; accepted 14 April 2007 Available online 24 June 2007 Abstract NOx formation during the combustion process occurs mainly through the oxidation of nitrogen in the combustion air (thermal NOx) and through oxidation

  6. Simultaneous Production and Distribution of Industrial Gas Supply-Chains Pablo A. Marchetti1

    E-Print Network [OSTI]

    Grossmann, Ignacio E.

    -chains. In this industry, cryogenic air separation processes are used to produce oxygen, nitrogen, and argon both as gaseous and liquid products. Air separation units consume large amounts of electricity, mainly due American Air Liquide Inc., Delaware Research and Technology Center, Newark, DE 19702 3 Air Liquide, Paris

  7. CALENDAR YEARS 2012-3 SCHEDULE Workshops to Improve Industrial Productivity by

    E-Print Network [OSTI]

    compressor control types. Learn how to achieve cost savings through more effective production and use determine system efficiency, identify degraded fans, collect data for trending system operation://www.eere.energy.gov/industry/bestpractices/fan_systems.html Motor Systems Management Motor Systems Management training is designed to help facility personnel reduce

  8. SUMMER-FALL 2011 SCHEDULE Workshops to Improve Industrial Productivity by

    E-Print Network [OSTI]

    compressor control types. Learn how to achieve cost savings through more effective production and use determine system efficiency, identify degraded fans, collect data for trending system operation://www.eere.energy.gov/industry/bestpractices/fan_systems.html Motor Systems Management Motor Systems Management training is designed to help facility personnel reduce

  9. Divisionalization, product cannibalization and product location choice: Evidence from the U.S. automobile industry 

    E-Print Network [OSTI]

    Jeong, Eui Kyo

    2004-09-30T23:59:59.000Z

    division's new product location choice. But this study didn't find any significant role of divisional status on new product location choice. And contrary to our expectation, the results of intra-firm divisional domain overlap and new product location choice...

  10. Addendum to industrial market assessment of the products of mild gasification

    SciTech Connect (OSTI)

    Not Available

    1992-05-01T23:59:59.000Z

    The objective of this report is to review and update the 1988 report by J. E. Sinor Consultants Inc., Industrial Market Assessment of the Products of Mild Gasification, and to more fully present market opportunities for two char-based products from the mild gasification process (MGP): Formcoke for the iron and steel industry, and activated carbon for wastewater cleanup and flue gas scrubbing. Please refer to the original report for additional details. In the past, coal conversion projects have and liquids produced, and the value of the residual char was limited to its fuel value. Some projects had limited success until gas and oil competition overwhelmed them. The strategy adopted for this assessment is to seek first a premium value for the char in a market that has advantages over gas and oil, and then to find the highest values possible for gases, liquids, and tars, either on-site or sold into existing markets. During the intervening years since the 1988 report, there have been many changes in the national economy, industrial production, international competition, and environmental regulations. The Clean Air Act Amendments of 1990 (CAAA) will have a large impact on industry. There is considerable uncertainty about how the Act will be implemented, but it specifically addresses coke-oven batteries. This may encourage industry to consider formcoke produced via mild gasification as a low-pollution substitute for conventional coke. The chemistry and technology of coke making steel were reviewed in the 1988 market assessment and will not be repeated here. The CAAA require additional pollution control measures for most industrial facilities, but this creates new opportunities for the mild gasification process.

  11. Addendum to industrial market assessment of the products of mild gasification

    SciTech Connect (OSTI)

    Not Available

    1992-05-01T23:59:59.000Z

    The objective of this report is to review and update the 1988 report by J. E. Sinor Consultants Inc., ``Industrial Market Assessment of the Products of Mild Gasification, and to more fully present market opportunities for two char-based products from the mild gasification process (MGP): Formcoke for the iron and steel industry, and activated carbon for wastewater cleanup and flue gas scrubbing. Please refer to the original report for additional details. In the past, coal conversion projects have and liquids produced, and the value of the residual char was limited to its fuel value. Some projects had limited success until gas and oil competition overwhelmed them. The strategy adopted for this assessment is to seek first a premium value for the char in a market that has advantages over gas and oil, and then to find the highest values possible for gases, liquids, and tars, either on-site or sold into existing markets. During the intervening years since the 1988 report, there have been many changes in the national economy, industrial production, international competition, and environmental regulations. The Clean Air Act Amendments of 1990 (CAAA) will have a large impact on industry. There is considerable uncertainty about how the Act will be implemented, but it specifically addresses coke-oven batteries. This may encourage industry to consider formcoke produced via mild gasification as a low-pollution substitute for conventional coke. The chemistry and technology of coke making steel were reviewed in the 1988 market assessment and will not be repeated here. The CAAA require additional pollution control measures for most industrial facilities, but this creates new opportunities for the mild gasification process.

  12. Technical Report #98T-010, Department of Industrial & Mfg. Systems Egnieering, Lehigh Univerisity COORDINATION PRODUCTION AND TRANSPORTATION

    E-Print Network [OSTI]

    Wu, David

    and production planning and analyze the costs introduced by coordination. Using a Lagrangean decomposition scheme process. Integration of a manufacturing supply chain involves myriad planning, control and coordination logistics have been dealt with separately both in industry and academia. In industry, a production plan

  13. Production of precipitated calcium carbonate from industrial by-product slags (Slag2PCC)

    E-Print Network [OSTI]

    Zevenhoven, Ron

    , it seems that carbonation of silicate minerals could be one of the solutions with most potential. More impor- tantly, it seems to be the only CO2 capture and storage (CCS) option for Finland (Koljonen et al industry, where it is used as a filler and coating pigment in paper. The potential for producing

  14. Progress in developing processes for converting {sup 99}Mo production from high- to low-enriched uranium--1998.

    SciTech Connect (OSTI)

    Conner, C.

    1998-10-28T23:59:59.000Z

    During 1998, the emphasis of our activities was focused mainly on target fabrication. Successful conversion requires a reliable irradiation target; the target being developed uses thin foils of uranium metal, which can be removed from the target hardware for dissolution and processing. This paper describes successes in (1) improving our method for heat-treating the uranium foil to produce a random-small grain structure, (2) improving electrodeposition of zinc and nickel fission-fragment barriers onto the foil, and (3) showing that these fission fragment barriers should be stable during transport of the targets following irradiation. A method was also developed for quantitatively electrodepositing uranium and plutonium contaminants in the {sup 99}Mo. Progress was also made in broadening international cooperation in our development activities.

  15. URANIUM IN ALKALINE ROCKS

    E-Print Network [OSTI]

    Murphy, M.

    2011-01-01T23:59:59.000Z

    chemical elements uranium zirconium niobium beryllium rarerare earths, niobium, zirconium, uranium, and thorium.respect, uranium and thorium are niobium in carbonatitcs.

  16. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611. U.S.

  17. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611. U.S.6.

  18. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.

  19. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.8. U.S.

  20. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.8.

  1. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.8.4.

  2. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.8.4.2.

  3. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars per611.8.4.2.3.

  4. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars

  5. Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars9. Summary

  6. Removal of uranium from aqueous HF solutions

    DOE Patents [OSTI]

    Pulley, Howard (West Paducah, KY); Seltzer, Steven F. (Paducah, KY)

    1980-01-01T23:59:59.000Z

    This invention is a simple and effective method for removing uranium from aqueous HF solutions containing trace quantities of the same. The method comprises contacting the solution with particulate calcium fluoride to form uranium-bearing particulates, permitting the particulates to settle, and separting the solution from the settled particulates. The CaF.sub.2 is selected to have a nitrogen surface area in a selected range and is employed in an amount providing a calcium fluoride/uranium weight ratio in a selected range. As applied to dilute HF solutions containing 120 ppm uranium, the method removes at least 92% of the uranium, without introducing contaminants to the product solution.

  7. Process for alloying uranium and niobium

    DOE Patents [OSTI]

    Holcombe, Cressie E. (Farragut, TN); Northcutt, Jr., Walter G. (Oak Ridge, TN); Masters, David R. (Knoxville, TN); Chapman, Lloyd R. (Knoxville, TN)

    1991-01-01T23:59:59.000Z

    Alloys such as U-6Nb are prepared by forming a stacked sandwich array of uraniun sheets and niobium powder disposed in layers between the sheets, heating the array in a vacuum induction melting furnace to a temperature such as to melt the uranium, holding the resulting mixture at a temperature above the melting point of uranium until the niobium dissolves in the uranium, and casting the uranium-niobium solution. Compositional uniformity in the alloy product is enabled by use of the sandwich structure of uranium sheets and niobium powder.

  8. Benefits of supplementing an industrial waste anaerobic digester with energy crops for increased biogas production

    SciTech Connect (OSTI)

    Nges, Ivo Achu, E-mail: Nges.Ivo_Achu@biotek.lu.se [Department of Biotechnology, Lund University, P.O. Box 124, SE 221 00 Lund (Sweden); Escobar, Federico; Fu Xinmei; Bjoernsson, Lovisa [Department of Biotechnology, Lund University, P.O. Box 124, SE 221 00 Lund (Sweden)

    2012-01-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer This study demonstrates the feasibility of co-digestion food industrial waste with energy crops. Black-Right-Pointing-Pointer Laboratory batch co-digestion led to improved methane yield and carbon to nitrogen ratio as compared to mono-digestion of industrial waste. Black-Right-Pointing-Pointer Co-digestion was also seen as a means of degrading energy crops with nutrients addition as crops are poor in nutrients. Black-Right-Pointing-Pointer Batch co-digestion methane yields were used to predict co-digestion methane yield in full scale operation. Black-Right-Pointing-Pointer It was concluded that co-digestion led an over all economically viable process and ensured a constant supply of feedstock. - Abstract: Currently, there is increasing competition for waste as feedstock for the growing number of biogas plants. This has led to fluctuation in feedstock supply and biogas plants being operated below maximum capacity. The feasibility of supplementing a protein/lipid-rich industrial waste (pig manure, slaughterhouse waste, food processing and poultry waste) mesophilic anaerobic digester with carbohydrate-rich energy crops (hemp, maize and triticale) was therefore studied in laboratory scale batch and continuous stirred tank reactors (CSTR) with a view to scale-up to a commercial biogas process. Co-digesting industrial waste and crops led to significant improvement in methane yield per ton of feedstock and carbon-to-nitrogen ratio as compared to digestion of the industrial waste alone. Biogas production from crops in combination with industrial waste also avoids the need for micronutrients normally required in crop digestion. The batch co-digestion methane yields were used to predict co-digestion methane yield in full scale operation. This was done based on the ratio of methane yields observed for laboratory batch and CSTR experiments compared to full scale CSTR digestion of industrial waste. The economy of crop-based biogas production is limited under Swedish conditions; therefore, adding crops to existing industrial waste digestion could be a viable alternative to ensure a constant/reliable supply of feedstock to the anaerobic digester.

  9. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

    SciTech Connect (OSTI)

    Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

    1991-09-01T23:59:59.000Z

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3.

  10. Comparison of conventional and solar-water-heating products and industries report

    SciTech Connect (OSTI)

    Noreen, D; LeChevalier, R; Choi, M; Morehouse, J

    1980-07-11T23:59:59.000Z

    President Carter established a goal that would require installation of at least one million solar water heaters by 1985 and 20 million water-heating systems by the year 2000. The goals established require that the solar industry be sufficiently mature to provide cost-effective, reliable designs in the immediate future. The objective of this study was to provide the Department of Energy with quantified data that can be used to assess and redirect, if necessary, the program plans to assure compliance with the President's goals. Results deal with the product, the industry, the market, and the consumer. All issues are examined in the framework of the conventional-hot-water industry. Based on the results of this solar hot water assessment study, there is documented proof that the solar industry is blessed with over 20 good solar hot water systems. A total of eight generic types are currently being produced, but a majority of the systems being sold are included in only five generic types. The good systems are well-packaged for quality, performance and installation ease. These leading systems are sized and designed to fit the requirements of the consumer in every respect. This delivery end also suffers from a lack of understanding of the best methods for selling the product. At the supplier end, there are problems also, including: some design deficiencies, improper materials selection and, occasionally, the improper selection of components and subsystems. These, in total, are not serious problems in the better systems and will be resolved as this industry matures.

  11. Divisionalization, product cannibalization and product location choice: Evidence from the U.S. automobile industry

    E-Print Network [OSTI]

    Jeong, Eui Kyo

    2004-09-30T23:59:59.000Z

    -firm divisional domain overlap with a rival division, relative to the focal division's own domain, is more likely to locate its new product (here new car model) closer to that rival's existing car models. And it was also found that divisional density affects a...

  12. The Pacific Northwest National Laboratory delivers financially attractive systems that use biomass to produce industrial and consumer products.

    E-Print Network [OSTI]

    of renewable biomass resources. A New Approach to Biomass #12;To create new uses for agricultural products biomass to produce industrial and consumer products. While biomass holds potential for a ready supply of renewable energy, the primary success factor for this resource--the ability to profitably produce products

  13. ISSUANCE 2015-05-12: Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Test Procedures for Consumer and Commercial Water Heaters

    Broader source: Energy.gov [DOE]

    Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Test Procedures for Consumer and Commercial Water Heaters

  14. Manufacturing industry challenges and responses to EU, California, and other product-targeted environmental regulations

    E-Print Network [OSTI]

    Kirschner, Michael

    2008-01-01T23:59:59.000Z

    that it took the automotive industry until 2002 to unifycounterparts in the automotive industry on lessons learned,but predating it, the automotive industry started developing

  15. Productivity of the U.S. freight rail industry: a review of the past and prospects for the future

    E-Print Network [OSTI]

    Kriem, Youssef

    2011-01-01T23:59:59.000Z

    Productivity growth in the U.S. freight rail industry has slowed in recent years, raising the issue of the sustainability of the significant improvements achieved during the past three decades. Indeed, between 1979 and ...

  16. India's iron and steel industry: Productivity, energy efficiency and carbon emissions

    SciTech Connect (OSTI)

    Schumacher, Katja; Sathaye, Jayant

    1998-10-01T23:59:59.000Z

    Historical estimates of productivity growth in India's iron and steel sector vary from indicating an improvement to a decline in the sector's productivity. The variance may be traced to the time period of study, source of data for analysis, and type of indices and econometric specifications used for reporting productivity growth. The authors derive both growth accounting and econometric estimates of productivity growth for this sector. Their results show that over the observed period from 1973--74 to 1993--94 productivity declined by 1.71{percent} as indicated by the Translog index. Calculations of the Kendrick and Solow indices support this finding. Using a translog specification the econometric analysis reveals that technical progress in India's iron and steel sector has been biased towards the use of energy and material, while it has been capital and labor saving. The decline in productivity was caused largely by the protective policy regarding price and distribution of iron and steel as well as by large inefficiencies in public sector integrated steel plants. Will these trends continue into the future, particularly where energy use is concerned? Most likely they will not. The authors examine the current changes in structure and energy efficiency undergoing in the sector. Their analysis shows that with the liberalization of the iron and steel sector, the industry is rapidly moving towards world-best technology, which will result in fewer carbon emissions and more efficient energy use in existing and future plants.

  17. Assessments of long-term uranium supply availability

    E-Print Network [OSTI]

    Zaterman, Daniel R

    2009-01-01T23:59:59.000Z

    The future viability of nuclear power will depend on the long-term availability of uranium. A two-form uranium supply model was used to estimate the date at which peak production will occur. The model assumes a constant ...

  18. China’s Shipbuilding Industry Development: A Boost for Naval Ship Production?

    E-Print Network [OSTI]

    Collins, Gabe

    2010-01-01T23:59:59.000Z

    Jiangsu-based Rongsheng Heavy Industries is us- ing blockShipbuilding Industry. Yantai Raffles Mitsubishi Heavy

  19. Depleted uranium dioxide melting in cold crucible melter and production of granules from the melt for use in casks for spent nuclear fuel and radioactive wastes

    SciTech Connect (OSTI)

    Gotovchikov, Vitaly; Seredenko, V.A.; Shatalov, V.V.; Mironov, B.S.; Kaplenkov, V.N.; Seredenko, A.V.; Saranchin, V.K.; Shulgin, A.S.; Kalmakov, Danila [All-Russian Research Institute of Chemical Technology (ARRICT), Kashirskoe Shosse 33, Moscow 115230 (Russian Federation); Haire, M.J.; Forsberg, C.W. [Oak Ridge National Laboratory - ORNL, 1 Bethel Valley Rd, Oak Ridge, TN 37830 (United States)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: This paper describes the results of joint research program of Russian Research Institute of Chemical Technology and Oak Ridge National Laboratory to develop new materials for build spent nuclear fuel (SNF) storage, transport, and disposal casks using shielding made with depleted uranium dioxide (DUO{sub 2}) in a DUO{sub 2}-steel cermet or a DUCRETE with DUAGG (DUO{sub 2} aggregate) with selective additives in cement matrix. The preparation of DUO{sub 2} particles and aggregates for shielding could be produced from technologies that are extrapolated from the costly multi-step nuclear fuel pellet technologies. Melting the DUO{sub 2} and allowing it to freeze will produce a product near 100% theoretical density and assure that the product produces no volatile materials upon subsequent heating. Melting is a one step process that provides an opportunity to include additives in the DUO{sub 2} to modify its chemical or nuclear properties. The proposed work is directed to develop cold-wall induction heated melters (ICCM) for this specific application. Experiments on melting DUO{sub 2} were carried out in high frequency ICCM with cold crucible. It was experimentally proved an opportunity to produce molten DUO{sub 2} from mixed oxides (DU{sub 3}O{sub 8}) by reducing melting in ICCM. This will allow using DU{sub 3}O{sub 8} generated in direct conversion of depleted uranium hexafluoride as source material for melted and granulated DUO{sub 2} production. Experiments on the addition of alloying components - gadolinium oxide and others into DUO{sub 2} melt while in crucible to improve neutron and gamma radiation-shielding and operation properties of the final solids were carried out. (authors)

  20. Depleted uranium dioxide melting in cold crucible melter and production of granules from the melt for use in casks for spent nuclear fuel and radioactive wastes

    SciTech Connect (OSTI)

    Gotovchikov, V.T.; Seredenko, V.A.; Shatalov, V.V.; Mironov, B.S.; Kaplenkov, V.N.; Seredenko, A.V.; Saranchin, V.K.; Shulgin, A.S. [All-Russian Research Institute of Chemical Technology (ARRICT), Moscow (Russian Federation); Haire, M.J.; Forsberg, C.W. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

    2007-07-01T23:59:59.000Z

    This paper describes the results of a joint research program between the Russian Research Institute of Chemical Technology and Oak Ridge National Laboratory in the United States to develop new radiation shielding materials for use in the construction of casks for spent nuclear fuel (SNF) and radioactive wastes. Research and development is underway to develop SNF storage, transport, and disposal casks using shielding made with two new depleted uranium dioxide (DUO{sub 2}) materials: a DUO{sub 2}-steel cermet, and, DUCRETE with DUAGG (DUO{sub 2} aggregate). Melting the DUO{sub 2} and allowing it to freeze will produce a near 100% theoretical density product and assures that the product produces no volatile materials upon subsequent heating. Induction cold-crucible melters (ICCM) are being developed for this specific application. An ICCM is, potentially, a high throughput low-cost process. Schematics of a pilot facility were developed for the production of molten DUO{sub 2} from DU{sub 3}O{sub 8} to produce granules <1 mm in diameter in a continuous mode of operation. Thermodynamic analysis was conducted for uranium-oxygen system in the temperature range from 300 to 4000 K in various gas mediums. Temperature limits of stability for various uranium oxides were determined. Experiments on melting DUO{sub 2} were carried out in a high frequency ICCM in a cold crucible with a 120 mm in diameter. The microstructure of molten DUO{sub 2} was studied and lattice parameters were determined. It was experimentally proved, and validated by X-ray analysis, that an opportunity exists to produce molten DUO{sub 2} from mixed oxides (primarily DU{sub 3}O{sub 8}) by reduction melting in ICCM. This will allow using DU{sub 3}O{sub 8} directly to make DUO{sub 2}-a separate unit operation to produce UO{sub 2} feed material is not needed. Experiments were conducted concerning the addition of alloying components, gadolinium et al. oxides, into the DUO{sub 2} melt while in the crucible. These additives improve neutron and gamma radiation shielding and operation properties of the final solids. Cermet samples of 50 wt % DUO{sub 2} were produced. (authors)

  1. Clean Energy Manufacturing Initiative Industrial Efficiency and...

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

    Industrial Efficiency and Energy Productivity Video Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video Addthis Description Industrial...

  2. The End of Cheap Uranium

    E-Print Network [OSTI]

    Michael Dittmar

    2011-06-21T23:59:59.000Z

    Historic data from many countries demonstrate that on average no more than 50-70% of the uranium in a deposit could be mined. An analysis of more recent data from Canada and Australia leads to a mining model with an average deposit extraction lifetime of 10+- 2 years. This simple model provides an accurate description of the extractable amount of uranium for the recent mining operations. Using this model for all larger existing and planned uranium mines up to 2030, a global uranium mining peak of at most 58 +- 4 ktons around the year 2015 is obtained. Thereafter we predict that uranium mine production will decline to at most 54 +- 5 ktons by 2025 and, with the decline steepening, to at most 41 +- 5 ktons around 2030. This amount will not be sufficient to fuel the existing and planned nuclear power plants during the next 10-20 years. In fact, we find that it will be difficult to avoid supply shortages even under a slow 1%/year worldwide nuclear energy phase-out scenario up to 2025. We thus suggest that a worldwide nuclear energy phase-out is in order. If such a slow global phase-out is not voluntarily effected, the end of the present cheap uranium supply situation will be unavoidable. The result will be that some countries will simply be unable to afford sufficient uranium fuel at that point, which implies involuntary and perhaps chaotic nuclear phase-outs in those countries involving brownouts, blackouts, and worse.

  3. Beneficial Uses of Depleted Uranium

    SciTech Connect (OSTI)

    Brown, C. [U.S. Department of Energy, Germantown, MD (United States); Croff, A.G.; Haire, M. J. [Oak Ridge National Lab., TN (United States)

    1997-08-01T23:59:59.000Z

    Naturally occurring uranium contains 0.71 wt% {sup 235}U. In order for the uranium to be useful in most fission reactors, it must be enriched the concentration of the fissile isotope {sup 235}U must be increased. Depleted uranium (DU) is a co-product of the processing of natural uranium to produce enriched uranium, and DU has a {sup 235}U concentration of less than 0.71 wt%. In the United States, essentially all of the DU inventory is in the chemical form of uranium hexafluoride (UF{sub 6}) and is stored in large cylinders above ground. If this co-product material were to be declared surplus, converted to a stable oxide form, and disposed, the costs are estimated to be several billion dollars. Only small amounts of DU have at this time been beneficially reused. The U.S. Department of Energy (DOE) has begun the Beneficial Uses of DU Project to identify large-scale uses of DU and encourage its reuse for the primary purpose of potentially reducing the cost and expediting the disposition of the DU inventory. This paper discusses the inventory of DU and its rate of increase; DU disposition options; beneficial use options; a preliminary cost analysis; and major technical, institutional, and regulatory issues to be resolved.

  4. Effect of industrial by-products containing electron acceptors on mitigating methane emission during rice cultivation

    SciTech Connect (OSTI)

    Ali, Muhammad Aslam [Department of Environmental Science, Bangladesh Agricultural University, Mymensingh 2202 (Bangladesh); Lee, Chang Hoon [Functional Cereal Crop Research Division, National Institute of Crop Science, RDA, 1085, Naey-dong, Milyang (Korea, Republic of); Kim, Sang Yoon [Division of Applied Life Science, Graduate School (Brain Korea 21 Program), Gyeongsang National University, Jinju 660-701 (Korea, Republic of); Kim, Pil Joo [Division of Applied Life Science, Graduate School (Brain Korea 21 Program), Gyeongsang National University, Jinju 660-701 (Korea, Republic of); Institute of Agriculture and Life Sciences, Gyeongsang National University, Jinju 660-701 (Korea, Republic of)], E-mail: pjkim@gnu.ac.kr

    2009-10-15T23:59:59.000Z

    Three industrial by-products (fly ash, phosphogypsum and blast furnace slag), were evaluated for their potential re-use as soil amendments to reduce methane (CH{sub 4}) emission resulting from rice cultivation. In laboratory incubations, CH{sub 4} production rates from anoxic soil slurries were significantly reduced at amendment levels of 0.5%, 1%, 2% and 5% (wt wt{sup -1}), while observed CO{sub 2} production rates were enhanced. The level of suppression in methane production was the highest for phosphogypsum, followed by blast slag and then fly ash. In the greenhouse experiment, CH{sub 4} emission rates from the rice planted potted soils significantly decreased with the increasing levels (2-20 Mg ha{sup -1}) of the selected amendments applied, while rice yield simultaneously increased compared to the control treatment. At 10 Mg ha{sup -1} application level of the amendments, total seasonal CH{sub 4} emissions were reduced by 20%, 27% and 25%, while rice grain yields were increased by 17%, 15% and 23% over the control with fly ash, phosphogypsum, and blast slag amendments, respectively. The suppression of CH{sub 4} production rates as well as total seasonal CH{sub 4} flux could be due to the increased concentrations of active iron, free iron, manganese oxides, and sulfate in the amended soil, which acted as electron acceptors and controlled methanogens' activity by limiting substrates availability. Among the amendments, blast furnace slag and fly ash contributed mainly to improve the soil nutrients balance and increased the soil pH level towards neutral point, but soil acidity was developed with phosphogypsum application. Conclusively, blast slag among the selected amendments would be a suitable soil amendment for reducing CH{sub 4} emissions as well as sustaining rice productivity.

  5. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal Final Report - Part 3

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31T23:59:59.000Z

    Since 1998, The Pennsylvania State University successfully managed the Consortium for Premium Carbon Products from Coal (CPCPC), which was a vehicle for industry-driven research on the promotion, development, and transfer of innovative technologies on premium carbon products from coal to the U.S. industry. The CPCPC was an initiative led by Penn State, its cocharter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provided the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity continued under cooperative agreement No. DE-FC26-03NT41874, which started October 1, 2003 and ended December 31, 2010. The objective of the second agreement was to continue the successful operation of the CPCPC. The CPCPC enjoyed tremendous success with its organizational structure, which included Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC was its industry-led council that selected proposals submitted by CPCPC members to ensure CPCPC target areas had strong industrial support. CPCPC had 58 member companies and universities engaged over the 7-year period of this contract. Members were from 17 states and five countries outside of the U.S. During this period, the CPCPC Executive Council selected 46 projects for funding. DOE/CPCPC provided $3.9 million in funding or an average of $564,000 per year. The total project costs were $5.45 million with $1.5 million, or ~28% of the total, provided by the members as cost share. Total average project size was $118,000 with $85,900 provided by DOE/CPCPC. In addition to the research, technology transfer/outreach was a large component of CPCPC's activities. Efficient technology transfer was critical for the deployment of new technologies into the field. CPCPC organized and hosted technology transfer meetings, tours, and tutorials, attended outreach conferences and workshops to represent CPCPC and attract new members, prepared and distributed reports and publications, and developed and maintained a Web site. The second contract ended December 31, 2010, and it is apparent that CPCPC positively impacted the carbon industry and coal research. Statistics and information were compiled to provide a comprehensive account of the impact the consortium had and the beneficial outcomes of many of the individual projects. Project fact sheet, success stories, and other project information were prepared. Two topical reports, a Synthesis report and a Web report, were prepared detailing this information.

  6. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal Final Report - Part 4

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31T23:59:59.000Z

    Since 1998, The Pennsylvania State University successfully managed the Consortium for Premium Carbon Products from Coal (CPCPC), which was a vehicle for industry-driven research on the promotion, development, and transfer of innovative technologies on premium carbon products from coal to the U.S. industry. The CPCPC was an initiative led by Penn State, its cocharter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provided the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity continued under cooperative agreement No. DE-FC26-03NT41874, which started October 1, 2003 and ended December 31, 2010. The objective of the second agreement was to continue the successful operation of the CPCPC. The CPCPC enjoyed tremendous success with its organizational structure, which included Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC was its industry-led council that selected proposals submitted by CPCPC members to ensure CPCPC target areas had strong industrial support. CPCPC had 58 member companies and universities engaged over the 7-year period of this contract. Members were from 17 states and five countries outside of the U.S. During this period, the CPCPC Executive Council selected 46 projects for funding. DOE/CPCPC provided $3.9 million in funding or an average of $564,000 per year. The total project costs were $5.45 million with $1.5 million, or {approx}28% of the total, provided by the members as cost share. Total average project size was $118,000 with $85,900 provided by DOE/CPCPC. In addition to the research, technology transfer/outreach was a large component of CPCPC's activities. Efficient technology transfer was critical for the deployment of new technologies into the field. CPCPC organized and hosted technology transfer meetings, tours, and tutorials, attended outreach conferences and workshops to represent CPCPC and attract new members, prepared and distributed reports and publications, and developed and maintained a Web site. The second contract ended December 31, 2010, and it is apparent that CPCPC positively impacted the carbon industry and coal research. Statistics and information were compiled to provide a comprehensive account of the impact the consortium had and the beneficial outcomes of many of the individual projects. Project fact sheet, success stories, and other project information were prepared. Two topical reports, a Synthesis report and a Web report, were prepared detailing this information.

  7. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal Final Report - Part 2

    SciTech Connect (OSTI)

    Miller, Bruce; Winton, Shea

    2010-12-31T23:59:59.000Z

    Since 1998, The Pennsylvania State University successfully managed the Consortium for Premium Carbon Products from Coal (CPCPC), which was a vehicle for industry-driven research on the promotion, development, and transfer of innovative technologies on premium carbon products from coal to the U.S. industry. The CPCPC was an initiative led by Penn State, its cocharter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provided the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity continued under cooperative agreement No. DE-FC26-03NT41874, which started October 1, 2003 and ended December 31, 2010. The objective of the second agreement was to continue the successful operation of the CPCPC. The CPCPC enjoyed tremendous success with its organizational structure, which included Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC was its industry-led council that selected proposals submitted by CPCPC members to ensure CPCPC target areas had strong industrial support. CPCPC had 58 member companies and universities engaged over the 7-year period of this contract. Members were from 17 states and five countries outside of the U.S. During this period, the CPCPC Executive Council selected 46 projects for funding. DOE/CPCPC provided $3.9 million in funding or an average of $564,000 per year. The total project costs were $5.45 million with $1.5 million, or ~28% of the total, provided by the members as cost share. Total average project size was $118,000 with $85,900 provided by DOE/CPCPC. In addition to the research, technology transfer/outreach was a large component of CPCPC's activities. Efficient technology transfer was critical for the deployment of new technologies into the field. CPCPC organized and hosted technology transfer meetings, tours, and tutorials, attended outreach conferences and workshops to represent CPCPC and attract new members, prepared and distributed reports and publications, and developed and maintained a Web site. The second contract ended December 31, 2010, and it is apparent that CPCPC positively impacted the carbon industry and coal research. Statistics and information were compiled to provide a comprehensive account of the impact the consortium had and the beneficial outcomes of many of the individual projects. Project fact sheet, success stories, and other project information were prepared. Two topical reports, a Synthesis report and a Web report, were prepared detailing this information.

  8. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal Final Report - Part 5

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31T23:59:59.000Z

    Since 1998, The Pennsylvania State University successfully managed the Consortium for Premium Carbon Products from Coal (CPCPC), which was a vehicle for industry-driven research on the promotion, development, and transfer of innovative technologies on premium carbon products from coal to the U.S. industry. The CPCPC was an initiative led by Penn State, its cocharter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provided the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity continued under cooperative agreement No. DE-FC26-03NT41874, which started October 1, 2003 and ended December 31, 2010. The objective of the second agreement was to continue the successful operation of the CPCPC. The CPCPC enjoyed tremendous success with its organizational structure, which included Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC was its industry-led council that selected proposals submitted by CPCPC members to ensure CPCPC target areas had strong industrial support. CPCPC had 58 member companies and universities engaged over the 7-year period of this contract. Members were from 17 states and five countries outside of the U.S. During this period, the CPCPC Executive Council selected 46 projects for funding. DOE/CPCPC provided $3.9 million in funding or an average of $564,000 per year. The total project costs were $5.45 million with $1.5 million, or {approx}28% of the total, provided by the members as cost share. Total average project size was $118,000 with $85,900 provided by DOE/CPCPC. In addition to the research, technology transfer/outreach was a large component of CPCPC's activities. Efficient technology transfer was critical for the deployment of new technologies into the field. CPCPC organized and hosted technology transfer meetings, tours, and tutorials, attended outreach conferences and workshops to represent CPCPC and attract new members, prepared and distributed reports and publications, and developed and maintained a Web site. The second contract ended December 31, 2010, and it is apparent that CPCPC positively impacted the carbon industry and coal research. Statistics and information were compiled to provide a comprehensive account of the impact the consortium had and the beneficial outcomes of many of the individual projects. Project fact sheet, success stories, and other project information were prepared. Two topical reports, a Synthesis report and a Web report, were prepared detailing this information.

  9. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal Final Report - Part 1

    SciTech Connect (OSTI)

    Miller, Bruce; Winton, Shea

    2010-12-31T23:59:59.000Z

    Since 1998, The Pennsylvania State University successfully managed the Consortium for Premium Carbon Products from Coal (CPCPC), which was a vehicle for industry-driven research on the promotion, development, and transfer of innovative technologies on premium carbon products from coal to the U.S. industry. The CPCPC was an initiative led by Penn State, its cocharter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provided the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity continued under cooperative agreement No. DE-FC26-03NT41874, which started October 1, 2003 and ended December 31, 2010. The objective of the second agreement was to continue the successful operation of the CPCPC. The CPCPC enjoyed tremendous success with its organizational structure, which included Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC was its industry-led council that selected proposals submitted by CPCPC members to ensure CPCPC target areas had strong industrial support. CPCPC had 58 member companies and universities engaged over the 7-year period of this contract. Members were from 17 states and five countries outside of the U.S. During this period, the CPCPC Executive Council selected 46 projects for funding. DOE/CPCPC provided $3.9 million in funding or an average of $564,000 per year. The total project costs were $5.45 million with $1.5 million, or ~28% of the total, provided by the members as cost share. Total average project size was $118,000 with $85,900 provided by DOE/CPCPC. In addition to the research, technology transfer/outreach was a large component of CPCPC's activities. Efficient technology transfer was critical for the deployment of new technologies into the field. CPCPC organized and hosted technology transfer meetings, tours, and tutorials, attended outreach conferences and workshops to represent CPCPC and attract new members, prepared and distributed reports and publications, and developed and maintained a Web site. The second contract ended December 31, 2010, and it is apparent that CPCPC positively impacted the carbon industry and coal research. Statistics and information were compiled to provide a comprehensive account of the impact the consortium had and the beneficial outcomes of many of the individual projects. Project fact sheet, success stories, and other project information were prepared. Two topical reports, a Synthesis report and a Web report, were prepared detailing this information.

  10. The socioeconomic effects of uranium development in south Texas: a human ecological approach

    E-Print Network [OSTI]

    Hopkins, Pamela Chris

    1982-01-01T23:59:59.000Z

    energy sources are solar, biomass, geothermal, coal, oil shale, and nuclear power. This last alternative re- quires the extraction and use of uranium and, although nuclear power is controversial, projections indicate that its use could be significant... defense and other industries. A review of national energy supply and demand pro- jections indicates that substantial production of likely alternatives to nuclear energy such as fuel from oil shale The style followed is that currently used in Rural...

  11. Electrochemical method of producing eutectic uranium alloy and apparatus

    DOE Patents [OSTI]

    Horton, James A. (Livermore, CA); Hayden, H. Wayne (Oakridge, TN)

    1995-01-01T23:59:59.000Z

    An apparatus and method for continuous production of liquid uranium alloys through the electrolytic reduction of uranium chlorides. The apparatus includes an electrochemical cell formed from an anode shaped to form an electrolyte reservoir, a cathode comprising a metal, such as iron, capable of forming a eutectic uranium alloy having a melting point less than the melting point of pure uranium, and molten electrolyte in the reservoir comprising a chlorine or fluorine containing salt and uranium chloride. The method of the invention produces an eutectic uranium alloy by creating an electrolyte reservoir defined by a container comprising an anode, placing an electrolyte in the reservoir, the electrolyte comprising a chlorine or fluorine containing salt and uranium chloride in molten form, positioning a cathode in the reservoir where the cathode comprises a metal capable of forming an uranium alloy having a melting point less than the melting point of pure uranium, and applying a current between the cathode and the anode.

  12. Recycling of the product of thermal inertization of cement-asbestos for various industrial applications

    SciTech Connect (OSTI)

    Gualtieri, Alessandro F., E-mail: alessandro.gualtieri@unimore.it [Dipartimento di Scienze della Terra, Universita di Modena e R.E., Via S. Eufemia 19, I-41100 Modena (Italy); Giacobbe, Carlotta; Sardisco, Lorenza; Saraceno, Michele [Dipartimento di Scienze della Terra, Universita di Modena e R.E., Via S. Eufemia 19, I-41100 Modena (Italy); Lassinantti Gualtieri, Magdalena [Dipartimento Ingegneria dei Materiali e dell'Ambiente, Universita di Modena e Reggio Emilia, Via Vignolese 905/a, I-41100 Modena (Italy); Lusvardi, Gigliola [Dipartimento di Chimica, Universita degli Studi di Modena e Reggio Emilia, Via G. Campi 183, I-41100 Modena (Italy); Cavenati, Cinzia; Zanatto, Ivano [ZETADI S.r.l., Via dell'Artigianato 10, Ferno (Italy)

    2011-01-15T23:59:59.000Z

    Recycling of secondary raw materials is a priority of waste handling in the countries of the European community. A potentially important secondary raw material is the product of the thermal transformation of cement-asbestos, produced by prolonged annealing at 1200-1300 {sup o}C. The product is chemically comparable to a Mg-rich clinker. Previous work has assured the reliability of the transformation process. The current challenge is to find potential applications as secondary raw material. Recycling of thermally treated asbestos-containing material (named KRY.AS) in traditional ceramics has already been studied with successful results. The results presented here are the outcome of a long termed project started in 2005 and devoted to the recycling of this secondary raw materials in various industrial applications. KRY.AS can be added in medium-high percentages (10-40 wt%) to commercial mixtures for the production of clay bricks, rock-wool glasses for insulation as well as Ca-based frits and glass-ceramics for the production of ceramic tiles. The secondary raw material was also used for the synthesis of two ceramic pigments; a green uvarovite-based pigment [Ca{sub 3}Cr{sub 2}(SiO{sub 4}){sub 3}] and a pink malayaite-based pigment [Ca(Sn,Cr)SiO{sub 5}]. The latter is especially interesting as a substitute for cadmium-based pigments. This work also shows that KRY.AS can replace standard fillers in polypropylene plastics without altering the properties of the final product. For each application, a description and relevant results are presented and discussed.

  13. Characterization of the bacterial metagenome in an industrial algae bioenergy production system

    SciTech Connect (OSTI)

    Huang, Shi [Chinese Academy of Sciences; Fulbright, Scott P [Colorado State University; Zeng, Xiaowei [Chinese Academy of Sciences; Yates, Tracy [Solix Biofuels; Wardle, Greg [Solix Biofuels; Chisholm, Stephen T [Colorado State University; Xu, Jian [Chinese Academy of Sciences; Lammers, Peter [New Mexico State University

    2011-03-16T23:59:59.000Z

    Cultivation of oleaginous microalgae for fuel generally requires growth of the intended species to the maximum extent supported by available light. The presence of undesired competitors, pathogens and grazers in cultivation systems will create competition for nitrate, phosphate, sulfate, iron and other micronutrients in the growth medium and potentially decrease microalgal triglyceride production by limiting microalgal health or cell density. Pathogenic bacteria may also directly impact the metabolism or survival of individual microalgal cells. Conversely, symbiotic bacteria that enhance microalgal growth may also be present in the system. Finally, the use of agricultural and municipal wastes as nutrient inputs for microalgal production systems may lead to the introduction and proliferation of human pathogens or interfere with the growth of bacteria with beneficial effects on system performance. These considerations underscore the need to understand bacterial community dynamics in microalgal production systems in order to assess microbiome effects on microalgal productivity and pathogen risks. Here we focus on the bacterial component of microalgal production systems and describe a pipeline for metagenomic characterization of bacterial diversity in industrial cultures of an oleaginous alga, Nannochloropsis salina. Environmental DNA was isolated from 12 marine algal cultures grown at Solix Biofuels, a region of the 16S rRNA gene was amplified by PCR, and 16S amplicons were sequenced using a 454 automated pyrosequencer. The approximately 70,000 sequences that passed quality control clustered into 53,950 unique sequences. The majority of sequences belonged to thirteen phyla. At the genus level, sequences from all samples represented 169 different genera. About 52.94% of all sequences could not be identified at the genus level and were classified at the next highest possible resolution level. Of all sequences, 79.92% corresponded to 169 genera and 70 other taxa. We apply a principal component analysis across the initial sample set to draw correlations between sample variables and changes in microbiome populations.

  14. URANIUM IN ALKALINE ROCKS

    E-Print Network [OSTI]

    Murphy, M.

    2011-01-01T23:59:59.000Z

    Greenland," in Uranium Exploration Geology, Int. AtomicMigration of Uranium and Thorium—Exploration Significance,"interesting for future uranium exploration. The c r i t e r

  15. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Oak Ridge Gaseous Diffusion Plant Site

    SciTech Connect (OSTI)

    Not Available

    1991-09-01T23:59:59.000Z

    In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) technology, with the near-term goal to provide the necessary information to make a deployment decision by November 1992. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. A programmatic document for use in screening DOE sites to locate the U-AVLIS production plant was developed and implemented in two parts (Wolsko et al. 1991). The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were then subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the ORGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use, socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3. Following the site description and additional data requirements, Sec. 4 provides a short, qualitative assessment of potential environmental issues. 37 refs., 20 figs., 18 tabs.

  16. Survey of lands held for uranium exploration, development, and production in fourteen western states in the six-month period ending June 30, 1980

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    The statistics set forth for the period covered in this report are based on data gathered from records available to the public. The county records of mining claim locations, reports of state and federal land offices, and commercial reporting services furnish the data for this report. Accordingly, if any fee land has been acquired in a private transaction not entered into a public record or report, that land transaction will not be accounted for in this report. Manpower is not available to survey, acquire, and evaluate data from each available source in each reporting period. Therefore, in any given report, the figures quoted for one or more land categories in a given state may be identical to the figures shown in earlier reports even though some changes probably have occurred. Such changes will be shown on subsequent reports. The figures used for acreage controlled at the beginning of the calendar year are those published for that date in Statistical Data of the Uranium Industry GJ0-100 published and distributed by the Grand Junction Office of the Department of Energy.

  17. Fingerprinting Uranium | EMSL

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

    Fingerprinting Uranium Fingerprinting Uranium Researchers show how to use x-rays to identify mobile, stationary forms of atomic pollutant PNNL and University of North Texas...

  18. Methane Digesters and Biogas Recovery - Masking the Environmental Consequences of Industrial Concentrated Livestock Production

    E-Print Network [OSTI]

    Di Camillo, Nicole G.

    2011-01-01T23:59:59.000Z

    Energy Production . C.Benefits and Renewable Energy Production One source ofsource of renewable energy production from such facilities.

  19. ISSUANCE 2015-06-25: Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Test Procedures for Residential and Commercial Water Heaters; Correction

    Broader source: Energy.gov [DOE]

    Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Test Procedures for Residential and Commercial Water Heaters; Correction

  20. Impact of product design choices on supply chain performance in the notebook computer industry

    E-Print Network [OSTI]

    Sailer, Chad (Chad Darren)

    2010-01-01T23:59:59.000Z

    Intel Corporation is the world's leading manufacturer of processors for personal computers. As the company strives to maintain its leadership position in this industry, it identifies significant trends in the industry and ...

  1. Product strategy in response to technological innovation in the semiconductor test industry

    E-Print Network [OSTI]

    Lin, Robert W. (Robert Wei-Pang), 1976-

    2004-01-01T23:59:59.000Z

    After the market boom of 2000 in the semiconductor industry changed significantly. The changes included stricter limits on capital cost spending, and the increased propensity of the industry to outsource the manufacturing ...

  2. Estimates of future regional heavy oil production at three production rates--background information for assessing effects in the US refining industry

    SciTech Connect (OSTI)

    Olsen, D.K.

    1993-07-01T23:59:59.000Z

    This report is one of a series of publications from a project considering the feasibility of increasing domestic heavy oil (10{degree} to 20{degree} API gravity inclusive) production being conducted for the US Department of Energy. The report includes projections of future heavy oil production at three production levels: 900,000; 500,000; and 300,000 BOPD above the current 1992 heavy oil production level of 750,000 BOPD. These free market scenario projections include time frames and locations. Production projections through a second scenario were developed to examine which heavy oil areas would be developed if significant changes in the US petroleum industry occurred. The production data helps to define the possible constraints (impact) of increased heavy oil production on the US refining industry (the subject of a future report). Constraints include a low oil price and low rate of return. Heavy oil has high production, transportation, and refining cost per barrel as compared to light oil. The resource is known, but the right mix of technology and investment is required to bring about significant expansion of heavy oil production in the US.

  3. Bioremediation of uranium contaminated soils and wastes

    SciTech Connect (OSTI)

    Francis, A.J.

    1998-12-31T23:59:59.000Z

    Contamination of soils, water, and sediments by radionuclides and toxic metals from uranium mill tailings, nuclear fuel manufacturing and nuclear weapons production is a major concern. Studies of the mechanisms of biotransformation of uranium and toxic metals under various microbial process conditions has resulted in the development of two treatment processes: (1) stabilization of uranium and toxic metals with reduction in waste volume and (2) removal and recovery of uranium and toxic metals from wastes and contaminated soils. Stabilization of uranium and toxic metals in wastes is accomplished by exploiting the unique metabolic capabilities of the anaerobic bacterium, Clostridium sp. The radionuclides and toxic metals are solubilized by the bacteria directly by enzymatic reductive dissolution, or indirectly due to the production of organic acid metabolites. The radionuclides and toxic metals released into solution are immobilized by enzymatic reductive precipitation, biosorption and redistribution with stable mineral phases in the waste. Non-hazardous bulk components of the waste volume. In the second process uranium and toxic metals are removed from wastes or contaminated soils by extracting with the complexing agent citric acid. The citric-acid extract is subjected to biodegradation to recover the toxic metals, followed by photochemical degradation of the uranium citrate complex which is recalcitrant to biodegradation. The toxic metals and uranium are recovered in separate fractions for recycling or for disposal. The use of combined chemical and microbiological treatment process is more efficient than present methods and should result in considerable savings in clean-up and disposal costs.

  4. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, J.P.

    1992-03-17T23:59:59.000Z

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

  5. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, John P. (Downers Grove, IL)

    1992-01-01T23:59:59.000Z

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

  6. Composition of the U.S. DOE Depleted Uranium Inventory

    E-Print Network [OSTI]

    Concentration Of Less

    about 2.75 wt% U-235. For further enrichment, the material was shipped to the Oak Ridge and Portsmouth plants. In addition to natural uranium, also uranium recycled from spent fuel was fed into the Paducah enrichment cascade (Table 2 and Fig. 2). The recycled uranium introduced various isotopes not found in natural uranium into the cascade: fission products, such as Technetium-99; transuranics, such as Neptunium-237 and Plutonium-239; and the artificial uranium isotope of Uranium-236. The spent fuel, from which uranium was recycled, originated from the Hanford and Savannah River military plutonium production reactors. This uranium was recycled, although its assay of U-235 was somewhat lower than in natural uranium (Table 2). This obviously must be seen in the context of the Cold War era, when uranium was a scarce resource. Due to the low burn-up of the military reactors, concentrations of artificial U-236 are comparatively low in this recycled uranium. The recycled uranium represents

  7. Compilation of Requirements for Safe Handling of Fluorine and Fluorine-Containing Products of Uranium Hexafluoride Conversion

    SciTech Connect (OSTI)

    Ferrada, J.J.

    2000-04-03T23:59:59.000Z

    Public Law (PL) 105-204 requires the U.S. Department of Energy to develop a plan for inclusion in the fiscal year 2000 budget for conversion of the Department's stockpile of depleted uranium hexafluoride (DUF{sub 6}) to a more stable form over an extended period. The conversion process into a more stable form will produce fluorine compounds (e.g., elemental fluorine or hydrofluoric acid) that need to be handled safely. This document compiles the requirements necessary to handle these materials within health and safety standards, which may apply in order to ensure protection of the environment and the safety and health of workers and the public. Fluorine is a pale-yellow gas with a pungent, irritating odor. It is the most reactive nonmetal and will react vigorously with most oxidizable substances at room temperature, frequently with ignition. Fluorine is a severe irritant of the eyes, mucous membranes, skin, and lungs. In humans, the inhalation of high concentrations causes laryngeal spasm and broncospasms, followed by the delayed onset of pulmonary edema. At sublethal levels, severe local irritation and laryngeal spasm will preclude voluntary exposure to high concentrations, unless the individual is trapped or incapacitated. A blast of fluorine gas on the shaved skin of a rabbit causes a second degree burn. Lower concentrations cause severe burns of insidious onset, resulting in ulceration, similar to the effects produced by hydrogen fluoride. Hydrofluoric acid is a colorless, fuming liquid or gas with a pungent odor. It is soluble in water with release of heat. Ingestion of an estimated 1.5 grams produced sudden death without gross pathological damage. Repeated ingestion of small amounts resulted in moderately advanced hardening of the bones. Contact of skin with anhydrous liquid produces severe burns. Inhalation of AHA or aqueous hydrofluoric acid mist or vapors can cause severe respiratory tract irritation that may be fatal. Based on the extreme chemical properties of these chemicals as noted above, fluorine or fluorine compounds must be handled appropriately within the boundaries of many safety requirements for the protection of the environment and the public. This report analyzes the safety requirements that regulatory agencies have issued to handle fluorine or fluorine compounds and lists them in Table 1. Table 1 lists the source of the requirements, the specific section of the source document, and a brief description of the requirements.

  8. Uranium mill tailings and radon

    SciTech Connect (OSTI)

    Hanchey, L A

    1981-01-01T23:59:59.000Z

    The major health hazard from uranium mill tailings is presumed to be respiratory cancer resulting from the inhalation of radon daughter products. A review of studies on inhalation of radon and its daughters indicates that the hazard from the tailings is extremely small. If the assumptions used in the studies are correct, one or two people per year in the US may develop cancer as a result of radon exhaled from all the Uranium Mill Tailings Remedial Action Program sites. The remedial action should reduce the hazard from the tailings by a factor of about 100.

  9. Manufacturing industry challenges and responses to EU, California, and other product-targeted environmental regulations

    E-Print Network [OSTI]

    Kirschner, Michael

    2008-01-01T23:59:59.000Z

    and manage their “product lifecycle process” has now comePRELIMINARY DRAFT The Product Lifecycle Process In order toproducts called the “product lifecycle process”. Often a “

  10. Conversion and Blending Facility highly enriched uranium to low enriched uranium as uranyl nitrate hexahydrate. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-07-05T23:59:59.000Z

    This Conversion and Blending Facility (CBF) will have two missions: (1) convert HEU materials to pure HEU uranyl nitrate (UNH) and (2) blend pure HEU UNH with depleted and natural UNH to produce HEU UNH crystals. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. To the extent practical, the chemical and isotopic concentrations of blended LEU product will be held within the specifications required for LWR fuel. Such blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry. Otherwise, blended LEU Will be produced as a waste suitable for storage or disposal.

  11. Scrap uranium recycling via electron beam melting

    SciTech Connect (OSTI)

    McKoon, R.

    1993-11-01T23:59:59.000Z

    A program is underway at the Lawrence Livermore National Laboratory (LLNL) to recycle scrap uranium metal. Currently, much of the material from forging and machining processes is considered radioactive waste and is disposed of by oxidation and encapsulation at significant cost. In the recycling process, uranium and uranium alloys in various forms will be processed by electron beam melting and continuously cast into ingots meeting applicable specifications for virgin material. Existing vacuum processing facilities at LLNL are in compliance with all current federal and state environmental, safety and health regulations for the electron beam melting and vaporization of uranium metal. One of these facilities has been retrofitted with an auxiliary electron beam gun system, water-cooled hearth, crucible and ingot puller to create an electron beam melt furnace. In this furnace, basic process R&D on uranium recycling will be performed with the goal of eventual transfer of this technology to a production facility.

  12. The Taiwanese Notebook Computer Production Network in China: Implication for Upgrading of the Chinese Electronics Industry

    E-Print Network [OSTI]

    Yang, Yungkai

    2006-01-01T23:59:59.000Z

    Learning the Technology of Electronics. ” World Development,Underdevelopment of Malaysian Electronics. ” Paper for the 3Series No. 15. China Electronics Industry Yearbook, 2004.

  13. LITERATURE REVIEW ON THE SORPTION OF PLUTONIUM, URANIUM, NEPTUNIUM, AMERICIUM AND TECHNETIUM TO CORROSION PRODUCTS ON WASTE TANK LINERS

    SciTech Connect (OSTI)

    Li, D.; Kaplan, D.

    2012-02-29T23:59:59.000Z

    The Savannah River Site (SRS) has conducted performance assessment (PA) calculations to determine the risk associated with closing liquid waste tanks. The PA estimates the risk associated with a number of scenarios, making various assumptions. Throughout all of these scenarios, it is assumed that the carbon-steel tank liners holding the liquid waste do not sorb the radionuclides. Tank liners have been shown to form corrosion products, such as Fe-oxyhydroxides (Wiersma and Subramanian 2002). Many corrosion products, including Fe-oxyhydroxides, at the high pH values of tank effluent, take on a very strong negative charge. Given that many radionuclides may have net positive charges, either as free ions or complexed species, it is expected that many radionuclides will sorb to corrosion products associated with tank liners. The objective of this report was to conduct a literature review to investigate whether Pu, U, Np, Am and Tc would sorb to corrosion products on tank liners after they were filled with reducing grout (cementitious material containing slag to promote reducing conditions). The approach was to evaluate radionuclides sorption literature with iron oxyhydroxide phases, such as hematite ({alpha}-Fe{sub 2}O{sub 3}), magnetite (Fe{sub 3}O{sub 4}), goethite ({alpha}-FeOOH) and ferrihydrite (Fe{sub 2}O{sub 3} {center_dot} 0.5H{sub 2}O). The primary interest was the sorption behavior under tank closure conditions where the tanks will be filled with reducing cementitious materials. Because there were no laboratory studies conducted using site specific experimental conditions, (e.g., high pH and HLW tank aqueous and solid phase chemical conditions), it was necessary to extend the literature review to lower pH studies and noncementitious conditions. Consequently, this report relied on existing lower pH trends, existing geochemical modeling, and experimental spectroscopic evidence conducted at lower pH levels. The scope did not include evaluating the appropriateness of K{sub d} values for the Fe-oxyhydroxides, but instead to evaluate whether it is a conservative assumption to exclude this sorption process of radionuclides onto tank liner corrosion products in the PA model. This may identify another source for PA conservatism since the modeling did not consider any sorption by the tank liner.

  14. Uranium Leasing Program: Program Summary | Department of Energy

    Energy Savers [EERE]

    then lease them to private industry for mineral exploration and for development and mining of uranium and vanadium ore. A total of 25,000 acres of land in southwestern Colorado,...

  15. WOSMIP II- Workshop on Signatures of Medical and Industrial Isotope Production

    SciTech Connect (OSTI)

    Matthews, Murray; Achim, Pascal; Auer, M.; Bell, Randy; Bowyer, Ted W.; Braekers, Damien; Bradley, Ed; Briyatmoko, Budi; Berglund, Helena; Camps, Johan; Carranza, Eduardo C.; Carty, Fitz; DeCaire, Richard; Deconninck, Benoit; DeGeer, Lars E.; Druce, Michael; Friese, Judah I.; Hague, Robert; Hoffman, Ian; Khrustalev, Kirill; Lucas, John C.; Mattassi, G.; Mattila, Aleski; Nava, Elisabetta; Nikkinin, Mika; Papastefanou, Constantin; Piefer, Gregory R.; Quintana, Eduardo; Ross, Ole; Rotty, Michel; Sabzian, Mohammad; Saey, Paul R.; Sameh, A. A.; Safari, M.; Schoppner, Michael; Siebert, Petra; Unger, Klaus K.; Vargas, Albert

    2011-11-01T23:59:59.000Z

    Medical and industrial fadioisotopes are fundamental tools used in science, medicine and industry with an ever expanding usage in medical practice where their availability is vital. Very sensitive environmental radionuclide monitoring networks have been developed for nuclear-security-related monitoring [particularly Comprehensive Test-Ban-Treaty (CTBT) compliance verification] and are now operational.

  16. Establishment of an Industry-Driven Consortium Focused on Improving the Production Performance of Domestic Stripper Wells

    SciTech Connect (OSTI)

    Joel Morrison; Sharon Elder

    2006-01-24T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the sixth quarterly technical progress report for the SWC. Key activities for this reporting period included: (1) Organized and hosted two technology transfer meetings; (2) Collaborated with the Pennsylvania Oil and Gas Association (POGAM) to host a Natural Gas Outlook conference in Pittsburgh, PA; (3) Provided a SWC presentation at the Interstate Oil and Gas Compact Commission (IOGCC) meeting in Jackson Hole, WY; and (4) Completed and released a stripper well industry documentary entitled: ''Independent Oil: Rediscovering America's Forgotten Wells''.

  17. Effects of various uranium leaching procedures on soil: Short-term vegetation growth and physiology. Progress report, April 1994

    SciTech Connect (OSTI)

    Edwards, N.T.

    1994-08-01T23:59:59.000Z

    Significant volumes of soil containing elevated levels of uranium exist in the eastern United States. The contamination resulted from the development of the nuclear industry in the United States requiring a large variety of uranium products. The contaminated soil poses a collection and disposal problem of a magnitude that justifies the development of decontamination methods. Consequently, the Department of Energy (DOE) Office of Technology Development formed the Uranium Soils Integrated Demonstration (USID) program to address the problem. The fundamental goal of the USID task group has been the selective extraction/leaching or removal of uranium from soil faster, cheaper, and safer than what can be done using current conventional technologies. The objective is to selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics and without generating waste that is difficult to manage and/or dispose of. However, procedures developed for removing uranium from contaminated soil have involved harsh chemical treatments that affect the physicochemical properties of the soil. The questions are (1) are the changes in soil properties severe enough to destroy the soil`s capacity to support and sustain vegetation growth and survival? and (2) what amendments might be made to the leached soil to return it to a reasonable vegetation production capacity? This study examines the vegetation-support capacity of soil that had been chemically leached to remove uranium. The approach is to conduct short-term germination and phytotoxicity tests for evaluating soils after they are subjected to various leaching procedures followed by longer term pot studies on successfully leached soils that show the greatest capacity to support plant growth. This report details the results from germination and short-term phytotoxicity testing of soils that underwent a variety of leaching procedures at the bench scale at ORNL and at the pilot plant at Fernald.

  18. Geological and geochemical aspects of uranium deposits. A selected, annotated bibliography

    SciTech Connect (OSTI)

    Garland, P.A.; Thomas, J.M.; Brock, M.L.; Daniel, E.W. (comps.)

    1980-06-01T23:59:59.000Z

    A bibliography of 479 references encompassing the fields of uranium and thorium geochemistry and mineralogy, geology of uranium deposits, uranium mining, and uranium exploration techniques has been compiled by the Ecological Sciences Information Center of Oak Ridge National Laboratory. The bibliography was produced for the National Uranium Resource Evaluation Program, which is funded by the Grand Junction Office of the Department of Energy. The references contained in the bibliography have been divided into the following eight subject categories: (1) geology of deposits, (2) geochemistry, (3) genesis O deposits, (4) exploration, (5) mineralogy, (6) uranium industry, (7) reserves and resources, and (8) geology of potential uranium-bearing areas. All categories specifically refer to uranium and thorium; the last category contains basic geologic information concerning areas which the Grand Junction Office feels are particularly favorable for uranium deposition. The references are indexed by author, geographic location, quadrangle name, geoformational feature, taxonomic name, and keyword.

  19. Electrolytic process for preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A. (Knoxville, TN)

    1990-01-01T23:59:59.000Z

    An electrolytic process for making uranium from uranium oxide using Cl.sub.2 anode product from an electrolytic cell to react with UO.sub.2 to form uranium chlorides. The chlorides are used in low concentrations in a melt comprising fluorides and chlorides of potassium, sodium and barium in the electrolytic cell. The electrolysis produces Cl.sub.2 at the anode that reacts with UO.sub.2 in the feed reactor to form soluble UCl.sub.4, available for a continuous process in the electrolytic cell, rather than having insoluble UO.sub.2 fouling the cell.

  20. Conversion and Blending Facility highly enriched uranium to low enriched uranium as metal. Revision 1

    SciTech Connect (OSTI)

    NONE

    1995-07-05T23:59:59.000Z

    The mission of this Conversion and Blending Facility (CBF) will be to blend surplus HEU metal and alloy with depleted uranium metal to produce an LEU product. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal.

  1. Manufacturing industry challenges and responses to EU, California, and other product-targeted environmental regulations

    E-Print Network [OSTI]

    Kirschner, Michael

    2008-01-01T23:59:59.000Z

    directive (2002/96/EC, “WEEE” ) the EU expanded its scope ofe-waste”) regulation like WEEE, decided to take matters intake its cues from RoHS and WEEE. While industry lobbying

  2. Productivity and competition in the U.S. trucking industry since deregulation

    E-Print Network [OSTI]

    Parming, Veiko Paul

    2013-01-01T23:59:59.000Z

    In 1980 Congress passed the Motor Carrier Act, substantially liberating trucking carriers from a federal regulatory structure that had exercised broad economic control over the industry for over four decades. Changes in ...

  3. Supply chain management for fast-moving products in the electronic industry

    E-Print Network [OSTI]

    Zafiriou, Konstantinos F

    2006-01-01T23:59:59.000Z

    The objective of this Thesis was to strategically redesign and transform the supply chain of a series of detonators in a leading Company serving the oil and gas industry. The scope of the Thesis included data gathering and ...

  4. The Taiwanese Notebook Computer Production Network in China: Implication for Upgrading of the Chinese Electronics Industry

    E-Print Network [OSTI]

    Yang, Yungkai

    2006-01-01T23:59:59.000Z

    manufacturing in China saves some cost for the Taiwanese NBin China for Taiwanese NB industry---cost incentives? ”in China saves about 1% of component costs (6 U.S. dollars)

  5. Combining Optimization and Simulation for Strategic and Operational Industrial Gas Production and Distribution

    E-Print Network [OSTI]

    Linderoth, Jeffrey T.

    ) are typically produced in bulk through a cryogenic air separation process. Air Products plans its production Engineering Bethlehem, PA {wag3,jtl3,jis6}@lehigh.edu Peter Connard Jim Hutton Air Products and Chemicals, Inc availability. The paper concludes with a case study using data from Air Products. Keywords: Enterprise

  6. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

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

    1991-12-31T23:59:59.000Z

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

  7. Depleted Uranium Technical Brief

    E-Print Network [OSTI]

    Depleted Uranium Technical Brief United States Environmental Protection Agency Office of Air and Radiation Washington, DC 20460 EPA-402-R-06-011 December 2006 #12;#12;Depleted Uranium Technical Brief EPA of Radiation and Indoor Air Radiation Protection Division ii #12;iii #12;FOREWARD The Depleted Uranium

  8. Green-IT: Green Initiative for Energy Efficient, Eco-products in the Construction Industry

    E-Print Network [OSTI]

    Bhar, R.

    2008-01-01T23:59:59.000Z

    GREEN-IT aims to introduce a product database [e2pilot] in the European building construction product sector and accelerate the EU market transformation towards regulated Energy Performance of Buildings....

  9. Sustainability in the product cycle : adopting a shared standard for the apparel industry

    E-Print Network [OSTI]

    Hartley, Alice C. (Alice Catherine)

    2012-01-01T23:59:59.000Z

    Decisions made by product designers strongly influence the social and environmental impacts that a consumer product will have over its lifetime. This study examines the Sustainable Apparel Index, a decision-support tool ...

  10. Presentation 2.7: Energy and the Forest Products Industry in Malaysia Zulkifli Bin Ahmad

    E-Print Network [OSTI]

    balanced utilization of oil, gas, hydro & coal To prolong lifespan of Malaysia's oil reserves for future in the production of wood products are collected to be used as raw materials to produce fibre boards

  11. Pricing and licensing of software products and services : a study on industry trends

    E-Print Network [OSTI]

    Nayak, Shivashis

    2006-01-01T23:59:59.000Z

    The software product business reached the $150 billion mark at the end of 2005. The pricing and licensing of new products, maintenance services, services and service maintenance have become an important strategy to deliver ...

  12. Digital production pipelines: examining structures and methods in the computer effects industry 

    E-Print Network [OSTI]

    Bettis, Dane Edward

    2005-08-29T23:59:59.000Z

    Computer animated films require collaboration: blending artistic concept with technical skill, meeting budget constraints and adhering to deadlines. The path which production follows from initial idea to finished product is known as the pipeline...

  13. Communicating Knowledge: A Case Study for Improving Technician Productivity in the Telecom Industry

    E-Print Network [OSTI]

    Santos, Sonia M.

    2008-05-16T23:59:59.000Z

    Organizational success is based on productivity. Productivity at the Mountainside Moonpies Corporation is currently in decline due to the swift advancement of telecommunication technology, an aging workforce, and minimal ...

  14. Lost Opportunities in Industrial Energy Efficiency: New Production Lean Manufacturing and Lean Energy 

    E-Print Network [OSTI]

    Seryak, J.; Epstein, G.; D'Antonio, M.

    2006-01-01T23:59:59.000Z

    , plant wide energy use is mainly a function of three variables: weather conditions, production quantity and operating hours. For example, as outdoor temperatures increase in the summer time, plant electricity use may also increase due to air... of production factors. Next, imagine dedicated production presses that shut off during idle cycle times. This equipment uses energy directly proportional to production quantity, regardless of the operating hours. Lighting equipment for this same operation...

  15. Stumbling Toward Capitalism: The State, Global Production Networks, and the Unexpected Emergence of China's Independent Auto Industry

    E-Print Network [OSTI]

    Chang, Crystal Whai-ku

    2011-01-01T23:59:59.000Z

    2004-2008. China Automotive Industry Yearbooks 2004, 2005,Latin America: The Automotive Industry in Argentina, Chilein the Chinese Automotive Industry. Discussion Paper Series,

  16. How managing more efficiently substances in the design process of industrial products? An example from the aeronautics sector

    E-Print Network [OSTI]

    Lemagnen, Maud; Brissaud, Daniel

    2009-01-01T23:59:59.000Z

    Lowering environmental impacts of products, i.e. ecodesign, is considered today as a new and promising approach environment protection. This article focuses on ecodesign in the aeronautical sector through the analysis of the practices of a company that designs and produces engine equipments. Noise, gas emissions, fuel consumptions are the main environmental aspects which are targeted by aeronautics. From now on, chemical risk linked to the use of materials and production processes has to be traced, not only because of regulation pressure (e.g. REACh) but also because of customers requirements. So far, the aeronautical sector hasn't been focusing much on managing chemical risks at the design stage. However, new substances regulations notably require that chemical risk management should be by industries used as early as possible in their product development process. The aeronautics sector has therefore to elaborate new chemical risk management. The aim of this paper is to present a new method hat should be adap...

  17. Optical Constants ofOptical Constants of Uranium Nitride Thin FilmsUranium Nitride Thin Films

    E-Print Network [OSTI]

    Hart, Gus

    Optical Constants ofOptical Constants of Uranium Nitride Thin FilmsUranium Nitride Thin FilmsDelta--Beta Scatter Plot at 220 eVBeta Scatter Plot at 220 eV #12;Why Uranium Nitride?Why Uranium Nitride? UraniumUranium, uranium,Bombard target, uranium, with argon ionswith argon ions Uranium atoms leaveUranium atoms leave

  18. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2002-09-27T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy (DOE), National Energy Technology Laboratory (NETL), will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the eighth quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) issuing subcontracts, (2) SWC membership class expansion, (3) planning SWC technology transfer meetings, and (4) extending selected 2001 project periods of performance. In addition, a literature search that focuses on the use of lasers, microwaves, and acoustics for potential stripper well applications continued.

  19. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2003-04-08T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the ninth quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) organizing and hosting two fall technology transfer meetings, (2) SWC membership class expansion, and (3) planning the SWC 2003 Spring meeting. In addition, a literature search that focuses on the use of lasers, microwaves, and acoustics for potential stripper well applications continued.

  20. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2001-09-14T23:59:59.000Z

    The Pennsylvania State University, under contract to the US Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the US petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the four quarterly technical progress report for the SWC. During this reporting period, Penn State primary focus was on finalizing all subcontracts, planning the SWC technology transfer meeting and two workshops in the southern US, and preparing the next SWC newsletter. Membership in the SWC now stands at 49.

  1. Establishment of an Industry-Driven Consortium Focused on Improving the Production Performance of Domestic Stripper Wells

    SciTech Connect (OSTI)

    Joel L. Morrison; Sharon L. Elder

    2006-04-21T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy (DOE), National Energy Technology Laboratory (NETL) has established a national industry-driven Stripper Well Consortium (SWC) that is focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the seventh quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) Nomination and election of the Executive Council members for the 2006-07 term, (2) Finalize and release the 2006 Request for Proposals (RFP), (3) Invoice and recruit members, (4) Plan for the spring meeting, (5) Improving communication efforts, and (6) Continue distribution of the DVD entitled: ''Independent Oil: Rediscovering American's Forgotten Wells''.

  2. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2005-01-04T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the seventeenth quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) organizing and hosting the SWC fall technology transfer meetings in Oklahoma City, Oklahoma and State College, Pennsylvania, (2) planning of the upcoming SWC spring proposal meeting, (3) release of the SWC Request-for-proposals (RFP), (4) revision of the SWC By-Laws, and (5) the SWC Executive Council nomination and election for 2005-2006 term members.

  3. 2014 Uranium Marketing Annual Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1 U.S. Department of Energygasoline4Residential17. Purchases of6a. Uranium

  4. 2014 Uranium Marketing Annual Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1 U.S. Department of Energygasoline4Residential17. Purchases4. Uranium

  5. 2014 Uranium Marketing Annual Survey

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1 U.S. Department of Energygasoline4Residential17. Purchases4. Uranium57.

  6. Economic Evaluation of By-Product Power/Co-Generation Systems for Industrial Plants with Fluidized-Bed Coal Burning Facilities

    E-Print Network [OSTI]

    Mesko, J. E.

    1980-01-01T23:59:59.000Z

    Economic analysis of the construction and operation of by-product electric power and steam/power cogeneration systems in coal fired fluidized-bed steam cycles, located at individual industrial sites analyzed by the author, is being presented...

  7. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial andSeptember 25,9,1996 N Y MDomestic

  8. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and

  9. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and1. Total

  10. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and1. Total3. U.S.

  11. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and1. Total3. U.S.4.

  12. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97. Employment in

  13. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97. Employment

  14. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97. Employment4.

  15. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97. Employment4.2.

  16. 2014 Domestic Uranium Production Report

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi" ,"Plant","Primary1. TotalRevenueTotal97.

  17. BIOREMEDIATION OF URANIUM CONTAMINATED SOILS AND WASTES.

    SciTech Connect (OSTI)

    FRANCIS,A.J.

    1998-09-17T23:59:59.000Z

    Contamination of soils, water, and sediments by radionuclides and toxic metals from uranium mill tailings, nuclear fuel manufacturing and nuclear weapons production is a major concern. Studies of the mechanisms of biotransformation of uranium and toxic metals under various microbial process conditions has resulted in the development of two treatment processes: (i) stabilization of uranium and toxic metals with reduction in waste volume and (ii) removal and recovery of uranium and toxic metals from wastes and contaminated soils. Stabilization of uranium and toxic metals in wastes is accomplished by exploiting the unique metabolic capabilities of the anaerobic bacterium, Clostridium sp. The radionuclides and toxic metals are solubilized by the bacteria directly by enzymatic reductive dissolution, or indirectly due to the production of organic acid metabolites. The radionuclides and toxic metals released into solution are immobilized by enzymatic reductive precipitation, biosorption and redistribution with stable mineral phases in the waste. Non-hazardous bulk components of the waste such as Ca, Fe, K, Mg and Na released into solution are removed, thus reducing the waste volume. In the second process uranium and toxic metals are removed from wastes or contaminated soils by extracting with the complexing agent citric acid. The citric-acid extract is subjected to biodegradation to recover the toxic metals, followed by photochemical degradation of the uranium citrate complex which is recalcitrant to biodegradation. The toxic metals and uranium are recovered in separate fractions for recycling or for disposal. The use of combined chemical and microbiological treatment process is more efficient than present methods and should result in considerable savings in clean-up and disposal costs.

  18. Uranium hexafluoride public risk

    SciTech Connect (OSTI)

    Fisher, D.R.; Hui, T.E.; Yurconic, M.; Johnson, J.R.

    1994-08-01T23:59:59.000Z

    The limiting value for uranium toxicity in a human being should be based on the concentration of uranium (U) in the kidneys. The threshold for nephrotoxicity appears to lie very near 3 {mu}g U per gram kidney tissue. There does not appear to be strong scientific support for any other improved estimate, either higher or lower than this, of the threshold for uranium nephrotoxicity in a human being. The value 3 {mu}g U per gram kidney is the concentration that results from a single intake of about 30 mg soluble uranium by inhalation (assuming the metabolism of a standard person). The concentration of uranium continues to increase in the kidneys after long-term, continuous (or chronic) exposure. After chronic intakes of soluble uranium by workers at the rate of 10 mg U per week, the concentration of uranium in the kidneys approaches and may even exceed the nephrotoxic limit of 3 {mu}g U per gram kidney tissue. Precise values of the kidney concentration depend on the biokinetic model and model parameters assumed for such a calculation. Since it is possible for the concentration of uranium in the kidneys to exceed 3 {mu}g per gram tissue at an intake rate of 10 mg U per week over long periods of time, we believe that the kidneys are protected from injury when intakes of soluble uranium at the rate of 10 mg U per week do not continue for more than two consecutive weeks. For long-term, continuous occupational exposure to low-level, soluble uranium, we recommend a reduced weekly intake limit of 5 mg uranium to prevent nephrotoxicity in workers. Our analysis shows that the nephrotoxic limit of 3 {mu}g U per gram kidney tissues is not exceeded after long-term, continuous uranium intake at the intake rate of 5 mg soluble uranium per week.

  19. Industrial Productivity Assessment Or One of the Best Ways to Save Energy is to Find Ways to Produce More Product!

    E-Print Network [OSTI]

    Welch, D.

    The success of an energy program is often judged by measuring the change in energy consumption over time. It can be argued that a more valid method would measure the change in energy consumption per pound (or other unit) of product since this takes...

  20. Solar production of industrial process steam at the Home Cleaning and Laundry Co. Final technical report

    SciTech Connect (OSTI)

    Not Available

    1984-06-01T23:59:59.000Z

    This report presents the results of the operation and performance evaluation period at the Home Laundry Solar Industrial Process Heat Project at Pasadena, California. The installation comprises 6496 ft/sup 2/ (603.5 m/sup 2/) of linear parabolic trough concentrating collectors supplying solar thermal energy for use in laundry and dry cleaning processes. The design phase began in September 1977, and an acceptance test was conducted during the week of April 12, 1982. The plant has been in operation since May 1982, with the 12-month Phase III (operational) period starting in October 1982. The objective of the operational evaluation experiment was to maximize energy delivery to the industrial participant while characterizing system performance. Data were acquired for monthly documentation of system performance, maintenance requirements, and operating costs.

  1. Supply Chain Integration, Product Modularity, and Market Valuation: Evidence from the Solar Energy Industry

    E-Print Network [OSTI]

    Davies, Jane; Joglekar, Nitin

    2013-07-17T23:59:59.000Z

    data set of public firms in the solar energy industry for the 2007 financial year. Clean technologies have experienced an accelerated adoption cycle with the increasing attention on climate change, rising oil prices and a supportive global regulatory... : concentrated solar power through reflecting mirrors, and photovoltaic (PV) generation through either thin-film or crystalline cells (NREL 2011). For the purpose of this study, we focus on the more common PV generation as it has a well defined supply chain...

  2. The Production Tax Credit is Key to a Strong U.S. Wind Industry |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOriginEducationVideoStrategic|Industrial Sector, January 2000 |The PlanetCategory 2

  3. Uranium Mill Tailings Management

    SciTech Connect (OSTI)

    Nelson, J.D.

    1982-01-01T23:59:59.000Z

    This book presents the papers given at the Fifth Symposium on Uranium Mill Tailings Management. Advances made with regard to uranium mill tailings management, environmental effects, regulations, and reclamation are reviewed. Topics considered include tailings management and design (e.g., the Uranium Mill Tailings Remedial Action Project, environmental standards for uranium mill tailings disposal), surface stabilization (e.g., the long-term stability of tailings, long-term rock durability), radiological aspects (e.g. the radioactive composition of airborne particulates), contaminant migration (e.g., chemical transport beneath a uranium mill tailings pile, the interaction of acidic leachate with soils), radon control and covers (e.g., radon emanation characteristics, designing surface covers for inactive uranium mill tailings), and seepage and liners (e.g., hydrologic observations, liner requirements).

  4. Spectroscopic Evidence for Uranium Bearing Precipitates in Vadose Zone

    E-Print Network [OSTI]

    Northwest Laboratory, Richland, Washington 99352 Uranium (U) solid-state speciation in vadose zone sediments of past nuclear fuel fabrication processes, uranium (U) has been recognized as one of the most widespreadHanfordsitesthatreceivedU-containingwastesduring its mission of Pu production between 1940 and 1990. Unirradiated fuel rod wastes were disposed

  5. Synthesis of Uranium Trichloride for the Pyrometallurgical Processing of Used Nuclear Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; J.C. Price; R.D. Mariani

    2011-11-01T23:59:59.000Z

    The pyroprocessing of used nuclear fuel via electrorefining requires the continued addition of uranium trichloride to sustain operations. Uranium trichloride is utilized as an oxidant in the system to allow separation of uranium metal from the minor actinides and fission products. The inventory of uranium trichloride had diminished to a point that production was necessary to continue electrorefiner operations. Following initial experimentation, cupric chloride was chosen as a reactant with uranium metal to synthesize uranium trichloride. Despite the variability in equipment and charge characteristics, uranium trichloride was produced in sufficient quantities to maintain operations in the electrorefiner. The results and conclusions from several experiments are presented along with a set of optimized operating conditions for the synthesis of uranium trichloride.

  6. Preparation of uranium compounds

    DOE Patents [OSTI]

    Kiplinger, Jaqueline L; Montreal, Marisa J; Thomson, Robert K; Cantat, Thibault; Travia, Nicholas E

    2013-02-19T23:59:59.000Z

    UI.sub.3(1,4-dioxane).sub.1.5 and UI.sub.4(1,4-dioxane).sub.2, were synthesized in high yield by reacting turnings of elemental uranium with iodine dissolved in 1,4-dioxane under mild conditions. These molecular compounds of uranium are thermally stable and excellent precursor materials for synthesizing other molecular compounds of uranium including alkoxide, amide, organometallic, and halide compounds.

  7. Process for recovering uranium from waste hydrocarbon oils containing the same. [Uranium contaminated lubricating oils from gaseous diffusion compressors

    DOE Patents [OSTI]

    Conrad, M.C.; Getz, P.A.; Hickman, J.E.; Payne, L.D.

    1982-06-29T23:59:59.000Z

    The invention is a process for the recovery of uranium from uranium-bearing hydrocarbon oils containing carboxylic acid as a degradation product. In one aspect, the invention comprises providing an emulsion of water and the oil, heating the same to a temperature effecting conversion of the emulsion to an organic phase and to an acidic aqueous phase containing uranium carboxylate, and recovering the uranium from the aqueous phase. The process is effective, simple and comparatively inexpensive. It avoids the use of toxic reagents and the formation of undesirable intermediates.

  8. Change management, production ramp up and the sustainable supply chain in the transportation industry

    E-Print Network [OSTI]

    Fortin, Sean (Sean Dubé)

    2009-01-01T23:59:59.000Z

    The ramp up phase is always the most risky part of any project, especially with a product material the company and its partners have very little experience with. One result of this lack of experience is frequent engineering ...

  9. A cross-industry analysis and framework of aftermarket products and services

    E-Print Network [OSTI]

    Englezos, Petros

    2006-01-01T23:59:59.000Z

    This thesis looks at how supply chains of Aftermarket Products and Services are structured. The study includes an overall examination of the Aftermarket Function, as well as an overview and examination of Aftermarket Supply ...

  10. Product line-up design based on preference measurement : a case study on TV industry

    E-Print Network [OSTI]

    Park, Chang Bae, S.M. Massachusetts Institute of Technology

    2011-01-01T23:59:59.000Z

    Sony, in 2010, introduced innovative product line-up setting process for its TV, using the technique of market segmentation and conjoint analysis. This practice was expected to increase its sales compared to traditional ...

  11. agro-industrial products materiels: Topics by E-print Network

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

    R. Naik Director, UWM on "Management & Use of Coal Combustion Products (CCPs)" held at San Antonio, TX, January 22-28, 2001. Department Wisconsin-Milwaukee, University of 110...

  12. eBusiness in the Forest Products Industry Opportunities and Realities

    E-Print Network [OSTI]

    2004 0 1 2 3 4 5 6 7 8 $USTrillion Asia Pacific Latin America W estern Europe North America (Forrester & Professor Louisiana Forest Products Development Center School of Renewable Natural Resources Louisiana State

  13. Progress toward uranium scrap recycling via EBCHR

    SciTech Connect (OSTI)

    McKoon, R.H.

    1994-11-01T23:59:59.000Z

    A 250 kW electron beam cold hearth refining (EBCHR) melt furnace at Lawrence Livermore National Laboratory (LLNL) has been in operation for over a year producing 5.5 in.-diameter ingots of various uranium alloys. Production of in-specification uranium-6%-niobium (U-6Nb) alloy ingots has been demonstrated using virgin feedstock. A vibratory scrap feeder has been installed on the system and the ability to recycle chopped U-6Nb scrap has been established. A preliminary comparison of vacuum arc remelted (VAR) and electron beam (EB) melted product is presented.

  14. Uranium Mining, Conversion, and Enrichment Industries

    Energy Savers [EERE]

    as "offsetting." REDACTED REDACTED REDACTED REDACTED 82 Declaration of Kevin P. Smith, ConverDyn v. Moniz, Case no. 1:14-cv-01012-RBW, Document 17-7 at 11 (July 7,...

  15. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2001-09-12T23:59:59.000Z

    The Pennsylvania State University, under contract to the US Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. the consortium creates a partnership with the US petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the third quarterly technical progress report for the SWC. During this reporting period the SWC entered into a co-funding arrangement with the New York State Energy Development Authority (NYSERDA) to provide an additional $100,000 in co-funding for stripper well production-orientated projects.The SWC hosted its first meeting in which members proposed research projects to the SWC membership. The meeting was held on April 9-10, 2001 in State College, Pennsylvania. Twenty three proposals were submitted to the SWC for funding consideration. Investigators of the proposed projects provided the SWC membership with a 20 minute (15 minute technical discussion, 5 minute question and answer session) presentation. Of the 23 proposals, the Executive Council approved $921,000 in funding for 13 projects. Penn State then immediately started the process of issuing subcontracts to the various projects approved for funding.

  16. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2002-09-30T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy (DOE), National Energy Technology Laboratory (NETL), has established a national industry-driven Stripper Well Consortium (SWC) that is focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the second topical report. The SWC has grown and diversified its membership during its first 24 months of existence. The Consortium is now focused on building strategic alliances with additional industrial, state, and federal entities to expand further the SWC membership base and transfer technologies as they are developed. In addition, the Consortium has successfully worked to attract state support to co-fund SWC projects. Penn State has entered a co-funding arrangement with the New York State Energy Development Authority (NYSERDA) which has provided $200,000 over the last two years to co-fund stripper well production-orientated projects that have relevance to New York state producers. During this reporting period, the Executive Council approved co-funding for 14 projects that have a total project value of $2,116,897. Since its inception, the SWC has approved cofunding for 27 projects that have a total project value of $3,632,109.84. The SWC has provided $2,242,701 in co-funding for these projects and programmatically maintains a cost share of 39%.

  17. TrendSetter Solar Products Inc aka Trendsetter Industries formerly Six

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTown of Ladoga, Indiana (Utility Company)LibraryDatasetsElectricRiver Solar | Open

  18. Uraniumhydrogen interactions: synthesis and crystal structures of tris(N,N-dimethylaminodiboranato)uranium(III)w

    E-Print Network [OSTI]

    Girolami, Gregory S.

    Uranium­hydrogen interactions: synthesis and crystal structures of tris(N,N-dimethylaminodiboranato)uranium919490h The reaction of UCl4 with Na(H3BNMe2BH3) in diethyl ether affords the uranium(III) product U(H3 in the two forms. Uranium hydride, UH3, has been proposed to be an ideal material for the generation of safe

  19. Sustainability of the cement and concrete industries UWM Center for By-Products Utilization, University of Wisconsin-Milwaukee, Milwaukee, WI, USA

    E-Print Network [OSTI]

    Wisconsin-Milwaukee, University of

    Sustainability of the cement and concrete industries T.R. Naik UWM Center for By of the most widely used construction materials in the world. However, the production of portland cement); production of one ton of portland cement produces about one ton of CO2 and other GHGs. The environmental

  20. Document: P1332 Category: Physical Sciences, Chemical/Materials License Status: Available for licensing Texas Industry Cluster: Petroleum Refining & Chemical Products

    E-Print Network [OSTI]

    Lightsey, Glenn

    for licensing Texas Industry Cluster: Petroleum Refining & Chemical Products Lower-cost fuel cells Problem, and they offer an alternative to petroleum-burning internal combustion engines. The U.S. Environ- mental and as a replacement for off-grid small power and grid production power plants. Development Stage/IP Status Lab

  1. Industrial market assessment of the products of mild gasification: Final report

    SciTech Connect (OSTI)

    Sinor, J.E.

    1988-01-01T23:59:59.000Z

    The goal of this study is to determine the best available conditions, in terms of market volumes and prices, for the products from a mild gasification facility. A process feasibility study will then have to determine the cost of building and operating a facility to make those products. The study is presented as a summary of the options available to a coal producer for creating added product value. For this reason, three specific coal mines owned by AMAX Inc. were chosen, and the options were analyzed from the viewpoint of increasing the total revenue derived from those coals. No specific mild gasification, or mild devolatilization technology was assumed during the assessment. The analysis considers only product prices, volumes, and specifications. It does not assign any intangible value or national benefit to substituting coal for oil or to producing a cleaner fuel. Although it would be desirable to conceive of a product slate which would be immune from energy price fluctuations, such a goal is probably unattainable and no particular emphasis was placed on it. 76 figs., 75 tabs.

  2. Demonstration of jackhammer incorporating depleted uranium

    SciTech Connect (OSTI)

    Fischer, L E; Hoard, R W; Carter, D L; Saculla, M D; Wilson, G V

    2000-04-01T23:59:59.000Z

    The United States Government currently has an abundance of depleted uranium (DU). This surplus of about 1 billion pounds is the result of an enrichment process using gaseous diffusion to produce enriched and depleted uranium. The enriched uranium has been used primarily for either nuclear weapons for the military or nuclear fuel for the commercial power industry. Most of the depleted uranium remains at the enrichment process plants in the form of depleted uranium hexafluoride (DUF{sub 6}). The Department of Energy (DOE) recently began a study to identify possible commercial applications for the surplus material. One of these potential applications is to use the DU in high-density strikers/hammers in pneumatically driven tools, such as jack hammers and piledrivers to improve their impulse performance. The use of DU could potentially increase tunneling velocity and excavation into target materials with improved efficiency. This report describes the efforts undertaken to analyze the particulars of using DU in two specific striking applications: the jackhammer and chipper tool.

  3. Thermal stress analysis of fused-cast AZS refractories during production; Part 1: Industrial study

    SciTech Connect (OSTI)

    Cockcroft, S.L.; Brimacombe, J.K. (Univ. of British Columbia, Vancouver, British Columbia (Canada). Centre for Metallurgical Process Engineering); Walrod, D.G.; Myles, T.A. (Carborundum Co., Falconer, NY (United States). Monofrax-S Plant)

    1994-06-01T23:59:59.000Z

    A study has been conducted to understand and prevent the formation of cracks in alumina-zirconia-silica (AZS) refractory blocks during solidification processing. A fundamental approach has been taken, centered on the development of a three-dimensional mathematical model to predict heat flow and stress generation in fused-cast AZS refractory blocks. In the first part of a two-part study, the voidless'' casting process has been carefully examined in an industrial setting. From a survey of the distribution, frequency of occurrence, and fracture surface morphology of cracks, an attempt was made to link the crack types found in the study to process variables. In-mold temperature data collected for a single casting throughout the normal cooling period have been used to validate the heat-flow model which is described in Part 2. The stress analysis, cause of the different cracks, and remedial action are also presented in Part 2.

  4. Du, X., Kockelman, K. M. 1 1 TRACKING TRANSPORTATION AND INDUSTRIAL PRODUCTION ACROSS A

    E-Print Network [OSTI]

    Kockelman, Kara M.

    commodities highlight the importance of food 35 and petroleum manufacturing sectors, in terms of production expansions) and exogenous economic shocks (e.g., increases in14 export demands).15 Other spatial IO commodity flows and transportation network flows to17 evaluate the indirect impacts of an unexpected event

  5. Department of Industrial Engineering Fall 2012 Laser Non-Contact Measurement of Moving Product

    E-Print Network [OSTI]

    Demirel, Melik C.

    With a non-contact measurement system improvements can be made in the inspection area ultimately eliminating Product Overview ArcelorMittal produces steel rails for railroads, cranes, transit agencies companies The team visited the factory again to conduct more measurements for the prototype and CAD models

  6. Chapter 1. Introduction Uranium is a common element in nature that has for centuries been used as a coloring agent in

    E-Print Network [OSTI]

    contained in the uranium nucleus.1 Another legacy of uranium exploration, mining, and ore processing were1-1 Chapter 1. Introduction Uranium is a common element in nature that has for centuries been used as a coloring agent in decorative glass and ceramics. Uranium and its radioactive decay products are ubiquitous

  7. CHARACTERIZATION OF URANIUM, URANIUM OXIDE AND SILICON MULTILAYER THIN FILMS

    E-Print Network [OSTI]

    Hart, Gus

    CHARACTERIZATION OF URANIUM, URANIUM OXIDE AND SILICON MULTILAYER THIN FILMS by David T. Oliphant. Woolley Dean, College of Physical and Mathematical Sciences #12;ABSTRACT CHARACTERIZATION OF URANIUM, URANIUM OXIDE AND SILICON MULTILAYER THIN FILMS David T. Oliphant Department of Physics and Astronomy

  8. Uranium dioxide electrolysis

    DOE Patents [OSTI]

    Willit, James L. (Batavia, IL); Ackerman, John P. (Prescott, AZ); Williamson, Mark A. (Naperville, IL)

    2009-12-29T23:59:59.000Z

    This is a single stage process for treating spent nuclear fuel from light water reactors. The spent nuclear fuel, uranium oxide, UO.sub.2, is added to a solution of UCl.sub.4 dissolved in molten LiCl. A carbon anode and a metallic cathode is positioned in the molten salt bath. A power source is connected to the electrodes and a voltage greater than or equal to 1.3 volts is applied to the bath. At the anode, the carbon is oxidized to form carbon dioxide and uranium chloride. At the cathode, uranium is electroplated. The uranium chloride at the cathode reacts with more uranium oxide to continue the reaction. The process may also be used with other transuranic oxides and rare earth metal oxides.

  9. Electrochemical method of producing eutectic uranium alloy and apparatus

    DOE Patents [OSTI]

    Horton, J.A.; Hayden, H.W.

    1995-01-10T23:59:59.000Z

    An apparatus and method are disclosed for continuous production of liquid uranium alloys through the electrolytic reduction of uranium chlorides. The apparatus includes an electrochemical cell formed from an anode shaped to form an electrolyte reservoir, a cathode comprising a metal, such as iron, capable of forming a eutectic uranium alloy having a melting point less than the melting point of pure uranium, and molten electrolyte in the reservoir comprising a chlorine or fluorine containing salt and uranium chloride. The method of the invention produces an eutectic uranium alloy by creating an electrolyte reservoir defined by a container comprising an anode, placing an electrolyte in the reservoir, the electrolyte comprising a chlorine or fluorine containing salt and uranium chloride in molten form, positioning a cathode in the reservoir where the cathode comprises a metal capable of forming an uranium alloy having a melting point less than the melting point of pure uranium, and applying a current between the cathode and the anode. 2 figures.

  10. Re-utilization of Industrial CO2 for Algae Production Using a Phase Change Material

    SciTech Connect (OSTI)

    Joseph, Brian

    2013-12-31T23:59:59.000Z

    This is the final report of a 36-month Phase II cooperative agreement. Under this project, Touchstone Research Laboratory (Touchstone) investigated the merits of incorporating a Phase Change Material (PCM) into an open-pond algae production system that can capture and re-use the CO2 from a coal-fired flue gas source located in Wooster, OH. The primary objective of the project was to design, construct, and operate a series of open algae ponds that accept a slipstream of flue gas from a coal-fired source and convert a significant portion of the CO2 to liquid biofuels, electricity, and specialty products, while demonstrating the merits of the PCM technology. Construction of the pilot facility and shakedown of the facility in Wooster, OH, was completed during the first two years, and the focus of the last year was on operations and the cultivation of algae. During this Phase II effort a large-scale algae concentration unit from OpenAlgae was installed and utilized to continuously harvest algae from indoor raceways. An Algae Lysing Unit and Oil Recovery Unit were also received and installed. Initial parameters for lysing nanochloropsis were tested. Conditions were established that showed the lysing operation was effective at killing the algae cells. Continuous harvesting activities yielded over 200 kg algae dry weight for Ponds 1, 2 and 4. Studies were conducted to determine the effect of anaerobic digestion effluent as a nutrient source and the resulting lipid productivity of the algae. Lipid content and total fatty acids were unaffected by culture system and nutrient source, indicating that open raceway ponds fed diluted anaerobic digestion effluent can obtain similar lipid productivities to open raceway ponds using commercial nutrients. Data were also collected with respect to the performance of the PCM material on the pilot-scale raceway ponds. Parameters such as evaporative water loss, temperature differences, and growth/productivity were tracked. The pond with the PCM material was consistently 2 to 5°C warmer than the control pond. This difference did not seem to increase significantly over time. During phase transitions for the PCM, the magnitude of the difference between the daily minimum and maximum temperatures decreased, resulting in smaller daily temperature fluctuations. A thin layer of PCM material reduced overall water loss by 74% and consistently provided algae densities that were 80% greater than the control pond.

  11. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2004-05-17T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the thirteenth quarterly technical progress report for the SWC. Key activities for this reporting period included: (1) hosting three fall technology transfer meetings in Wyoming, Texas, and Pennsylvania, (2) releasing the 2004 SWC request-for-proposal (RFP), and (3) initial planning of the SWC spring meeting in Golden Colorado for selecting the 2004 SWC projects. The Fall technology transfer meetings attracted 100+ attendees between the three workshops. The SWC membership which attended the Casper, Wyoming workshop was able to see several SWC-funded projects operating in the field at the Rocky Mountain Oilfield Testing Center. The SWC is nearing the end of its initial funding cycle. The Consortium has a solid membership foundation and a demonstrated ability to review and select projects that have relevancy to meet the needs of domestic stripper well operators.

  12. ESTABLISHMENT OF AN INDUSTRY-DRIVEN CONSORTIUM FOCUSED ON IMPROVING THE PRODUCTION PERFORMANCE OF DOMESTIC STRIPPER WELLS

    SciTech Connect (OSTI)

    Joel L. Morrison

    2004-05-10T23:59:59.000Z

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the eleventh quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) organizing and hosting the Spring SWC meeting in Pearl River, New York, (2) working with successful applicants and Penn State's Office of Sponsored Research to get subcontracts in place, and (3) planning three SWC technology transfer meetings to take place in the fall of 2003. During this reporting period, the efforts were focused primarily on the organizing and hosting the SWC Spring proposal meeting and organizing the fall technology transfer meetings.

  13. LonMark Open Solutions: An Industry Update-New Products, Solutions, Educational Programs, Standards, and how They Affect the Future of Building

    E-Print Network [OSTI]

    Bernstein, R.

    2011-01-01T23:59:59.000Z

    ? Standardization of enterprise data model LONMARK Update, Programs, And Resources Who is LONMARK International? ? Independent, non-profit member supported organization ? Product Manufacturers ? System Integrators ? Engineers ? End Users Vision ? LONMARK...1 LONMARK Open Solutions Programs and Industry Update Ron Bernstein LonMark International a non-profit industry trade and standards development association supporting the open buildings control market Agenda ? Trend Towards Open Systems...

  14. EPA Update: NESHAP Uranium Activities

    E-Print Network [OSTI]

    EPA Update: NESHAP Uranium Activities Reid J. Rosnick Environmental Protection Agency Radiation Protection Division (6608J) Washington, DC 20460 NMA/NRC Uranium Recovery Workshop July 2, 2009 #12 for underground uranium mining operations (Subpart B) EPA regulatory requirements for operating uranium mill

  15. NPDES Individual Permit for Industrial Facilities - Mail Merge...

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

    WATER DISCHARGES ASSOCIATED WITH INDUSTRIAL ACTIVITY FROM FABRICATED METAL PRODUCTS INDUSTRY......44 I. CONTENTS OF PLAN. ......

  16. Decarburization of uranium via electron beam processing

    SciTech Connect (OSTI)

    McKoon, R H

    1998-10-23T23:59:59.000Z

    For many commercial and military applications, the successive Vacuum Induction Melting of uranium metal in graphite crucibles results in a product which is out of specification in carbon. The current recovery method involves dissolution of the metal in acid and chemical purification. This is both expensive and generates mixed waste. A study was undertaken at Lawrence Livermore National Laboratory to investigate the feasibility of reducing the carbon content of uranium metal using electron beam techniques. Results will be presented on the rate and extent of carbon removal as a function of various operating parameters.

  17. Innovative Elution Processes for Recovering Uranium from Seawater

    SciTech Connect (OSTI)

    Wai, Chien; Tian, Guoxin; Janke, Christopher

    2014-05-29T23:59:59.000Z

    Utilizing amidoxime-based polymer sorbents for extraction of uranium from seawater has attracted considerable interest in recent years. Uranium collected in the sorbent is recovered typically by elution with an acid. One drawback of acid elution is deterioration of the sorbent which is a significant factor that limits the economic competitiveness of the amidoxime-based sorbent systems for sequestering uranium from seawater. Developing innovative elution processes to improve efficiency and to minimize loss of sorbent capacity become essential in order to make this technology economically feasible for large-scale industrial applications. This project has evaluated several elution processes including acid elution, carbonate elution, and supercritical fluid elution for recovering uranium from amidoxime-based polymer sorbents. The elution efficiency, durability and sorbent regeneration for repeated uranium adsorption- desorption cycles in simulated seawater have been studied. Spectroscopic techniques are used to evaluate chemical nature of the sorbent before and after elution. A sodium carbonate-hydrogen peroxide elution process for effective removal of uranium from amidoxime-based sorbent is developed. The cause of this sodium carbonate and hydrogen peroxide synergistic leaching of uranium from amidoxime-based sorbent is attributed to the formation of an extremely stable uranyl peroxo-carbonato complex. The efficiency of uranium elution by the carbonate-hydrogen peroxide method is comparable to that of the hydrochloric acid elution but damage to the sorbent material is much less for the former. The carbonate- hydrogen peroxide elution also does not need any elaborate step to regenerate the sorbent as those required for hydrochloric acid leaching. Several CO2-soluble ligands have been tested for extraction of uranium from the sorbent in supercritical fluid carbon dioxide. A mixture of hexafluoroacetylacetone and tri-n-butylphosphate shows the best result but uranium removal from the sorbent reaches only 80% after 10 hours of leaching. Some information regarding coordination of vanadium with amidoxime molecules and elution of vanadium from amidoxime- based sorbents is also given in the report.

  18. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

    Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

    2000-06-01T23:59:59.000Z

    The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

  19. Workbook for prioritizing petroleum industry exploration and production sites for remediation

    SciTech Connect (OSTI)

    White, G.J.

    1998-08-03T23:59:59.000Z

    The purpose of this Workbook is to provide a screening-level method for prioritizing petroleum exploration and production sites for remediation that is based on readily available information, but which does not require a full characterization of the sites being evaluated. The process draws heavily from the Canadian National Classification System for Contaminated Sites, and fits into the framework for ecological risk assessment provided in guidance from the US Environmental Protection Agency. Using this approach, scoring guidelines are provided for a number of Evaluation Factors relating to: (1) the contaminants present at the site; (2) the potential exposure pathways for these contaminants; and (3) the potential receptors of those contaminants. The process therefore incorporates a risk-based corrective action (RBCA) framework to estimate the relative threat posed by a site to human health and to ecological systems. Physical (non-toxic) disturbance factors have also been incorporated into the process. It should also be noted that the process described in this Workbook has not yet been field tested at petroleum E and P sites. The first logical step in the field testing of this process is to apply the method at a small number of sites to assess the availability of the information that is needed to score each evaluation factor. Following this evaluation, the Workbook process should be applied at a series of sites to determine the effectiveness of the process at ranking sites according to their relative need for remediation. Upon completion of these tests, the Workbook should be revised to reflect the findings of the field tests.

  20. Separation of uranium from technetium in recovery of spent nuclear fuel

    DOE Patents [OSTI]

    Pruett, D.J.; McTaggart, D.R.

    1983-08-31T23:59:59.000Z

    Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

  1. Stumbling Toward Capitalism: The State, Global Production Networks, and the Unexpected Emergence of China's Independent Auto Industry

    E-Print Network [OSTI]

    Chang, Crystal Whai-ku

    2011-01-01T23:59:59.000Z

    China‘s overall energy needs, Chinese ?green industries? – especially those firms engaged in wind turbine and solar

  2. Projections of the impact of expansion of domestic heavy oil production on the U.S. refining industry from 1990 to 2010. Topical report

    SciTech Connect (OSTI)

    Olsen, D.K.; Ramzel, E.B.; Strycker, A.R. [National Institute for Petroleum and Energy Research, Bartlesville, OK (United States). ITT Research Institute] [National Institute for Petroleum and Energy Research, Bartlesville, OK (United States). ITT Research Institute; Guariguata, G.; Salmen, F.G. [Bonner and Moore Management Science, Houston, TX (United States)] [Bonner and Moore Management Science, Houston, TX (United States)

    1994-12-01T23:59:59.000Z

    This report is one of a series of publications assessing the feasibility of increasing domestic heavy oil (10{degrees} to 20{degrees} API gravity) production. This report provides a compendium of the United States refining industry and analyzes the industry by Petroleum Administration for Defense District (PADD) and by ten smaller refining areas. The refining capacity, oil source and oil quality are analyzed, and projections are made for the U.S. refining industry for the years 1990 to 2010. The study used publicly available data as background. A linear program model of the U.S. refining industry was constructed and validated using 1990 U.S. refinery performance. Projections of domestic oil production (decline) and import of crude oil (increases) were balanced to meet anticipated demand to establish a base case for years 1990 through 2010. The impact of additional domestic heavy oil production, (300 MB/D to 900 MB/D, originating in select areas of the U.S.) on the U.S. refining complex was evaluated. This heavy oil could reduce the import rate and the balance of payments by displacing some imported, principally Mid-east, medium crude. The construction cost for refining units to accommodate this additional domestic heavy oil production in both the low and high volume scenarios is about 7 billion dollars for bottoms conversion capacity (delayed coking) with about 50% of the cost attributed to compliance with the Clean Air Act Amendment of 1990.

  3. High-efficiency Forage Systems for Texas Beef Production The cattle industry in Texas is facing a crisis due to doubling of fertilizer, grain, and

    E-Print Network [OSTI]

    High-efficiency Forage Systems for Texas Beef Production The cattle industry in Texas is facing for adaptation, water· use efficiency, pest resistance, and forage nutritive value. New, efficient beef) and high plant nutrient efficiency grasses. Develop improved management systems to incorporate the new

  4. The non-aqueous chemistry of uranium has been an active area of exploration in recent decades1,2

    E-Print Network [OSTI]

    Cai, Long

    -purity depleted uranium produced as a by-product of nuclear isotope enrichment programmes. The early actinideThe non-aqueous chemistry of uranium has been an active area of exploration in recent decades1 for uranium will be created in part by the quest of researchers to understand the properties and potential

  5. Geological and geochemical aspects of uranium deposits: a selected, annotated bibliography. [474 references

    SciTech Connect (OSTI)

    Thomas, J.M.; Garland, P.A.; White, M.B.; Daniel, E.W.

    1980-09-01T23:59:59.000Z

    This bibliography, a compilation of 474 references, is the fourth in a series compiled from the National Uranium Resource Evaluation (NURE) Bibliographic Data Base. This data base was created for the Grand Junction Office of the Department of Energy's National Uranium Resource Evaluation Project by the Ecological Sciences Information Center, Oak Ridge National Laboratory. The references in the bibliography are arranged by subject category: (1) geochemistry, (2) exploration, (3) mineralogy, (4) genesis of deposits, (5) geology of deposits, (6) uranium industry, (7) geology of potential uranium-bearing areas, and (8) reserves and resources. The references are indexed by author, geographic location, quadrangle name, geoformational feature, and keyword.

  6. Biogeochemical Processes In Ethanol Stimulated Uranium Contaminated...

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

    Processes In Ethanol Stimulated Uranium Contaminated Subsurface Sediments. Biogeochemical Processes In Ethanol Stimulated Uranium Contaminated Subsurface Sediments. Abstract: A...

  7. Electrotechnologies in Process Industries

    E-Print Network [OSTI]

    Amarnath, K. R.

    The Industrial Program at the Electric Power Research Institute (EPRI) promotes the efficient use of electricity to improve the competitive position of the American industry. Electrotechnologies that improve productivity, improve quality...

  8. Stormwater Best Management Practices (BMPs) for Selected Industrial Sectors in the Lower Fraser Basin

    E-Print Network [OSTI]

    Concrete Industry Lime Industry Refined Petroleum Products (Bulk Storage) Other Petroleum and Coal Products and Planing Mill Products Industry Wire and Wire Products Industries Hydraulic Cernent Industry Ready Mixed

  9. Process for electrolytically preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A. (Knoxville, TN)

    1989-01-01T23:59:59.000Z

    A process for making uranium metal from uranium oxide by first fluorinating uranium oxide to form uranium tetrafluoride and next electrolytically reducing the uranium tetrafluoride with a carbon anode to form uranium metal and CF.sub.4. The CF.sub.4 is reused in the fluorination reaction rather than being disposed of as a hazardous waste.

  10. Controlling uranium reactivity March 18, 2008

    E-Print Network [OSTI]

    Meyer, Karsten

    for the last decade. Most of their work involves depleted uranium, a more common form of uraniumMarch 2008 Controlling uranium reactivity March 18, 2008 Uranium is an often misunderstood metal uranium research. In reality, uranium presents a wealth of possibilities for funda- mental chemistry. Many

  11. Influence of uranium hydride oxidation on uranium metal behaviour

    SciTech Connect (OSTI)

    Patel, N.; Hambley, D. [National Nuclear Laboratory (United Kingdom); Clarke, S.A. [Sellafield Ltd (United Kingdom); Simpson, K.

    2013-07-01T23:59:59.000Z

    This work addresses concerns that the rapid, exothermic oxidation of active uranium hydride in air could stimulate an exothermic reaction (burning) involving any adjacent uranium metal, so as to increase the potential hazard arising from a hydride reaction. The effect of the thermal reaction of active uranium hydride, especially in contact with uranium metal, does not increase in proportion with hydride mass, particularly when considering large quantities of hydride. Whether uranium metal continues to burn in the long term is a function of the uranium metal and its surroundings. The source of the initial heat input to the uranium, if sufficient to cause ignition, is not important. Sustained burning of uranium requires the rate of heat generation to be sufficient to offset the total rate of heat loss so as to maintain an elevated temperature. For dense uranium, this is very difficult to achieve in naturally occurring circumstances. Areas of the uranium surface can lose heat but not generate heat. Heat can be lost by conduction, through contact with other materials, and by convection and radiation, e.g. from areas where the uranium surface is covered with a layer of oxidised material, such as burned-out hydride or from fuel cladding. These rates of heat loss are highly significant in relation to the rate of heat generation by sustained oxidation of uranium in air. Finite volume modelling has been used to examine the behaviour of a magnesium-clad uranium metal fuel element within a bottle surrounded by other un-bottled fuel elements. In the event that the bottle is breached, suddenly, in air, it can be concluded that the bulk uranium metal oxidation reaction will not reach a self-sustaining level and the mass of uranium oxidised will likely to be small in relation to mass of uranium hydride oxidised. (authors)

  12. Selective Extraction of Uranium from Liquid or Supercritical Carbon Dioxide

    SciTech Connect (OSTI)

    Farawila, Anne F.; O'Hara, Matthew J.; Wai, Chien M.; Taylor, Harry Z.; Liao, Yu-Jung

    2012-07-31T23:59:59.000Z

    Current liquid-liquid extraction processes used in recycling irradiated nuclear fuel rely on (1) strong nitric acid to dissolve uranium oxide fuel, and (2) the use of aliphatic hydrocarbons as a diluent in formulating the solvent used to extract uranium. The nitric acid dissolution process is not selective. It dissolves virtually the entire fuel meat which complicates the uranium extraction process. In addition, a solvent washing process is used to remove TBP degradation products, which adds complexity to the recycling plant and increases the overall plant footprint and cost. A liquid or supercritical carbon dioxide (l/sc -CO2) system was designed to mitigate these problems. Indeed, TBP nitric acid complexes are highly soluble in l/sc -CO2 and are capable of extracting uranium directly from UO2, UO3 and U3O8 powders. This eliminates the need for total acid dissolution of the irradiated fuel. Furthermore, since CO2 is easily recycled by evaporation at room temperature and pressure, it eliminates the complex solvent washing process. In this report, we demonstrate: (1) A reprocessing scheme starting with the selective extraction of uranium from solid uranium oxides into a TBP-HNO3 loaded Sc-CO2 phase, (2) Back extraction of uranium into an aqueous phase, and (3) Conversion of recovered purified uranium into uranium oxide. The purified uranium product from step 3 can be disposed of as low level waste, or mixed with enriched uranium for use in a reactor for another fuel cycle. After an introduction on the concept and properties of supercritical fluids, we first report the characterization of the different oxides used for this project. Our extraction system and our online monitoring capability using UV-Vis absorbance spectroscopy directly in sc-CO2 is then presented. Next, the uranium extraction efficiencies and kinetics is demonstrated for different oxides and under different physical and chemical conditions: l/sc -CO2 pressure and temperature, TBP/HNO3 complex used, reductant or complexant used for selectivity, and ionic liquids used as supportive media. To complete the extraction and recovery cycle, we then demonstrate uranium back extraction from the TBP loaded sc-CO2 phase into an aqueous phase and the characterization of the uranium complex formed at the end of this process. Another aspect of this project was to limit proliferation risks by either co-extracting uranium and plutonium, or by leaving plutonium behind by selectively extracting uranium. We report that the former is easily achieved, since plutonium is in the tetravalent or hexavalent oxidation state in the oxidizing environment created by the TBP-nitric acid complex, and is therefore co-extracted. The latter is more challenging, as a reductant or complexant to plutonium has to be used to selectively extract uranium. After undertaking experiments on different reducing or complexing systems (e.g., AcetoHydroxamic Acid (AHA), Fe(II), ascorbic acid), oxalic acid was chosen as it can complex tetravalent actinides (Pu, Np, Th) in the aqueous phase while allowing the extraction of hexavalent uranium in the sc-CO2 phase. Finally, we show results using an alternative media to commonly used aqueous phases: ionic liquids. We show the dissolution of uranium in ionic liquids and its extraction using sc-CO2 with and without the presence of AHA. The possible separation of trivalent actinides from uranium is also demonstrated in ionic liquids using neodymium as a surrogate and diglycolamides as the extractant.

  13. Partial Oxidation Gas Turbine for Power and Hydrogen Co-Production from Coal-Derived Fuel in Industrial Applications

    SciTech Connect (OSTI)

    Joseph Rabovitser

    2009-06-30T23:59:59.000Z

    The report presents a feasibility study of a new type of gas turbine. A partial oxidation gas turbine (POGT) shows potential for really high efficiency power generation and ultra low emissions. There are two main features that distinguish a POGT from a conventional gas turbine. These are associated with the design arrangement and the thermodynamic processes used in operation. A primary design difference of the POGT is utilization of a non?catalytic partial oxidation reactor (POR) in place of a conventional combustor. Another important distinction is that a much smaller compressor is required, one that typically supplies less than half of the air flow required in a conventional gas turbine. From an operational and thermodynamic point of view a key distinguishing feature is that the working fluid, fuel gas provided by the OR, has a much higher specific heat than lean combustion products and more energy per unit mass of fluid can be extracted by the POGT expander than in the conventional systems. The POGT exhaust stream contains unreacted fuel that can be combusted in different bottoming ycle or used as syngas for hydrogen or other chemicals production. POGT studies include feasibility design for conversion a conventional turbine to POGT duty, and system analyses of POGT based units for production of power solely, and combined production of power and yngas/hydrogen for different applications. Retrofit design study was completed for three engines, SGT 800, SGT 400, and SGT 100, and includes: replacing the combustor with the POR, compressor downsizing for about 50% design flow rate, generator replacement with 60 90% ower output increase, and overall unit integration, and extensive testing. POGT performances for four turbines with power output up to 350 MW in POGT mode were calculated. With a POGT as the topping cycle for power generation systems, the power output from the POGT ould be increased up to 90% compared to conventional engine keeping hot section temperatures, pressures, and volumetric flows practically identical. In POGT mode, the turbine specific power (turbine net power per lb mass flow from expander exhaust) is twice the value of the onventional turbine. POGT based IGCC plant conceptual design was developed and major components have been identified. Fuel flexible fluid bed gasifier, and novel POGT unit are the key components of the 100 MW IGCC plant for co producing electricity, hydrogen and/or yngas. Plant performances were calculated for bituminous coal and oxygen blown versions. Various POGT based, natural gas fueled systems for production of electricity only, coproduction of electricity and hydrogen, and co production of electricity and syngas for gas to liquid and hemical processes were developed and evaluated. Performance calculations for several versions of these systems were conducted. 64.6 % LHV efficiency for fuel to electricity in combined cycle was achieved. Such a high efficiency arise from using of syngas from POGT exhaust s a fuel that can provide required temperature level for superheated steam generation in HRSG, as well as combustion air preheating. Studies of POGT materials and combustion instabilities in POR were conducted and results reported. Preliminary market assessment was performed, and recommendations for POGT systems applications in oil industry were defined. POGT technology is ready to proceed to the engineering prototype stage, which is recommended.

  14. Uranium in granites from the southwestern United States: actinide parent-daughter systems, sites and mobilization. Second year report. National Uranium Resource Evaluation

    SciTech Connect (OSTI)

    Silver, L.T.; Woodhead, J.A.; Williams, I.S.; Chappell, B.W.

    1984-09-01T23:59:59.000Z

    Results of detailed field and laboratory studies are reported on the primary distribution of uranium (and thorium and lead) in the radioactive minerals of five radioactive granite bodies in Arizona and California. This distribution was examined in a granite pluton. Granites with uranium concentrations ranging from 4 to 47 ppM, thorium concentrations from 11 to 181 ppM, and Th/U ratios of 0.6 to 16.0 were compared. Evidence for secondary mobilization, migration, fixation and/or loss of uranium, thorium and radiogenic leads was explored. Uranium distribution in radioactive granites is hosted in a far greater diversity of sites than has previously been known. Uranium and thorium distribution in primary minerals of granites is almost entirely a disequilibrium product involving local fractionation processes during magmatic crystallization. Every radioactive granite studied contains minerals that contain uranium and/or thorium as major stoichiometric components. When the granites are subject to secondary geochemical events and processes, the behavior of uranium is determined by the stability fields of the different radioactive minerals in the rocks. The two most powerful tools for evaluating uranium migration in a granite are (a) isotope dilution mass spectrometry and (b) the electron microprobe. Uranium mobilization and loss is a common feature in radioactive granites of the southwestern United States. A model for the evaluation of uranium loss from granites has been developed. The mineral zircon can be used as an independent indicator of uranium and thorium endowment. The weathering products show surprising differences in the response of different granites in arid region settings. Significant losses of primary uranium (up to 70%) has been a common occurrence. Uranium, thorium and radiogenic lead exist in labile (movable) form on surfaces of cleavages, fractures and grain boundaries in granites.

  15. Final Technical Report - High-Performance, Oxide-Dispersion-Strengthened Tubes for Production of Ethylene adn Other Industrial Chemicals

    SciTech Connect (OSTI)

    McKimpson, Marvin G.

    2006-04-06T23:59:59.000Z

    This project was undertaken by Michigan Technological University and Special Metals Corporation to develop creep-resistant, coking-resistant oxide-dispersion-strengthened (ODS) tubes for use in industrial-scale ethylene pyrolysis and steam methane reforming operations. Ethylene pyrolysis tubes are exposed to some of the most severe service conditions for metallic materials found anywhere in the chemical process industries, including elevated temperatures, oxidizing atmospheres and high carbon potentials. During service, hard deposits of carbon (coke) build up on the inner wall of the tube, reducing heat transfer and restricting the flow of the hydrocarbon feedstocks. About every 20 to 60 days, the reactor must be taken off-line and decoked by burning out the accumulated carbon. This decoking costs on the order of $9 million per year per ethylene plant, accelerates tube degradation, and requires that tubes be replaced about every 5 years. The technology developed under this program seeks to reduce the energy and economic cost of coking by creating novel bimetallic tubes offering a combination of improved coking resistance, creep resistance and fabricability not available in current single-alloy tubes. The inner core of this tube consists of Incoloy(R) MA956, a commercial ferritic Fe-Cr-Al alloy offering a 50% reduction in coke buildup combined with improved carburization resistance. The outer sheath consists of a new material - oxide dispersion strengthened (ODS) Alloy 803(R) developed under the program. This new alloy retains the good fireside environmental resistance of Alloy 803, a commercial wrought alloy currently used for ethylene production, and provides an austenitic casing to alleviate the inherently-limited fabricability of the ferritic Incoloy(R) MA956 core. To provide mechanical compatibility between the two alloys and maximize creep resistance of the bimetallic tube, both the inner Incoloy(R) MA956 and the outer ODS Alloy 803 are oxide dispersion strengthened materials produced using mechanical alloying technology. To minimize cost, the bimetallic tube is produced by direct powder co-extrusion. This technology has potential for domestic energy savings of up to 4.1 trillion BTU/year (4.3 x 1015J/year) and a reduction of 370,000 tons (340,000 tonnes) of CO2 emissions in short-residence-time ethylene furnaces. This represents an energy savings and CO2 emissions reduction of about 3.3%. If the technology is also applied to other types of ethylene pyrolysis furnaces, total energy savings and CO2 emissions reductions could increase by up to five times. The work involved: Developing powder and consolidation processing protocols to produce an oxide-dispersion strengthened variant of Alloy 803 exhibiting creep strength comparable to Incoloy? Alloy MA956, Developing a direct powder co-extrusion protocol for fabricating co-extruded bimetallic Incoloy? Alloy MA956 / ODS Alloy 803 tubes, Characterizing the properties of the ODS Alloy 803 material, the welding characteristics of the bimetallic tubes, and the coking characteristics of the Incoloy? MA956 alloy, and Documenting the potential energy savings and user requirements for these bimetallic pyrolysis furnace tubes. The project demonstrated that oxide dispersion strengthened Alloy 803 can be produced successfully using conventional mechanical alloying technology. The oxide dispersion strengthened bimetallic radiant coil technology explored under this program has significant potential for energy savings and productivity improvements for domestic ethylene producers. In today's competitive market, however, domestic furnace manufacturers and ethylene producers appear reluctant to pay any cost premium for higher-performance coil materials offering either higher temperature capabilities or longer service life. Interest in oxide dispersion strengthened radiant coils is likely to increase if furnace and ethylene producers begin to focus more on increasing tube wall temperatures to improve productivity.

  16. Uranium resources: Issues and facts

    SciTech Connect (OSTI)

    Delene, J.G.

    1993-12-31T23:59:59.000Z

    Although there are several secondary issues, the most important uranium resource issue is, ``will there be enough uranium available at a cost which will allow nuclear power to be competitive in the future?`` This paper will attempt to answer this question by discussing uranium supply, demand, and economics from the perspective of the United States. The paper will discuss: how much uranium is available; the sensitivity of nuclear power costs to uranium price; the potential future demand for uranium in the Unites States, some of the options available to reduce this demand, the potential role of the Advanced Liquid Metal Cooled Reactor (ALMR) in reducing uranium demand; and potential alternative uranium sources and technologies.

  17. Uranium-titanium-niobium alloy

    DOE Patents [OSTI]

    Ludtka, Gail M. (Oak Ridge, TN); Ludtka, Gerard M. (Oak Ridge, TN)

    1990-01-01T23:59:59.000Z

    A uranium alloy having small additions of Ti and Nb shows improved strength and ductility in cross section of greater than one inch over prior uranium alloy having only Ti as an alloying element.

  18. Microsoft PowerPoint - PGDP Industry Day Overview Presentation...

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

    Ordnance Works site for the second of three planned uranium enrichment plants. * Construction began in 1951. The first product was shipped in 1952. * Construction 1951-54 *...

  19. Stumbling Toward Capitalism: The State, Global Production Networks, and the Unexpected Emergence of China's Independent Auto Industry

    E-Print Network [OSTI]

    Chang, Crystal Whai-ku

    2011-01-01T23:59:59.000Z

    a division of SGM) PLM Product lifecycle management R&Ddesign software. Product lifecycle management (PLM) software

  20. Corrosion-resistant uranium

    DOE Patents [OSTI]

    Hovis, V.M. Jr.; Pullen, W.C.; Kollie, T.G.; Bell, R.T.

    1981-10-21T23:59:59.000Z

    The present invention is directed to the protecting of uranium and uranium alloy articles from corrosion by providing the surfaces of the articles with a layer of an ion-plated metal selected from aluminum and zinc to a thickness of at least 60 microinches and then converting at least the outer surface of the ion-plated layer of aluminum or zinc to aluminum chromate or zinc chromate. This conversion of the aluminum or zinc to the chromate form considerably enhances the corrosion resistance of the ion plating so as to effectively protect the coated article from corrosion.

  1. A National Resource for Industry

    E-Print Network [OSTI]

    alloys, and metal matrix composite products carbon fibe's manufacturing industries. These industries call upon ORNL's expertise in materials synthesis, characterization-efficient manufacturing processes and materials targeting products of the future. The Department of Energy's first

  2. Preparation of High Purity, High Molecular-Weight Chitin from Ionic Liquids for Use as an Adsorbate for the Extraction of Uranium from Seawater (Workscope MS-FC: Fuel Cycle R&D)

    SciTech Connect (OSTI)

    Rogers, Robin

    2013-12-21T23:59:59.000Z

    Ensuring a domestic supply of uranium is a key issue facing the wider implementation of nuclear power. Uranium is mostly mined in Kazakhstan, Australia, and Canada, and there are few high-grade uranium reserves left worldwide. Therefore, one of the most appealing potential sources of uranium is the vast quantity dissolved in the oceans (estimated to be 4.4 billion tons worldwide). There have been research efforts centered on finding a means to extract uranium from seawater for decades, but so far none have resulted in an economically viable product, due in part to the fact that the materials that have been successfully demonstrated to date are too costly (in terms of money and energy) to produce on the necessary scale. Ionic Liquids (salts which melt below 100{degrees}C) can completely dissolve raw crustacean shells, leading to recovery of a high purity, high molecular weight chitin powder and to fibers and films which can be spun directly from the extract solution suggesting that continuous processing might be feasible. The work proposed here will utilize the unprecedented control this makes possible over the chitin fiber a) to prepare electrospun nanofibers of very high surface area and in specific architectures, b) to modify the fiber surfaces chemically with selective extractant capacity, and c) to demonstrate their utility in the direct extraction and recovery of uranium from seawater. This approach will 1) provide direct extraction of chitin from shellfish waste thus saving energy over the current industrial process for obtaining chitin; 2) allow continuous processing of nanofibers for very high surface area fibers in an economical operation; 3) provide a unique high molecular weight chitin not available from the current industrial process leading to stronger, more durable fibers; and 4) allow easy chemical modification of the large surface areas of the fibers for appending uranyl selective functionality providing selectivity and ease of stripping. The resulting sorbent should prove economically feasible, as well as providing an overall net energy gain.

  3. Process for producing enriched uranium having a {sup 235}U content of at least 4 wt. % via combination of a gaseous diffusion process and an atomic vapor laser isotope separation process to eliminate uranium hexafluoride tails storage

    DOE Patents [OSTI]

    Horton, J.A.; Hayden, H.W. Jr.

    1995-05-30T23:59:59.000Z

    An uranium enrichment process capable of producing an enriched uranium, having a {sup 235}U content greater than about 4 wt. %, is disclosed which will consume less energy and produce metallic uranium tails having a lower {sup 235}U content than the tails normally produced in a gaseous diffusion separation process and, therefore, eliminate UF{sub 6} tails storage and sharply reduce fluorine use. The uranium enrichment process comprises feeding metallic uranium into an atomic vapor laser isotope separation process to produce an enriched metallic uranium isotopic mixture having a {sup 235} U content of at least about 2 wt. % and a metallic uranium residue containing from about 0.1 wt. % to about 0.2 wt. % {sup 235} U; fluorinating this enriched metallic uranium isotopic mixture to form UF{sub 6}; processing the resultant isotopic mixture of UF{sub 6} in a gaseous diffusion process to produce a final enriched uranium product having a {sup 235}U content of at least 4 wt. %, and up to 93.5 wt. % or higher, of the total uranium content of the product, and a low {sup 235}U content UF{sub 6} having a {sup 235}U content of about 0.71 wt. % of the total uranium content of the low {sup 235}U content UF{sub 6}; and converting this low {sup 235}U content UF{sub 6} to metallic uranium for recycle to the atomic vapor laser isotope separation process. 4 figs.

  4. Process for producing enriched uranium having a .sup.235 U content of at least 4 wt. % via combination of a gaseous diffusion process and an atomic vapor laser isotope separation process to eliminate uranium hexafluoride tails storage

    DOE Patents [OSTI]

    Horton, James A. (Livermore, CA); Hayden, Jr., Howard W. (Oakridge, TN)

    1995-01-01T23:59:59.000Z

    An uranium enrichment process capable of producing an enriched uranium, having a .sup.235 U content greater than about 4 wt. %, is disclosed which will consume less energy and produce metallic uranium tails having a lower .sup.235 U content than the tails normally produced in a gaseous diffusion separation process and, therefore, eliminate UF.sub.6 tails storage and sharply reduce fluorine use. The uranium enrichment process comprises feeding metallic uranium into an atomic vapor laser isotope separation process to produce an enriched metallic uranium isotopic mixture having a .sup.235 U content of at least about 2 wt. % and a metallic uranium residue containing from about 0.1 wt. % to about 0.2 wt. % .sup.235 U; fluorinating this enriched metallic uranium isotopic mixture to form UF.sub.6 ; processing the resultant isotopic mixture of UF.sub.6 in a gaseous diffusion process to produce a final enriched uranium product having a .sup.235 U content of at least 4 wt. %, and up to 93.5 wt. % or higher, of the total uranium content of the product, and a low .sup.235 U content UF.sub.6 having a .sup.235 U content of about 0.71 wt. % of the total uranium content of the low .sup.235 U content UF.sub.6 ; and converting this low .sup.235 U content UF.sub.6 to metallic uranium for recycle to the atomic vapor laser isotope separation process.

  5. High loading uranium fuel plate

    DOE Patents [OSTI]

    Wiencek, Thomas C. (Bolingbrook, IL); Domagala, Robert F. (Indian Head Park, IL); Thresh, Henry R. (Palos Heights, IL)

    1990-01-01T23:59:59.000Z

    Two embodiments of a high uranium fuel plate are disclosed which contain a meat comprising structured uranium compound confined between a pair of diffusion bonded ductile metal cladding plates uniformly covering the meat, the meat having a uniform high fuel loading comprising a content of uranium compound greater than about 45 Vol. % at a porosity not greater than about 10 Vol. %. In a first embodiment, the meat is a plurality of parallel wires of uranium compound. In a second embodiment, the meat is a dispersion compact containing uranium compound. The fuel plates are fabricated by a hot isostatic pressing process.

  6. Phosphate Barriers for Immobilization of Uranium Plumes

    SciTech Connect (OSTI)

    Burns, Peter C.

    2004-12-01T23:59:59.000Z

    Uranium contamination of the subsurface remains a persistent problem plaguing remedial design at sites across the U.S. that were involved with production, handling, storage, milling, and reprocessing of uranium for both civilian and defense related purposes. Remediation efforts to date have relied upon excavation, pump-and-treat, or passive remediation barriers (PRB?s) to remove or attenuate uranium mobility. Documented cases convincingly demonstrate that excavation and pump-and-treat methods are ineffective for a number of highly contaminated sites. There is growing concern that use of conventional PRB?s, such as zero-valent iron, may be a temporary solution to a problem that will persist for thousands of years. Alternatives to the standard treatment methods are therefore warranted. The core objective of our research is to demonstrate that a phosphorus amendment strategy will result in a reduction of dissolved uranium to below the proposed drinking water standard. Our hypothesis is that long-chain sodium polyphosphate compounds forestall precipitation of sparingly soluble uranyl phosphate compounds, which is paramount to preventing fouling of wells at the point of injection.

  7. Derivation of uranium residual radioactive material guidelines for the Shpack site

    SciTech Connect (OSTI)

    Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

    1991-08-01T23:59:59.000Z

    Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs.

  8. Energy balance for uranium recovery from seawater

    SciTech Connect (OSTI)

    Schneider, E.; Lindner, H. [The University of Texas, 1 University Station C2200, Austin, TX 78712 (United States)

    2013-07-01T23:59:59.000Z

    The energy return on investment (EROI) of an energy resource is the ratio of the energy it ultimately produces to the energy used to recover it. EROI is a key viability measure for a new recovery technology, particularly in its early stages of development when financial cost assessment would be premature or highly uncertain. This paper estimates the EROI of uranium recovery from seawater via a braid adsorbent technology. In this paper, the energy cost of obtaining uranium from seawater is assessed by breaking the production chain into three processes: adsorbent production, adsorbent deployment and mooring, and uranium elution and purification. Both direct and embodied energy inputs are considered. Direct energy is the energy used by the processes themselves, while embodied energy is used to fabricate their material, equipment or chemical inputs. If the uranium is used in a once-through fuel cycle, the braid adsorbent technology EROI ranges from 12 to 27, depending on still-uncertain performance and system design parameters. It is highly sensitive to the adsorbent capacity in grams of U captured per kg of adsorbent as well as to potential economies in chemical use. This compares to an EROI of ca. 300 for contemporary terrestrial mining. It is important to note that these figures only consider the mineral extraction step in the fuel cycle. At a reference performance level of 2.76 g U recovered per kg adsorbent immersed, the largest energy consumers are the chemicals used in adsorbent production (63%), anchor chain mooring system fabrication and operations (17%), and unit processes in the adsorbent production step (12%). (authors)

  9. Matrix Infrared Spectroscopic and Computational Investigations of Novel Small Uranium Containing Molecules - Final Technical Report

    SciTech Connect (OSTI)

    Andrews, Lester

    2014-10-17T23:59:59.000Z

    Direct reactions of f-element uranium, thorium and lanthanide metal atoms were investigated with small molecules. These metal atoms were generated by laser ablation and mixed with the reagent molecules then condensed with noble gases at 4K. The products were analyzed by absorption of infrared light to measure vibrational frequencies which were confirmed by quantum chemical calculations. We have learned more about the reactivity of uranium atoms with common molecules, which will aid in the develolpment of further applications of uranium.

  10. Uranium-series constraints on radionuclide transport and groundwater flow at the Nopal I uranium deposit, Sierra Pena Blanca, Mexico

    SciTech Connect (OSTI)

    Goldstein, S.J.; Abdel-Fattah, A.I.; Murrell, M.T.; Dobson, P.F.; Norman, D.E.; Amato, R.S.; Nunn, A. J.

    2009-10-01T23:59:59.000Z

    Uranium-series data for groundwater samples from the Nopal I uranium ore deposit were obtained to place constraints on radionuclide transport and hydrologic processes for a nuclear waste repository located in fractured, unsaturated volcanic tuff. Decreasing uranium concentrations for wells drilled in 2003 are consistent with a simple physical mixing model that indicates that groundwater velocities are low ({approx}10 m/y). Uranium isotopic constraints, well productivities, and radon systematics also suggest limited groundwater mixing and slow flow in the saturated zone. Uranium isotopic systematics for seepage water collected in the mine adit show a spatial dependence which is consistent with longer water-rock interaction times and higher uranium dissolution inputs at the front adit where the deposit is located. Uranium-series disequilibria measurements for mostly unsaturated zone samples indicate that {sup 230}Th/{sup 238}U activity ratios range from 0.005-0.48 and {sup 226}Ra/{sup 238}U activity ratios range from 0.006-113. {sup 239}Pu/{sup 238}U mass ratios for the saturated zone are <2 x 10{sup -14}, and Pu mobility in the saturated zone is >1000 times lower than the U mobility. Saturated zone mobility decreases in the order {sup 238}U{approx}{sup 226}Ra > {sup 230}Th{approx}{sup 239}Pu. Radium and thorium appear to have higher mobility in the unsaturated zone based on U-series data from fractures and seepage water near the deposit.

  11. Uranium from seawater

    SciTech Connect (OSTI)

    Gregg, D.; Folkendt, M.

    1982-09-21T23:59:59.000Z

    A novel process for recovering uranium from seawater is proposed and some of the critical technical parameters are evaluated. The process, in summary, consists of two different options for contacting adsorbant pellets with seawater without pumping the seawater. It is expected that this will reduce the mass handling requirements, compared to pumped seawater systems, by a factor of approximately 10/sup 5/, which should also result in a large reduction in initial capital investment. Activated carbon, possibly in combination with a small amount of dissolved titanium hydroxide, is expected to be the preferred adsorbant material instead of the commonly assumed titanium hydroxide alone. The activated carbon, after exposure to seawater, can be stripped of uranium with an appropriate eluant (probably an acid) or can be burned for its heating value (possible in a power plant) leaving the uranium further enriched in its ash. The uranium, representing about 1% of the ash, is then a rich ore and would be recovered in a conventional manner. Experimental results have indicated that activated carbon, acting alone, is not adequately effective in adsorbing the uranium from seawater. We measured partition coefficients (concentration ratios) of approximately 10/sup 3/ in seawater instead of the reported values of 10/sup 5/. However, preliminary tests carried out in fresh water show considerable promise for an extraction system that uses a combination of dissolved titanium hydroxide (in minute amounts) which forms an insoluble compound with the uranyl ion, and the insoluble compound then being sorbed out on activated carbon. Such a system showed partition coefficients in excess of 10/sup 5/ in fresh water. However, the system was not tested in seawater.

  12. Innovation and the state : development strategies for high technology industries in a world of fragmented production : Israel, Ireland, and Taiwan

    E-Print Network [OSTI]

    Breznitz, Dan

    2005-01-01T23:59:59.000Z

    One of the most unexpected changes of the 1990s is that firms in a number of emerging economies not previously known for their high-technology industries have leapfrogged to the forefront in new Information Technologies ...

  13. Aluminum and polymeric coatings for protection of uranium

    SciTech Connect (OSTI)

    Colmenares, C.; McCreary, T.; Monaco, S.; Walkup, C.; Gleeson, G.; Kervin, J.; Smith, R.L.; McCaffrey, C.

    1983-12-21T23:59:59.000Z

    Ion-plated aluminum films on uranium will not provide adequate protection for 25 years. Magnetron-plated aluminum films on uranium are much better than ion-plated ones. Kel-F 800 films on uranium can provide adequate protection for 25 years. Their use in production must be delayed until the following factors are sorted out: water permeability in Kel-F 800 must be determined between 30 and 60/sup 0/C; the effect of UF/sub 3/, at the Kel-F/metal interface, on the permeability of water must be assessed; and the effect of crystallinity on water permeability must be evaluated. Applying Kel-F films on aluminum ion-plated uranium provides a good interim solution for long term storage.

  14. Method of preparation of uranium nitride

    DOE Patents [OSTI]

    Kiplinger, Jaqueline Loetsch; Thomson, Robert Kenneth James

    2013-07-09T23:59:59.000Z

    Method for producing terminal uranium nitride complexes comprising providing a suitable starting material comprising uranium; oxidizing the starting material with a suitable oxidant to produce one or more uranium(IV)-azide complexes; and, sufficiently irradiating the uranium(IV)-azide complexes to produce the terminal uranium nitride complexes.

  15. URANIUM MILLING ACTIVITIES AT SEQUOYAH FUELS CORPORATION

    E-Print Network [OSTI]

    unknown authors

    Sequoyah Fuels Corporation (SFC) describes previous operations at its Gore, Oklahoma, uranium conversion facility as: (1) the recovery of uranium by concentration and purification processes; and (2) the conversion of concentrated and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these

  16. Method for fabricating uranium foils and uranium alloy foils

    DOE Patents [OSTI]

    Hofman, Gerard L. (Downers Grove, IL); Meyer, Mitchell K. (Idaho Falls, ID); Knighton, Gaven C. (Moore, ID); Clark, Curtis R. (Idaho Falls, ID)

    2006-09-05T23:59:59.000Z

    A method of producing thin foils of uranium or an alloy. The uranium or alloy is cast as a plate or sheet having a thickness less than about 5 mm and thereafter cold rolled in one or more passes at substantially ambient temperatures until the uranium or alloy thereof is in the shape of a foil having a thickness less than about 1.0 mm. The uranium alloy includes one or more of Zr, Nb, Mo, Cr, Fe, Si, Ni, Cu or Al.

  17. Surface and subsurface characterization of uranium contamination at the Fernald environmental management site

    SciTech Connect (OSTI)

    Schilk, A.J.; Perkins, R.W.; Abel, K.H.; Brodzinski, R.L.

    1993-04-01T23:59:59.000Z

    The past operations of uranium production and support facilities at several Department of Energy (DOE) sites have occasionally resulted in the local contamination of some surface and subsurface soils, and the three-dimensional distribution of the uranium at these sites must be thoroughly characterized before any effective remedial protocols can be established. To this end, Pacific Northwest Laboratory (PNL) has been tasked by the DOE`s Office of Technology Development with adapting, developing, and demonstrating technologies for the measurement of uranium in surface and subsurface soils at the Fernald Uranium in Soils Integrated Demonstration site. These studies are detailed in this report.

  18. Containment and storage of uranium hexafluoride at US Department of Energy uranium enrichment plants

    SciTech Connect (OSTI)

    Barlow, C.R.; Alderson, J.H.; Blue, S.C.; Boelens, R.A.; Conkel, M.E.; Dorning, R.E.; Ecklund, C.D.; Halicks, W.G.; Henson, H.M.; Newman, V.S.; Philpot, H.E.; Taylor, M.S.; Vournazos, J.P. [Oak Ridge K-25 Site, TN (United States). UEO Enrichment Technical Operations Div.; Russell, J.R. [USDOE Oak Ridge Field Office, TN (United States); Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States); Ziehlke, K.T. [MJB Technical Associates (United States)

    1992-07-01T23:59:59.000Z

    Isotopically depleted UF{sub 6} (uranium hexafluoride) accumulates at a rate five to ten times greater than the enriched product and is stored in steel vessels at the enrichment plant sites. There are approximately 55,000 large cylinders now in storage at Paducah, Kentucky; Portsmouth, Ohio; and Oak Ridge, Tennessee. Most of them contain a nominal 14 tons of depleted UF{sub 6}. Some of these cylinders have been in the unprotected outdoor storage environment for periods approaching 40 years. Storage experience, supplemented by limited corrosion data, suggests a service life of about 70 years under optimum conditions for the 48-in. diameter, 5/16-in.-wall pressure vessels (100 psi working pressure), using a conservative industry-established 1/4-in.-wall thickness as the service limit. In the past few years, however, factors other than atmospheric corrosion have become apparent that adversely affect the serviceability of small numbers of the storage containers and that indicate the need for a managed program to ensure maintenance ofcontainment integrity for all the cylinders in storage. The program includes periodic visual inspections of cylinders and storage yards with documentation for comparison with other inspections, a group of corrosion test programs to permit cylinder life forecasts, and identification of (and scheduling for remedial action) situations in which defects, due to handling damage or accelerated corrosion, can seriously shorten the storage life or compromise the containment integrity of individual cylinders. The program also includes rupture testing to assess the effects of certain classes of damage on overall cylinder strength, aswell as ongoing reviews of specifications, procedures, practices, and inspection results to effect improvements in handling safety, containment integrity, and storage life.

  19. Achieving and sustaining an optimal product portfolio in the healthcare industry through SKU rationalization, complexity costing, and dashboards

    E-Print Network [OSTI]

    Hilliard, David (David John)

    2012-01-01T23:59:59.000Z

    After years of new product launches, and entry into emerging markets, Company X, a healthcare company, has seen its product portfolio proliferate and bring costly complexity into its operations. Today, Company X seeks to ...

  20. Stumbling Toward Capitalism: The State, Global Production Networks, and the Unexpected Emergence of China's Independent Auto Industry

    E-Print Network [OSTI]

    Chang, Crystal Whai-ku

    2011-01-01T23:59:59.000Z

    Center (a division of SGM) PLM Product lifecycle managementProduct lifecycle management (PLM) software is used by cara French firm, provides PLM software to most of the world‘s

  1. Recovery of uranium from seawater

    SciTech Connect (OSTI)

    Sugasaka, K. (Government Industrial Research Inst., Shikoku, Japan); Katoh, S.; Takai, N.; Takahashi, H.; Umezawa, Y.

    1981-01-01T23:59:59.000Z

    Seawater contains various elements in solution. Deuterium, lithium, and uranium are the important ingredients for energy application at present and in the future. This paper deals with the recovery of uranium from seawater, with emphasis on the development of an adsorbent with high selectivity and rate of adsorption for uranium. Polyacrylamidoxime chelating resins were synthesized from various co-polymers of acrylonitrile and cross-linking agents. The resulting resins with the chelating amidoxime group showed selective adsorption for uranium in seawater. The amount of uranium adsorbed from seawater at room temperature reached 3.2 mg/g resin after 180 days. Polyacrylamidoxime fiber, which was prepared from polyacrylonitrile fiber and hydroxylamine, showed a high rate of adsorption for uranium. The polyacrylamidoxime fiber conditioned with 1 M HC1 and 1 M NaOH adsorbed 4 mg U/g fiber from seawater in ten days. 9 figures, 6 tables.

  2. Ionic Liquids as templating agents in formation of uranium-containing nanomaterials

    SciTech Connect (OSTI)

    Visser, Ann E; Bridges, Nicholas J

    2014-06-10T23:59:59.000Z

    A method for forming nanoparticles containing uranium oxide is described. The method includes combining a uranium-containing feedstock with an ionic liquid to form a mixture and holding the mixture at an elevated temperature for a period of time to form the product nanoparticles. The method can be carried out at low temperatures, for instance less than about 300.degree. C.

  3. Uranium Oxide Aerosol Transport in Porous Graphite

    SciTech Connect (OSTI)

    Blanchard, Jeremy; Gerlach, David C.; Scheele, Randall D.; Stewart, Mark L.; Reid, Bruce D.; Gauglitz, Phillip A.; Bagaasen, Larry M.; Brown, Charles C.; Iovin, Cristian; Delegard, Calvin H.; Zelenyuk, Alla; Buck, Edgar C.; Riley, Brian J.; Burns, Carolyn A.

    2012-01-23T23:59:59.000Z

    The objective of this paper is to investigate the transport of uranium oxide particles that may be present in carbon dioxide (CO2) gas coolant, into the graphite blocks of gas-cooled, graphite moderated reactors. The transport of uranium oxide in the coolant system, and subsequent deposition of this material in the graphite, of such reactors is of interest because it has the potential to influence the application of the Graphite Isotope Ratio Method (GIRM). The GIRM is a technology that has been developed to validate the declared operation of graphite moderated reactors. GIRM exploits isotopic ratio changes that occur in the impurity elements present in the graphite to infer cumulative exposure and hence the reactor’s lifetime cumulative plutonium production. Reference Gesh, et. al., for a more complete discussion on the GIRM technology.

  4. Disposition of Surplus Highly Enriched Uranium

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

    four alternatives that would eliminate the weapons-usability of HEU by blending it with depleted uranium, natural uranium, or low-enriched uranium (LEU) to create LEU, either as...

  5. Uranium for hydrogen storage applications : a materials science perspective.

    SciTech Connect (OSTI)

    Shugard, Andrew D.; Tewell, Craig R.; Cowgill, Donald F.; Kolasinski, Robert D.

    2010-08-01T23:59:59.000Z

    Under appropriate conditions, uranium will form a hydride phase when exposed to molecular hydrogen. This makes it quite valuable for a variety of applications within the nuclear industry, particularly as a storage medium for tritium. However, some aspects of the U+H system have been characterized much less extensively than other common metal hydrides (particularly Pd+H), likely due to radiological concerns associated with handling. To assess the present understanding, we review the existing literature database for the uranium hydride system in this report and identify gaps in the existing knowledge. Four major areas are emphasized: {sup 3}He release from uranium tritides, the effects of surface contamination on H uptake, the kinetics of the hydride phase formation, and the thermal desorption properties. Our review of these areas is then used to outline potential avenues of future research.

  6. Uranium in prehistoric Indian pottery

    E-Print Network [OSTI]

    Filberth, Ernest William

    1976-01-01T23:59:59.000Z

    URANIUM IN PREHISTORIC INDIAN POTTERY A Thesis by ERNEST WILLIAM FILBERTH Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE December 1976 Major Subject...: Chemistry URANIUM IN PREHISTORIC INDIAN POTTERY A Thesis by ERNEST WILLIAM FILBERTH Approved as to style and content by: (Chairman of Committee) (Head of Department) (Member) (Membe (Member) (Member) December 1976 ABSTRACT Uranium in Prehistoric...

  7. CRAD, Occupational Safety & Health- Y-12 Enriched Uranium Operations Oxide Conversion Facility

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January 2005 assessment of Industrial Safety and Industrial Health programs at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

  8. Industrial policy and the Indian electronics industry

    E-Print Network [OSTI]

    Love, Robert (Robert Eric)

    2008-01-01T23:59:59.000Z

    Recently, production within India's Electronics sector amounted to a low $12 billion when compared to the global output of $1400 billion. The slow growth in the local industry is often judged to be the result of late ...

  9. U.S. Environmental Protection Agency Evaluation of Uranium Mining TENORM Wastes-Characteristics, Occurrence, and Risks

    SciTech Connect (OSTI)

    Setlow, L.W. [U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (6608J), Washington, DC (United States); Peake, R.T. [U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (6608J), Washington, DC (United States)

    2007-07-01T23:59:59.000Z

    The U.S. Environmental Protection Agency is completing a multi year effort to issue technical reports and obtain stakeholder views on future programs to mitigate potential hazards associated with uranium mining Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM). The technical reports are the most comprehensive issued by the Agency on this topic, and should have utility for reclamation of abandoned uranium mines, as well as providing information for new mines proposed by the uranium mining industry. This presentation will provide principal results of the three technical reports issued, and elements of the proposed EPA program for uranium mining TENORM. (authors)

  10. anthropogenic uranium enrichments: Topics by E-print Network

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

    Websites Summary: Flats Plutonium and Uranium Weapons-Grade Plutonium Enriched Uranium Depleted Uranium Plutonium-238 0.01 - 0.05% Uranium-234 0.1 - 1.02% Uranium-234...

  11. EIS-0359: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site

    Broader source: Energy.gov [DOE]

    This site-specific EIS considers the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three locations within the Paducah site; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride (HF) produced as a conversion co-product; and neutralization of HF to calcium fluoride and its sale or disposal in the event that the HF product is not sold.

  12. Separation of uranium from technetium in recovery of spent nuclear fuel

    DOE Patents [OSTI]

    Friedman, H.A.

    1984-06-13T23:59:59.000Z

    A method for decontaminating uranium product from the Purex 5 process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO/sub 2//sup 2 +/) uranium and heptavalent technetium (TcO/sub 4/-). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H/sub 2/C/sub 2/O/sub 4/), and the Tc-oxalate complex is readily separated from the 10 uranium by solvent extraction with 30 vol % tributyl phosphate in n-dodecane.

  13. Standard specification for sintered gadolinium oxide-uranium dioxide pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01T23:59:59.000Z

    1.1 This specification is for finished sintered gadolinium oxide-uranium dioxide pellets for use in light-water reactors. It applies to gadolinium oxide-uranium dioxide pellets containing uranium of any 235U concentration and any concentration of gadolinium oxide. 1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for gadolinium oxide-uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design. 1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aw...

  14. Disposition of Surplus Highly Enriched Uranium

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

    of Surplus Highly Enriched Uranium Environmental Impact Statement kternationd Atomic Energy Agency Idaho Nationrd Engineering Laborato low-enriched uranium low-level waste...

  15. Unexpected, Stable Form of Uranium Detected | EMSL

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

    Unexpected, Stable Form of Uranium Detected Unexpected, Stable Form of Uranium Detected Insights on underappreciated reaction could shed light on environmental cleanup options...

  16. Uranium Weapons Components Successfully Dismantled | National...

    National Nuclear Security Administration (NNSA)

    Our Jobs Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline Uranium Weapons Components Successfully Dismantled Uranium Weapons Components Successfully...

  17. Adsorptive Stripping Voltammetric Measurements of Trace Uranium...

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

    Adsorptive Stripping Voltammetric Measurements of Trace Uranium at the Bismuth Film Electrode. Adsorptive Stripping Voltammetric Measurements of Trace Uranium at the Bismuth Film...

  18. Uranium Enrichment Decontamination and Decommissioning Fund's...

    Office of Environmental Management (EM)

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2008 and 2007 Financial Statement Audit, OAS-FS-10-05 Uranium Enrichment Decontamination and...

  19. Industrial Permit

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

    Protection Obeying Environmental Laws Industrial Permit Industrial Permit The Industrial Permit authorizes the Laboratory to discharge point-source effluents under the...

  20. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal, Annual Progress Report, October 1, 2005 through September 30, 2006

    SciTech Connect (OSTI)

    Bruce G. Miller

    2006-09-29T23:59:59.000Z

    Since 1998, The Pennsylvania State University has been successfully managing the Consortium for Premium Carbon Products from Coal (CPCPC), which is a vehicle for industry-driven research on the promotion, development, and transfer of innovative technology on premium carbon produces from coal to the U.S. industry. The CPCPC is an initiative being led by Penn State, its co-charter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provides the base funding for the program, with Penn State responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity has continued under the present cooperative agreement, No. DE-FC26-03NT41874, which started October 1, 2003. The objective of the second agreement is to continue the successful operation of the CPCPC. The CPCPC has enjoyed tremendous success with its organizational structure, that includes Penn State and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC is its industry-led council that selects proposals submitted by CPCPC members to ensure CPCPC target areas have strong industrial support. Base funding for the selected projects is provided by NETL with matching funds from industry. At the annual funding meeting held in October 2003, ten projects were selected for funding. Subcontracts were let from Penn State to the subcontractors on March 1, 2004. Nine of the ten 2004 projects were completed during the previous annual reporting period and their final reports were submitted with the previous annual report (i.e., 10/01/04-09/30/05). The final report for the remaining project, which was submitted during this reporting period (i.e., 10/01/05-09/30/06), is attached. At the annual funding meeting held in November 2004, eleven projects were selected for funding. Subcontracts were let from Penn State to the subcontractors on March 1, 2005. Three additional projects were selected for funding during the April 2005 tutorial/funding meeting. Subcontracts were let from Penn State to the subcontractors on July 1, 2005. Of these fourteen 2005 projects, eleven have been completed and the final reports are attached. An annual funding meeting was held in November 2005 and the council selected five projects for funding. Subcontracts were let from Penn State to the subcontractors on March 1, 2006, except for one that started October 1, 2006.

  1. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal, Annual Progress Report, October 1, 2004 through September 30, 2005

    SciTech Connect (OSTI)

    Miller, Bruce G

    2006-03-01T23:59:59.000Z

    Since 1998, The Pennsylvania State University (PSU) has been successfully operating the Consortium for Premium Carbon Products from Coal (CPCPC), which is a vehicle for industry-driven research on the promotion, development, and transfer of innovative technology on premium carbon produces from coal to the U.S. industry. The CPCPC is an initiative being led by PSU, its co-charter member West Virginia University (WVU), and the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL), who also provides the base funding for the program, with PSU responsible for consortium management. CPCPC began in 1998 under DOE Cooperative Agreement No. DE-FC26-98FT40350. This agreement ended November 2004 but the CPCPC activity has continued under the present cooperative agreement, No. DE-FC26-03NT41874, which started October 1, 2003. The objective of the second agreement is to continue the successful operation of the CPCPC. The CPCPC has enjoyed tremendous success with its organizational structure, that includes PSU and WVU as charter members, numerous industrial affiliate members, and strategic university affiliate members together with NETL, forming a vibrant and creative team for innovative research in the area of transforming coal to carbon products. The key aspect of CPCPC is its industry-led council that selects proposals submitted by CPCPC members to ensure CPCPC target areas have strong industrial support. A second contract was executed with DOE NETL starting in October 2003 to continue the activities of CPCPC. An annual funding meeting was held in October 2003 and the council selected ten projects for funding. Base funding for the projects is provided by NETL with matching funds from industry. Subcontracts were let from Penn State to the subcontractors on March 1, 2004. Nine of the ten projects have been completed and the final reports for these 2004 projects are attached. An annual funding meeting was held in November 2004 and the council selected eleven projects for funding. Subcontracts were let from Penn State to the subcontractors on March 1, 2005. Three additional projects were selected for funding during the April 2005 tutorial/funding meeting. Subcontracts were let from Penn State to the subcontractors on July 1, 2005.

  2. Conversion of depleted uranium hexafluoride to a solid uranium compound

    DOE Patents [OSTI]

    Rothman, Alan B. (Willowbrook, IL); Graczyk, Donald G. (Lemont, IL); Essling, Alice M. (Elmhurst, IL); Horwitz, E. Philip (Naperville, IL)

    2001-01-01T23:59:59.000Z

    A process for converting UF.sub.6 to a solid uranium compound such as UO.sub.2 and CaF. The UF.sub.6 vapor form is contacted with an aqueous solution of NH.sub.4 OH at a pH greater than 7 to precipitate at least some solid uranium values as a solid leaving an aqueous solution containing NH.sub.4 OH and NH.sub.4 F and remaining uranium values. The solid uranium values are separated from the aqueous solution of NH.sub.4 OH and NH.sub.4 F and remaining uranium values which is then diluted with additional water precipitating more uranium values as a solid leaving trace quantities of uranium in a dilute aqueous solution. The dilute aqueous solution is contacted with an ion-exchange resin to remove substantially all the uranium values from the dilute aqueous solution. The dilute solution being contacted with Ca(OH).sub.2 to precipitate CaF.sub.2 leaving dilute NH.sub.4 OH.

  3. 2015-01-16 Issuance: Energy Efficiency Program for Consumer Products and Commercial and Industrial Equipment: Notice of Information Collection Extension

    Broader source: Energy.gov [DOE]

    This document is a pre-publication Federal Register notice of information collection extension regarding consumer products and commercial and industrial equipment, as issued by the Deputy Assistant Secretary for Energy Efficiency on January 16, 2015. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  4. Radio-Ecological Conditions of Groundwater in the Area of Uranium Mining and Milling Facility - 13525

    SciTech Connect (OSTI)

    Titov, A.V.; Semenova, M.P.; Seregin, V.A.; Isaev, D.V.; Metlyaev, E.G. [FSBU SRC A.I.Burnasyan Federal Medical Biophysical Center of FMBA of Russia, Zhivopisnaya Street, 46, Moscow (Russian Federation)] [FSBU SRC A.I.Burnasyan Federal Medical Biophysical Center of FMBA of Russia, Zhivopisnaya Street, 46, Moscow (Russian Federation); Glagolev, A.V.; Klimova, T.I.; Sevtinova, E.B. [FSESP 'Hydrospecgeologiya' (Russian Federation)] [FSESP 'Hydrospecgeologiya' (Russian Federation); Zolotukhina, S.B.; Zhuravleva, L.A. [FSHE 'Centre of Hygiene and Epidemiology no. 107' under FMBA of Russia (Russian Federation)] [FSHE 'Centre of Hygiene and Epidemiology no. 107' under FMBA of Russia (Russian Federation)

    2013-07-01T23:59:59.000Z

    Manmade chemical and radioactive contamination of groundwater is one of damaging effects of the uranium mining and milling facilities. Groundwater contamination is of special importance for the area of Priargun Production Mining and Chemical Association, JSC 'PPMCA', because groundwater is the only source of drinking water. The paper describes natural conditions of the site, provides information on changes of near-surface area since the beginning of the company, illustrates the main trends of contaminators migration and assesses manmade impact on the quality and mode of near-surface and ground waters. The paper also provides the results of chemical and radioactive measurements in groundwater at various distances from the sources of manmade contamination to the drinking water supply areas. We show that development of deposits, mine water discharge, leakages from tailing dams and cinder storage facility changed general hydro-chemical balance of the area, contributed to new (overlaid) aureoles and flows of scattering paragenetic uranium elements, which are much smaller in comparison with natural ones. However, increasing flow of groundwater stream at the mouth of Sukhoi Urulyungui due to technological water infiltration, mixing of natural water with filtration streams from industrial reservoirs and sites, containing elevated (relative to natural background) levels of sulfate-, hydro-carbonate and carbonate- ions, led to the development and moving of the uranium contamination aureole from the undeveloped field 'Polevoye' to the water inlet area. The aureole front crossed the southern border of water inlet of drinking purpose. The qualitative composition of groundwater, especially in the southern part of water inlet, steadily changes for the worse. The current Russian intervention levels of gross alpha activity and of some natural radionuclides including {sup 222}Rn are in excess in drinking water; regulations for fluorine and manganese concentrations are also in excess. Possible ways to improve the situation are considered. (authors)

  5. Candidate processes for diluting the {sup 235}U isotope in weapons-capable highly enriched uranium

    SciTech Connect (OSTI)

    Snider, J.D.

    1996-02-01T23:59:59.000Z

    The United States Department of Energy (DOE) is evaluating options for rendering its surplus inventories of highly enriched uranium (HEU) incapable of being used to produce nuclear weapons. Weapons-capable HEU was earlier produced by enriching uranium in the fissile {sup 235}U isotope from its natural occurring 0.71 percent isotopic concentration to at least 20 percent isotopic concentration. Now, by diluting its concentration of the fissile {sup 235}U isotope in a uranium blending process, the weapons capability of HEU can be eliminated in a manner that is reversible only through isotope enrichment, and therefore, highly resistant to proliferation. To the extent that can be economically and technically justified, the down-blended uranium product will be made suitable for use as commercial reactor fuel. Such down-blended uranium product can also be disposed of as waste if chemical or isotopic impurities preclude its use as reactor fuel.

  6. Proceedings of the Seventh Walnut Council Research Symposium 15GTR-NRS-P-115 BIOREFINERY OPPORTUNITIES FOR FOREST PRODUCTS INDUSTRIES

    E-Print Network [OSTI]

    capabilities to succeed with biorefineries. Most forest products companies already have the first capability the acquisition of woody residues for making new products while minimizing competition for valuable timber companies to look at the overall biorefinery effort and acquire the expertise to move thermal

  7. Econometric and Neural Network Analysis of the Labor Productivity and Average Gross Earnings Indices in the Romanian Industry

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Econometric and Neural Network Analysis of the Labor Productivity and Average Gross Earnings and models that were used consist of several lag econometric models, ARIMA processes, as well as feed forward AGEI and LPI. Key-Words: - labor productivity, econometric model, ARIMA, VAR, neural network, forecast

  8. CALIFORNIA ENERGY PETROLEUM INDUSTRY INFORMATION

    E-Print Network [OSTI]

    PETROLEUM AND NON-PETROLEUM ................................................... 40 PRODUCT DEFINITIONS Major Petroleum Product Storer and Terminal Weekly Report Major petroleum product storers, terminalCALIFORNIA ENERGY COMMISSION PETROLEUM INDUSTRY INFORMATION REPORTING ACT (PIIRA) PROGRAM REPORTING

  9. Uranium Marketing Annual Report -

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

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

  10. Uranium Marketing Annual Report -

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial and InstitutionalArea:Mnt(N)3. Deliveries of uranium4.

  11. Uranium Marketing Annual Report -

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at Commercial and InstitutionalArea:Mnt(N)3. Deliveries2.5.3. Uranium

  12. Innovative New Industrial Technologies: An Industry/DOE Joint Endeavor

    E-Print Network [OSTI]

    Gross, T. J.

    The Department of Energy’s Office of Industrial Programs supports research and development leading to improved energy efficiency and greater overall productivity in the industrial sector. Its basic strategy is a program of cost-shared R...

  13. Phosphate Barriers for Immobilization of Uranium Plumes

    SciTech Connect (OSTI)

    Burns, Peter C.

    2005-06-01T23:59:59.000Z

    Uranium contamination of the subsurface has remained a persistent problem plaguing remedial design at sites across the U.S. that were involved with production, handling, storage, milling, and reprocessing of fissile uranium for both civilian and defense related purposes. Remediation efforts to date have relied upon excavation, pump-and-treat, or passive remediation barriers (PRB?s) to remove or attenuate uranium mobility. Documented cases convincingly demonstrate that excavation and pump-and-treat methods are ineffective for a number of highly contaminated sites. There is growing concern that use of conventional PRB?s, such as zero-valent iron, are a temporary solution to a problem that will persist for thousands of years. Alternatives to the standard treatment methods are therefore warranted. The core objective of our research is to demonstrate that a phosphorous amendment strategy will result in a reduction of dissolved uranium to below the proposed drinking water standard. Our hypothesis is that long-chain polyphosphate compounds forestall precipitation of sparingly soluble uranyl phosphate compounds, which is key to preventing fouling of wells at the point of injection. Our other fundamental objective is to synthesize and correctly characterize the uranyl phosphate phases that form in the geochemical conditions under consideration. This report summarizes work conducted at the University of Notre Dame through November of 2003 under DOE grant DE-FG07-02ER63489, which has been funded since September, 2002. The objectives at Notre Dame are development of synthesis techniques for uranyl phosphate phases, together with detailed structural and chemical characterization of the myriad of uranyl phosphate phases that may form under geochemical conditions under consideration.

  14. The study of material accountancy procedures for uranium in a whole nuclear fuel cycle

    SciTech Connect (OSTI)

    Nakano, Hiromasa; Akiba, Mitsunori [Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

    1995-07-01T23:59:59.000Z

    Material accountancy procedures for uranium under a whole nuclear fuel cycle were studied by taking into consideration the material accountancy capability associated with realistic measurement uncertainties. The significant quantity used by the International Atomic Energy Agency (IAEA) for low-enriched uranium is 75 kg U-235 contained. A loss of U-235 contained in uranium can be detected by either of the following two procedures: one is a traditional U-235 isotope balance, and the other is a total uranium element balance. Facility types studied in this paper were UF6 conversion, gas centrifuge uranium enrichment, fuel fabrication, reprocessing, plutonium conversion, and MOX fuel production in Japan, where recycled uranium is processed in addition to natural uranium. It was found that the material accountancy capability of a total uranium element balance was almost always higher than that of a U-235 isotope balance under normal accuracy of weight, concentration, and enrichment measurements. Changing from the traditional U-235 isotope balance to the total uranium element balance for these facilities would lead to a gain of U-235 loss detection capability through material accountancy and to a reduction in the required resources of both the IAEA and operators.

  15. A multi-attribute value assessment method for the early product development phase with application to the business airplane industry

    E-Print Network [OSTI]

    Downen, Troy Douglas

    2005-01-01T23:59:59.000Z

    (cont.) market. The method is also used to extract quantitative evidence indicating the existence of enterprise-related attributes for consumer value in products. Marking the first independent review of the loss function-based ...

  16. SHEEP MOUNTAIN URANIUM PROJECT CROOKS GAP, WYOMING

    E-Print Network [OSTI]

    SHEEP MOUNTAIN URANIUM PROJECT CROOKS GAP, WYOMING US EPA Project Meeting April 7 2011April 7, 2011/Titan Uranium, VP Development · Deborah LebowAal/EPA Region 8 Air Program Introduction to Titan Uranium USA;PROJECT OVERVIEW ·Site Location·Site Location ·Fremont , Wyoming ·Existing Uranium Mine Permit 381C

  17. APPENDIX J Partition Coefficients For Uranium

    E-Print Network [OSTI]

    APPENDIX J Partition Coefficients For Uranium #12;Appendix J Partition Coefficients For Uranium J.1.0 Background The review of uranium Kd values obtained for a number of soils, crushed rock and their effects on uranium adsorption on soils are discussed below. The solution pH was also used as the basis

  18. Discovery of the actinium, thorium, protactinium, and uranium isotopes

    E-Print Network [OSTI]

    C. Fry; M. Thoennessen

    2012-03-06T23:59:59.000Z

    Currently, 31 actinium, 31 thorium, 28 protactinium, and 23 uranium isotopes have so far been observed; the discovery of these isotopes is discussed. For each isotope a brief summary of the first refereed publication, including the production and identification method, is presented.

  19. Power production and ADS

    SciTech Connect (OSTI)

    Raja, Rajendran; /Fermilab

    2010-03-01T23:59:59.000Z

    We describe the power production process in Accelerator Driven Sub-critical systems employing Thorium-232 and Uranium-238 as fuel and examine the demands on the power of the accelerator required.

  20. Safe Operating Procedure SAFETY PROTOCOL: URANIUM

    E-Print Network [OSTI]

    Farritor, Shane

    involve the use of natural or depleted uranium. Natural isotopes of uranium are U-238, U-235 and U-234 (see Table 1 for natural abundances). Depleted uranium contains less of the isotopes: U-235 and U-234. The specific activity of depleted uranium (5.0E-7 Ci/g) is less than that of natural uranium (7.1E-7 Ci

  1. Method for cleaning bomb-reduced uranium derbies

    DOE Patents [OSTI]

    Banker, John G. (Boulder, CO); Wigginton, Hubert L. (Oak Ridge, TN); Beck, David E. (Knoxville, TN); Holcombe, Cressie E. (Knoxville, TN)

    1981-01-01T23:59:59.000Z

    The concentration of carbon in uranium metal ingots induction cast from derbies prepared by the bomb-reduction of uranium tetrafluoride in the presence of magnesium is effectively reduced to less than 100 ppm by removing residual magnesium fluoride from the surface of the derbies prior to casting. This magnesium fluoride is removed from the derbies by immersing them in an alkali metal salt bath which reacts with and decomposes the magnesium fluoride. A water quenching operation followed by a warm nitric acid bath and a water rinse removes the residual salt and reaction products from the derbies.

  2. Uranium(VI) Diffusion in Low-Permeability Subsurface Materials...

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

    Uranium(VI) Diffusion in Low-Permeability Subsurface Materials. Uranium(VI) Diffusion in Low-Permeability Subsurface Materials. Abstract: Uranium(VI) diffusion was investigated in...

  3. Proteogenomic monitoring of Geobacter physiology during stimulated uranium bioremediation

    E-Print Network [OSTI]

    Wilkins, M.J.

    2010-01-01T23:59:59.000Z

    Phillips.  1992.  Bioremediation of  uranium contamination in situ uranium bioremediation.  Microbial Biotechnology 2:genes during in situ bioremediation of uranium?contaminated 

  4. adepleted uranium hexafluoride: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 15...

  5. active uranium americium: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 5...

  6. anthropogenic uranium concentration: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 12...

  7. abandoned uranium mill: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 3...

  8. anaconda uranium mill: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 3...

  9. THE THEORY OF URANIUM ENRICHMENT BY THE GAS CENTRIFUGE

    E-Print Network [OSTI]

    Olander, Donald R.

    2013-01-01T23:59:59.000Z

    1979) in "Uranium Enrichment", S. Villani, Ed. , Springer-E. (1973) "Uranium Enrichment by Gas Centrifuge" Mills andTHE THEORY OF URANIUM ENRICHMENT BY THE GAS CENTRIFUGE

  10. Microsoft PowerPoint - DOE Paducah Site Tour Industry Day - 2012...

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

    Ordnance Works site for the second of three planned uranium enrichment plants. Construction began in 1951. The first product was shipped in 1952. Placing a converter in an...

  11. Heat Recovery in the Forge Industry

    E-Print Network [OSTI]

    Shingledecker, R. B.

    1982-01-01T23:59:59.000Z

    Department of Energy figures reveal that in 1979 the forging and stamping operations were the primary consumers of energy (27%) within the 'Fabricated Metals Products Industry' (SIC 34). Industrial furnaces utilized by the forging industry often...

  12. Industrial Crops and Products 43 (2013) 802811 Contents lists available at SciVerse ScienceDirect

    E-Print Network [OSTI]

    Khan, Saad A.

    2013-01-01T23:59:59.000Z

    copolymers (Lee, 1996) to replace petro-derived plastics (Yu et al., 1999). Of the various biodegradable Accepted 10 August 2012 Keywords: Biodegradable plastics Polyhydroxyalkanoate (PHA) Sucrose Two-stage batch (ATCC 29714) for production of polyhydroxybutyrate (PHB), a biodegradable plastic, was explored

  13. From Geometric Modeling to Product Data Models: Collaboration Between Engineering, Computer Science, and Industry at Leeds University

    E-Print Network [OSTI]

    Whitney, Daniel

    to include concurrent engineering.1 In both cases, the Unit has established strong ties with the Computer with defining product data models that will support concurrent engineering. Both fabrication and assembly in manufacturing must be structured like concurrent engineering activities: the users of the research must be part

  14. Uranium chloride extraction of transuranium elements from LWR fuel

    DOE Patents [OSTI]

    Miller, William E. (Naperville, IL); Ackerman, John P. (Downers Grove, IL); Battles, James E. (Oak Forest, IL); Johnson, Terry R. (Wheaton, IL); Pierce, R. Dean (Naperville, IL)

    1992-01-01T23:59:59.000Z

    A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.

  15. Uranium chloride extraction of transuranium elements from LWR fuel

    DOE Patents [OSTI]

    Miller, W.E.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Pierce, R.D.

    1992-08-25T23:59:59.000Z

    A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800 C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein. 1 figure.

  16. Micro-Scale Heterogeneity in Biogeochemical Uranium Cycling

    SciTech Connect (OSTI)

    Ginder-Vogel, M.; Wu, W.-M.; Kelly, S.; Criddle, C.S.; Carley, J.; Jardine, P.; Kemner, K.M.; Fendorf, S.

    2009-06-04T23:59:59.000Z

    One method for the in situ remediation of uranium contaminated subsurface environments is the removal of highly soluble U(VI) from groundwater by microbial reduction to the sparingly soluble U(IV) mineral uraninite. Success of this remediation strategy will, in part, be determined by the extent and products of microbial reduction. In heterogeneous subsurface environments, microbial processes will likely yield a combination of U(IV) and U(VI) phases distributed throughout the soil matrix. Here, we use a combination of bulk X-ray absorption spectroscopy (XAS) and micro-focused XAS and X-ray diffraction to determine uranium speciation and distribution with sediment from a pilot-scale uranium remediation project located in Oak Ridge, TN.

  17. Domestic Uranium Production Report 2004-13

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127by Local(Dollars9.Domestic Thank

  18. Domestic Uranium Production Report - Quarterly - Energy Information

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40 Buildingto17 3400, U.S. DEPARTMENTshort05) EnergyAdministration All Nuclear

  19. Domestic Uranium Production Report - Energy Information Administration

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for On-Highway4,1,50022,3,,,,6,1,9,1,50022,3,,,,6,1,Decade Year-0E (2001)gasoline353/06) 2Yonthly Energy :and CommercialDomestic

  20. Uranium effluent testing for the Oak Ridge Toxic Substances Control Act mixed waste incinerator

    SciTech Connect (OSTI)

    Shor, J.T. [Oak Ridge National Lab., TN (United States); Bostick, W.D.; Hoffmann, D.P.; Gibson, L.V. Jr. [Oak Ridge K-25 Site, TN (United States); Ho, T.C. [Lamar Univ., Beaumont, TX (United States). Dept. of Chemical Engineering

    1993-07-01T23:59:59.000Z

    The Oak Ridge K-25 Site Toxic Substances Control Act (TSCA) Incinerator has been undergoing a series of routine tests to determine uranium partitioning to the stack, scrubber waters, and bottom ash. This paper discusses the results of the most recent experiment in which relatively high rates of uranium stack gas emissions were identified: 6.11 g/h or 8 wt % based on the uranium feed. These data are compared with earlier data, and an empirical correlation is suggested between the stack emissions of uranium and the product of the uranium and chlorine concentration of the feed. This is consistent with certain findings with other metals, in which increasing chlorine feed contents led to increasing emissions.

  1. Feasibility study of wood-fired cogeneration at a Wood Products Industrial Park, Belington, WV. Phase II

    SciTech Connect (OSTI)

    Vasenda, S.K.; Hassler, C.C.

    1992-06-01T23:59:59.000Z

    Customarily, electricity is generated in a utility power plant while thermal energy is generated in a heating/cooling plant; the electricity produced at the power plant is transmitted to the heating/cooling plant to power equipments. These two separate systems waste vast amounts of heat and result in individual efficiencies of about 35%. Cogeneration is the sequential production of power (electrical or mechanical) and thermal energy (process steam, hot/chilled water) from a single power source; the reject heat of one process issued as input into the subsequent process. Cogeneration increases the efficiency of these stand-alone systems by producing these two products sequentially at one location using a small additional amount of fuel, rendering the system efficiency greater than 70%. This report discusses cogeneration technologies as applied to wood fuel fired system.

  2. Industrial Engineering Industrial Advisory Board

    E-Print Network [OSTI]

    Gelfond, Michael

    Industrial Engineering Industrial Advisory Board (IAB) #12;PURPOSE: The Texas Tech University - Industrial Engineering Industrial Ad- visory Board (IAB) is an association of professionals with a com- mon goal - promoting and developing the Texas Tech Department of Industrial Engineering and its students

  3. Laser induced phosphorescence uranium analysis

    DOE Patents [OSTI]

    Bushaw, Bruce A. (Kennewick, WA)

    1986-01-01T23:59:59.000Z

    A method is described for measuring the uranium content of aqueous solutions wherein a uranyl phosphate complex is irradiated with a 5 nanosecond pulse of 425 nanometer laser light and resultant 520 nanometer emissions are observed for a period of 50 to 400 microseconds after the pulse. Plotting the natural logarithm of emission intensity as a function of time yields an intercept value which is proportional to uranium concentration.

  4. Laser induced phosphorescence uranium analysis

    DOE Patents [OSTI]

    Bushaw, B.A.

    1983-06-10T23:59:59.000Z

    A method is described for measuring the uranium content of aqueous solutions wherein a uranyl phosphate complex is irradiated with a 5 nanosecond pulse of 425 nanometer laser light and resultant 520 nanometer emissions are observed for a period of 50 to 400 microseconds after the pulse. Plotting the natural logarithm of emission intensity as a function of time yields an intercept value which is proportional to uranium concentration.

  5. UMTRA -- The US Uranium Mill Tailings Remedial Action Project

    SciTech Connect (OSTI)

    Lightner, R. [Dept. of Energy, Washington, DC (United States); Cormier, C. [Department of Energy, Albuquerque, NM (United States); Bierley, D. [Roy F. Weston, Inc., Albuquerque, NM (United States)

    1995-12-31T23:59:59.000Z

    In the late 1970s, the United States (US) established the first comprehensive regulatory structure for the management, disposal, and long-term care of wastes produced from its domestic uranium processing industry. This regulatory framework was established through the passage of the Uranium Mill Tailings Radiation Control Act of 1978, often referred to as UMTRCA. This legislation created the Uranium Mill Tailings Remedial Action (UMTRA) Project and assigned the US Department of Energy (DOE) the lead in conducting the required remedial action at 24 designated inactive uranium ore processing sites. With the majority of these 22 sites complete, the DOE`s UMTRA Project has established a distinguished reputation for safely and effectively remediating these low-level waste sites in a complex regulatory and socioeconomic environment. This paper describes the past accomplishments and current status of the UMTRA Project and discusses the DOE`s plans for addressing ground water contamination associated with these sites and its commitment to continuing the long-term care and management of these disposal cells.

  6. Nuclear reactor fuel structure containing uranium alloy wires embedded in a metallic matrix plate

    DOE Patents [OSTI]

    Travelli, A.

    1985-10-25T23:59:59.000Z

    A flat or curved plate structure, to be used as fuel in a nuclear reactor, comprises elongated fissionable wires or strips embedded in a metallic continuous non-fissionable matrix plate. The wires or strips are made predominantly of a malleable uranium alloy, such as uranium silicide, uranium gallide or uranium germanide. The matrix plate is made predominantly of aluminum or an aluminum alloy. The wires or strips are located in a single row at the midsurface of the plate, parallel with one another and with the length dimension of the plate. The wires or strips are separated from each other, and from the surface of the plate, by sufficient thicknesses of matrix material, to provide structural integrity and effective fission product retention, under neutron irradiation. This construction makes it safely feasible to provide a high uranium density, so that the uranium enrichment with uranium 235 may be reduced below about 20%, to deter the reprocessing of the uranium for use in nuclear weapons.

  7. Nuclear reactor fuel structure containing uranium alloy wires embedded in a metallic matrix plate

    DOE Patents [OSTI]

    Travelli, Armando (Hinsdale, IL)

    1988-01-01T23:59:59.000Z

    A flat or curved plate structure, to be used as fuel in a nuclear reactor, comprises elongated fissionable wires or strips embedded in a metallic continuous non-fissionable matrix plate. The wires or strips are made predominantly of a malleable uranium alloy, such as uranium silicide, uranium gallide or uranium germanide. The matrix plate is made predominantly of aluminum or an aluminum alloy. The wires or strips are located in a single row at the midsurface of the plate, parallel with one another and with the length dimension of the plate. The wires or strips are separated from each other, and from the surface of the plate, by sufficient thicknesses of matrix material, to provide structural integrity and effective fission product retention, under neutron irradiation. This construction makes it safely feasible to provide a high uranium density, so that the uranium enrichment with uranium 235 may be reduced below about 20%, to deter the reprocessing of the uranium for use in nuclear weapons.

  8. Evaluation of health effects in Sequoyah Fuels Corporation workers from accidental exposure to uranium hexafluoride

    SciTech Connect (OSTI)

    Fisher, D.R. (Pacific Northwest Lab., Richland, WA (USA)); Swint, M.J.; Kathren, R.L. (Hanford Environmental Health Foundation, Richland, WA (USA))

    1990-05-01T23:59:59.000Z

    Urine bioassay measurements for uranium and medical laboratory results were studied to determine whether there were any health effects from uranium intake among a group of 31 workers exposed to uranium hexafluoride (UF{sub 6}) and hydrolysis products following the accidental rupture of a 14-ton shipping cylinder in early 1986 at the Sequoyah Fuels Corporation uranium conversion facility in Gore, Oklahoma. Physiological indicators studied to detect kidney tissue damage included tests for urinary protein, casts and cells, blood, specific gravity, and urine pH, blood urea nitrogen, and blood creatinine. We concluded after reviewing two years of follow-up medical data that none of the 31 workers sustained any observable health effects from exposure to uranium. The early excretion of uranium in urine showed more rapid systemic uptake of uranium from the lung than is assumed using the International Commission on Radiological Protection (ICRP) Publication 30 and Publication 54 models. The urinary excretion data from these workers were used to develop an improved systemic recycling model for inhaled soluble uranium. We estimated initial intakes, clearance rates, kidney burdens, and resulting radiation doses to lungs, kidneys, and bone surfaces. 38 refs., 10 figs., 7 tabs.

  9. Compact reaction cell for homogenizing and down-blending highly enriched uranium metal

    DOE Patents [OSTI]

    McLean, W. II; Miller, P.E.; Horton, J.A.

    1995-05-02T23:59:59.000Z

    The invention is a specialized reaction cell for converting uranium metal to uranium oxide. In a preferred form, the reaction cell comprises a reaction chamber with increasing diameter along its length (e.g. a cylindrical chamber having a diameter of about 2 inches in a lower portion and having a diameter of from about 4 to about 12 inches in an upper portion). Such dimensions are important to achieve the necessary conversion while at the same time affording criticality control and transportability of the cell and product. The reaction chamber further comprises an upper port and a lower port, the lower port allowing for the entry of reactant gases into the reaction chamber, the upper port allowing for the exit of gases from the reaction chamber. A diffuser plate is attached to the lower port of the reaction chamber and serves to shape the flow of gas into the reaction chamber. The reaction cell further comprises means for introducing gases into the reaction chamber and a heating means capable of heating the contents of the reaction chamber. The present invention also relates to a method for converting uranium metal to uranium oxide in the reaction cell of the present invention. The invention is useful for down-blending highly enriched uranium metal by the simultaneous conversion of highly enriched uranium metal and natural or depleted uranium metal to uranium oxide within the reaction cell. 4 figs.

  10. Compact reaction cell for homogenizing and down-blanding highly enriched uranium metal

    DOE Patents [OSTI]

    McLean, II, William (Oakland, CA); Miller, Philip E. (Livermore, CA); Horton, James A. (Livermore, CA)

    1995-01-01T23:59:59.000Z

    The invention is a specialized reaction cell for converting uranium metal to uranium oxide. In a preferred form, the reaction cell comprises a reaction chamber with increasing diameter along its length (e.g. a cylindrical chamber having a diameter of about 2 inches in a lower portion and having a diameter of from about 4 to about 12 inches in an upper portion). Such dimensions are important to achieve the necessary conversion while at the same time affording criticality control and transportability of the cell and product. The reaction chamber further comprises an upper port and a lower port, the lower port allowing for the entry of reactant gasses into the reaction chamber, the upper port allowing for the exit of gasses from the reaction chamber. A diffuser plate is attached to the lower port of the reaction chamber and serves to shape the flow of gas into the reaction chamber. The reaction cell further comprises means for introducing gasses into the reaction chamber and a heating means capable of heating the contents of the reaction chamber. The present invention also relates to a method for converting uranium metal to uranium oxide in the reaction cell of the present invention. The invention is useful for down-blending highly enriched uranium metal by the simultaneous conversion of highly enriched uranium metal and natural or depleted uranium metal to uranium oxide within the reaction cell.

  11. Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2007-01-01T23:59:59.000Z

    Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration

  12. Performance Assessment Transport Modeling of Uranium at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site

    SciTech Connect (OSTI)

    NSTec Radioactive Waste

    2010-10-12T23:59:59.000Z

    Following is a brief summary of the assumptions that are pertinent to the radioactive isotope transport in the GoldSim Performance Assessment model of the Area 5 Radioactive Waste Management Site, with special emphasis on the water-phase reactive transport of uranium, which includes depleted uranium products.

  13. Industrial Scale Demonstration of Smart Manufacturing Achieving...

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

    Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Industrial Scale Demonstration of Smart Manufacturing Achieving...

  14. author research productivity: Topics by E-print Network

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

    2007 -Forest industry production Authorities Renewable Energy Websites Summary: FINLAND SOURCES 2007 - Forest industry production Print Home Finland Government Authorities...

  15. Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications 

    E-Print Network [OSTI]

    Helmreich, Grant

    2012-02-14T23:59:59.000Z

    The sintering behavior of uranium and uranium-zirconium alloys in the alpha phase were characterized in this research. Metal uranium powder was produced from pieces of depleted uranium metal acquired from the Y-12 plant via hydriding...

  16. Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications

    E-Print Network [OSTI]

    Helmreich, Grant

    2012-02-14T23:59:59.000Z

    The sintering behavior of uranium and uranium-zirconium alloys in the alpha phase were characterized in this research. Metal uranium powder was produced from pieces of depleted uranium metal acquired from the Y-12 plant via hydriding...

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01T23:59:59.000Z

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

  18. Depleted uranium disposal options.

    SciTech Connect (OSTI)

    Biwer, B. M.; Ranek, N. L.; Goldberg, M.; Avci, H. I.

    2000-04-01T23:59:59.000Z

    Depleted uranium hexafluoride (UF{sub 6}) has been produced in the United States since the 1940s as part of both the military program and the civilian nuclear energy program. The U.S. Department of Energy (DOE) is the agency responsible for managing most of the depleted UF{sub 6} that has been produced in the United States. The total quantity of depleted UF{sub 6} that DOE has to or will have to manage is approximately 700,000 Mg. Studies have been conducted to evaluate the various alternatives for managing this material. This paper evaluates and summarizes the alternative of disposal as low-level waste (LLW). Results of the analysis indicate that UF{sub 6} needs to be converted to a more stable form, such as U{sub 3}O{sub 8}, before disposal as LLW. Estimates of the environmental impacts of disposal in a dry environment are within the currently applicable standards and regulations. Of the currently operating LLW disposal facilities, available information indicates that either of two DOE facilities--the Hanford Site or the Nevada Test Site--or a commercial facility--Envirocare of Utah--would be able to dispose of up to the entire DOE inventory of depleted UF{sub 6}.

  19. Spatial and Geochemical Spatial and Geochemical Heterogeneity Impacts on Iron Biomineralization and Uranium Sequestration

    SciTech Connect (OSTI)

    Scott Fendorf; Shawn Benner; Jim Neiss; Colleen Hansel; Peter Nico; Chris Francis; Phil Jardine

    2004-03-17T23:59:59.000Z

    Bioreductive transformations of iron (hydr)oxides are a critically important processes controlling the fate and transport of contaminants in soil and aquifer systems. Heterogeneity arising from both chemical and physical conditions will lead to various biomineralization products of iron oxides and will additionally alter reactions controlling the partitioning of hazardous elements such as uranium. We are presently exploring chemical and mineralogical transformations within physically complex material having a range of pore-size distribution and chemical environments. Here we discuss the impact of calcium on the reactive transport of uranium and the spatial heterogeneity in iron hydroxide mineralization and concomitant uranium reduction along a diffusive flow path.

  20. Urbanization and the Transition from Agrarian to Industrial Society

    E-Print Network [OSTI]

    Fields, Gary

    1999-01-01T23:59:59.000Z

    modes of production - feudalism, antiquity - linked to thebridge the historical abyss between feudalism and industrial

  1. Potential Land Use Implications of a Global Biofuels Industry

    E-Print Network [OSTI]

    Gurgel, Angelo C.

    In this paper we investigate the potential production and implications of a global biofuels industry. We

  2. Depleted uranium hexafluoride: The source material for advanced shielding systems

    SciTech Connect (OSTI)

    Quapp, W.J.; Lessing, P.A. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Cooley, C.R. [Department of Technology, Germantown, MD (United States)

    1997-02-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has a management challenge and financial liability problem in the form of 50,000 cylinders containing 555,000 metric tons of depleted uranium hexafluoride (UF{sub 6}) that are stored at the gaseous diffusion plants. DOE is evaluating several options for the disposition of this UF{sub 6}, including continued storage, disposal, and recycle into a product. Based on studies conducted to date, the most feasible recycle option for the depleted uranium is shielding in low-level waste, spent nuclear fuel, or vitrified high-level waste containers. Estimates for the cost of disposal, using existing technologies, range between $3.8 and $11.3 billion depending on factors such as the disposal site and the applicability of the Resource Conservation and Recovery Act (RCRA). Advanced technologies can reduce these costs, but UF{sub 6} disposal still represents large future costs. This paper describes an application for depleted uranium in which depleted uranium hexafluoride is converted into an oxide and then into a heavy aggregate. The heavy uranium aggregate is combined with conventional concrete materials to form an ultra high density concrete, DUCRETE, weighing more than 400 lb/ft{sup 3}. DUCRETE can be used as shielding in spent nuclear fuel/high-level waste casks at a cost comparable to the lower of the disposal cost estimates. Consequently, the case can be made that DUCRETE shielded casks are an alternative to disposal. In this case, a beneficial long term solution is attained for much less than the combined cost of independently providing shielded casks and disposing of the depleted uranium. Furthermore, if disposal is avoided, the political problems associated with selection of a disposal location are also avoided. Other studies have also shown cost benefits for low level waste shielded disposal containers.

  3. A uranium-titanium-niobium alloy

    SciTech Connect (OSTI)

    Ludtka, G.M.; Ludtka, G.M.

    1990-02-23T23:59:59.000Z

    A uranium alloy having small additions of Ti and Nb shows improved strength and ductility in cross section of greater than one inch over prior uranium alloy having only Ti as an alloying element.

  4. Inherently safe in situ uranium recovery

    DOE Patents [OSTI]

    Krumhansl, James L; Brady, Patrick V

    2014-04-29T23:59:59.000Z

    An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

  5. Uranium Acquisition | Y-12 National Security Complex

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

    of Interest (EOI) to acquire up to 6,800 metric tons of Uranium (MTU) of high purity depleted uranium metal (DU) and related material and services. This request for EOI does...

  6. Uranium-233 purification and conversion to stabilized ceramic grade urania for LWBR fuel fabrication (LWBR Development Program)

    SciTech Connect (OSTI)

    Lloyd, R.

    1980-10-01T23:59:59.000Z

    High purity ceramic grade urania (/sup 233/UO/sub 2/) used in manufacturing the fuel for the Light Water Breeder Reactor (LWBR) core was made from uranium-233 that was obtained by irradiating thoria under special conditions to result in not more than 10 ppM of uranium-232 in the recovered uranium-233 product. A developmental study established the operating parameters of the conversion process for transforming the uranium-233 into urania powder with the appropriate chemical and physical attributes for use in fabricating the LWBR core fuel. This developmental study included the following: (a) design of an ion exchange purification process for removing the gamma-emitting alpha-decay daughters of uranium-232, to reduce the gamma-radiation field of the uranium-233 during LWBR fuel manufacture; (b) definition of the parameters for precipitating the uranium-233 as ammonium uranate (ADU) and for reducing the ADU with hydrogen to yield a urania conversion product of the proper particle size, surface area and sinterability for use in manufacturing the LWBR fuel; (c) establishment of parameters and design of equipment for stabilizing the urania conversion product to prevent it from undergoing excessive oxidation on exposure to the air during LWBR fuel manufacturing operations; and (d) development of a procedure and a facility to reprocess the unirradiated thoria-urania fuel scrap from the LWBR core manufacturing operations to recover the uranium-233 and convert it into high purity ceramic grade urania for LWBR core fabrication.

  7. XAFS of Synthetic Iron(III)-Arsenate Co-Precipitates and Uranium Mill Neutralized Raffinate

    SciTech Connect (OSTI)

    Chen, N. [Canadian Light Source, University of Saskatchewan, Saskatoon, SK S7N 0X4 (Canada); Department of Geological Sciences, University of Saskatchewan, Saskatoon, SK (Canada); Jiang, D. T. [Canadian Light Source, University of Saskatchewan, Saskatoon, SK S7N 0X4 (Canada); COGEMA Resources Inc., Saskatoon, SK S7K 3X5 (Canada); Department of Physics, University of Guelph, Guelph, ON N1G 2W1 (Canada); Cutler, J. [Canadian Light Source, University of Saskatchewan, Saskatoon, SK S7N 0X4 (Canada); Demopoulos, G. P. [Department of Geological Sciences, University of Saskatchewan, Saskatoon, SK (Canada); Rowson, J. W. [Department of Materials Engineering, McGill University, Montreal, QC H3A 2B2 (Canada)

    2007-02-02T23:59:59.000Z

    XAFS studies were carried out for chemical speciation of arsenic species in uranium mill neutralized raffinate solids. To aid the structural characterization, synthetic iron(III)-arsenate co-precipitates were prepared to mimic the actual uranium mill tailings neutralization products. The principle components analysis method was used to validate the synthetic amorphous scorodite as a primary model compound for arsenate species in the raffinate samples under the specific precipitation conditions.

  8. D Riso-R-429 Automated Uranium

    E-Print Network [OSTI]

    -induced delayed-neutron coun- ting is applied preferably in large geochemical exploration pro- grammes. UraniumCM i D Riso-R-429 Automated Uranium Analysis by Delayed-Neutron Counting H. Kunzendorf, L. Lřvborg AUTOMATED URANIUM ANALYSIS BY DELAYED-NEUTRON COUNTING H. Kunzendorf, L. Lřvborg and E.M. Christiansen

  9. Remediation and Recovery of Uranium from Contaminated

    E-Print Network [OSTI]

    Lovley, Derek

    that Geobacter species can effectively remove uranium from contaminated groundwater by reducing soluble U emplaced in flow- through columns of uranium-contaminated sediments readily removed U(VI) from the groundwater, and 87% of the uranium that had been removed was recovered from the electrode surface after

  10. High strength uranium-tungsten alloys

    DOE Patents [OSTI]

    Dunn, Paul S. (Santa Fe, NM); Sheinberg, Haskell (Los Alamos, NM); Hogan, Billy M. (Los Alamos, NM); Lewis, Homer D. (Bayfield, CO); Dickinson, James M. (Los Alamos, NM)

    1991-01-01T23:59:59.000Z

    Alloys of uranium and tungsten and a method for making the alloys. The amount of tungsten present in the alloys is from about 4 wt % to about 35 wt %. Tungsten particles are dispersed throughout the uranium and a small amount of tungsten is dissolved in the uranium.

  11. High strength uranium-tungsten alloy process

    DOE Patents [OSTI]

    Dunn, Paul S. (Santa Fe, NM); Sheinberg, Haskell (Los Alamos, NM); Hogan, Billy M. (Los Alamos, NM); Lewis, Homer D. (Bayfield, CO); Dickinson, James M. (Los Alamos, NM)

    1990-01-01T23:59:59.000Z

    Alloys of uranium and tungsten and a method for making the alloys. The amount of tungsten present in the alloys is from about 4 wt % to about 35 wt %. Tungsten particles are dispersed throughout the uranium and a small amount of tungsten is dissolved in the uranium.

  12. Uranium Watch REGULATORY CONFUSION: FEDERALAND STATE

    E-Print Network [OSTI]

    Uranium Watch Report REGULATORY CONFUSION: FEDERALAND STATE ENFORCEMENT OF 40 C.F.R. PART 61 SUBPART W INTRODUCTION 1. This Uranium Watch Report, Regulatory Confusion: Federal and State Enforcement at the White Mesa Uranium Mill, San Juan County, Utah. 2. The DAQ, a Division of the Utah Department

  13. Clean Air Act Requirements: Uranium Mill Tailings

    E-Print Network [OSTI]

    EPA'S Clean Air Act Requirements: Uranium Mill Tailings Radon Emissions Rulemaking Reid J. Rosnick requirements for operating uranium mill tailings (Subpart W) Status update on Subpart W activities Outreach/Communications #12;3 EPA Regulatory Requirements for Operating Uranium Mill Tailings (Clean Air Act) · 40 CFR 61

  14. URANIUM MILL TAILINGS RADON FLUX CALCULATIONS

    E-Print Network [OSTI]

    URANIUM MILL TAILINGS RADON FLUX CALCULATIONS PIĂ?ON RIDGE PROJECT MONTROSE COUNTY, COLORADO Inc. (Golder) was commissioned by EFRC to evaluate the operations of the uranium mill tailings storage in this report were conducted using the WISE Uranium Mill Tailings Radon Flux Calculator, as updated on November

  15. Preserving Ultra-Pure Uranium-233

    SciTech Connect (OSTI)

    Krichinsky, Alan M [ORNL; Goldberg, Dr. Steven A. [DOE SC - Chicago Office; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL)

    2011-10-01T23:59:59.000Z

    Uranium-233 ({sup 233}U) is a synthetic isotope of uranium formed under reactor conditions during neutron capture by natural thorium ({sup 232}Th). At high purities, this synthetic isotope serves as a crucial reference material for accurately quantifying and characterizing uranium-bearing materials assays and isotopic distributions for domestic and international nuclear safeguards. Separated, high purity {sup 233}U is stored in vaults at Oak Ridge National Laboratory (ORNL). These materials represent a broad spectrum of {sup 233}U from the standpoint of isotopic purity - the purest being crucial for precise analyses in safeguarding uranium. All {sup 233}U at ORNL is currently scheduled to be disposed of by down-blending with depleted uranium beginning in 2015. This will reduce safety concerns and security costs associated with storage. Down-blending this material will permanently destroy its potential value as a certified reference material for use in uranium analyses. Furthermore, no credible options exist for replacing {sup 233}U due to the lack of operating production capability and the high cost of restarting currently shut down capabilities. A study was commissioned to determine the need for preserving high-purity {sup 233}U. This study looked at the current supply and the historical and continuing domestic need for this crucial isotope. It examined the gap in supplies and uses to meet domestic needs and extrapolated them in the context of international safeguards and security activities - superimposed on the recognition that existing supplies are being depleted while candidate replacement material is being prepared for disposal. This study found that the total worldwide need by this projection is at least 850 g of certified {sup 233}U reference material over the next 50 years. This amount also includes a strategic reserve. To meet this need, 18 individual items totaling 959 g of {sup 233}U were identified as candidates for establishing a lasting supply of certified reference materials (CRM), all having an isotopic purity of at least 99.4% {sup 233}U and including materials up to 99.996% purity. Current plans include rescuing the purest {sup 233}U materials during a 3-year project beginning in FY 2012 in three phases involving preparations, handling preserved materials, and cleanup. The first year will involve preparations for handling the rescued material for sampling, analysis, distribution, and storage. Such preparations involve modifying or developing work control documents and physical preparations in the laboratory, which include preparing space for new material-handling equipment and procuring and (in some cases) refurbishing equipment needed for handling {sup 233}U or qualifying candidate CRM. Once preparations are complete, an evaluation of readiness will be conducted by independent reviewers to verify that the equipment, work controls, and personnel are ready for operations involving handling radioactive materials with nuclear criticality safety as well as radiological control requirements. The material-handling phase will begin in FY 2013 and be completed early in FY 2014, as currently scheduled. Material handling involves retrieving candidate CRM items from the ORNL storage facility and shipping them to another laboratory at ORNL; receiving and handling rescued items at the laboratory (including any needed initial processing, acquisition and analysis of samples from each item, and preparation for shipment); and shipping bulk material to destination labs or to a yet-to-be-designated storage location. There are seven groups of {sup 233}U identified for handling based on isotopic purity that require the utmost care to prevent cross-contamination. The last phase, cleanup, also will be completed in 2014. It involves cleaning and removing the equipment and material-handling boxes and characterizing, documenting, and disposing of waste. As part of initial planning, the cost of rescuing candidate {sup 233}U items was estimated roughly. The annualized costs were found to be $1,228K in FY 2012, $1,375K in FY 2013,

  16. Process for producing an aggregate suitable for inclusion into a radiation shielding product

    DOE Patents [OSTI]

    Lessing, Paul A. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID)

    2000-01-01T23:59:59.000Z

    The present invention is directed to methods for converting depleted uranium hexafluoride to a stable depleted uranium silicide in a one-step reaction. Uranium silicide provides a stable aggregate material that can be added to concrete to increase the density of the concrete and, consequently, shield gamma radiation. As used herein, the term "uranium silicide" is defined as a compound generically having the formula U.sub.x Si.sub.y, wherein the x represents the molecules of uranium and the y represent the molecules of silicon. In accordance with the present invention, uranium hexafluoride is converted to a uranium silicide by contacting the uranium hexafluoride with a silicon-containing material at a temperature in a range between about 1450.degree. C. and about 1750.degree. C. The stable depleted uranium silicide is included as an aggregate in a radiation shielding product, such as a concrete product.

  17. 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...

  18. Physical and mechanical metallurgy of uranium and uranium alloys

    SciTech Connect (OSTI)

    Eckelmeyer, K.H. [Sandia National Labs. (United States)

    1998-12-31T23:59:59.000Z

    Engineering disadvantages of unalloyed uranium include relatively low strength, low ductility, and poor oxidation and corrosion resistance. As-cast uranium typically exhibits very large grains that cause nonuniform deformation and low tensile ductility. Uranium is often alloyed to improve its corrosion resistance and mechanical properties. Titanium is most commonly used to increase strength; niobium and molybdenum, to increase oxidation and corrosion resistance; and vanadium, to refine alpha grain size in castings. Under equilibrium conditions these elements are extensively soluble in the high-temperature gamma phase, slightly soluble in the intermediate temperature beta phase, and essentially insoluble in the low-temperature alpha phase. Uranium alloys are vacuum solution heat treated in the gamma range to dissolve the alloying elements and remove hydrogen. The subsequent microstructures and properties are determined by the cooling rate from the solution treatment temperature. Oxidation and corrosion resistance increases with increasing the amount of alloy in solid solution. As a result, alloys such as U-6%Nb and U-10%Mo are often used in applications requiring good corrosion resistance.

  19. The Texas Industrial Energy Conservation Program 

    E-Print Network [OSTI]

    Waldrop, T.

    1982-01-01T23:59:59.000Z

    cesses listed. Chart1-lndustrial Target Groups SIC CODE INDUSTRY 201 Meat Products 204 Feed and Grain 207 Fats and Oils 26 Paper and Allied Products 28 Chemicals and Allied Products 30 Rubber and Plastics 33 Primary Metals 34 Fabricated Metals... industry seminars. In the preparation of workbooks for industrial processes, a screening of engineering firms was 763 ESL-IE-82-04-139 Proceedings from the Fourth Industrial Energy Technology Conference, Houston, TX, April 4-7, 1982 conducted in order...

  20. Electron Backscatter Diffraction (EBSD) Characterization of Uranium and Uranium Alloys

    SciTech Connect (OSTI)

    McCabe, Rodney J. [Los Alamos National Laboratory; Kelly, Ann Marie [Los Alamos National Laboratory; Clarke, Amy J. [Los Alamos National Laboratory; Field, Robert D. [Los Alamos National Laboratory; Wenk, H. R. [University of California, Berkeley

    2012-07-25T23:59:59.000Z

    Electron backscatter diffraction (EBSD) was used to examine the microstructures of unalloyed uranium, U-6Nb, U-10Mo, and U-0.75Ti. For unalloyed uranium, we used EBSD to examine the effects of various processes on microstructures including casting, rolling and forming, recrystallization, welding, and quasi-static and shock deformation. For U-6Nb we used EBSD to examine the microstructural evolution during shape memory loading. EBSD was used to study chemical homogenization in U-10Mo, and for U-0.75Ti, we used EBSD to study the microstructure and texture evolution during thermal cycling and deformation. The studied uranium alloys have significant microstructural and chemical differences and each of these alloys presents unique preparation challenges. Each of the alloys is prepared by a sequence of mechanical grinding and polishing followed by electropolishing with subtle differences between the alloys. U-6Nb and U-0.75Ti both have martensitic microstructures and both require special care in order to avoid mechanical polishing artifacts. Unalloyed uranium has a tendency to rapidly oxidize when exposed to air and a two-step electropolish is employed, the first step to remove the damaged surface layer resulting from the mechanical preparation and the second step to passivate the surface. All of the alloying additions provide a level of surface passivation and different one and two step electropolishes are employed to create good EBSD surfaces. Because of its low symmetry crystal structure, uranium exhibits complex deformation behavior including operation of multiple deformation twinning modes. EBSD was used to observe and quantify twinning contributions to deformation and to examine the fracture behavior. Figure 1 shows a cross section of two mating fracture surfaces in cast uranium showing the propensity of deformation twinning and intergranular fracture largely between dissimilarly oriented grains. Deformation of U-6Nb in the shape memory regime occurs by the motion of twin boundaries formed during the martensitic transformation. Deformation actually results in a coarsening of the microstructure making EBSD more practical following a limited amount of strain. Figure 2 shows the microstructure resulting from 6% compression. Casting of U-10Mo results in considerable chemical segregation as is apparent in Figure 2a. The segregation subsists through rolling and heat treatment processes as shown in Figure 2b. EBSD was used to study the effects of homogenization time and temperature on chemical heterogeneity. It was found that times and temperatures that result in a chemically homogeneous microstructure also result in a significant increase in grain size. U-0.75Ti forms an acicular martinsite as shown in Figure 4. This microstructure prevails through cycling into the higher temperature solid uranium phases.

  1. RESULTS OF THE TECHNICAL AND ECONOMIC FEASIBILITY ANALYSIS FOR A NOVEL BIOMASS GASIFICATION-BASED POWER GENERATION SYSTEM FOR THE FOREST PRODUCTS INDUSTRY

    SciTech Connect (OSTI)

    Bruce Bryan; Joseph Rabovitser; Sunil Ghose; Jim Patel

    2003-11-01T23:59:59.000Z

    In 2001, the Gas Technology Institute (GTI) entered into Cooperative Agreement DE-FC26-01NT41108 with the U.S. Department of Energy (DOE) for an Agenda 2020 project to develop an advanced biomass gasification-based power generation system for near-term deployment in the Forest Products Industry (FPI). The advanced power system combines three advanced components, including biomass gasification, 3-stage stoker-fired combustion for biomass conversion, and externally recuperated gas turbines (ERGTs) for power generation. The primary performance goals for the advanced power system are to provide increased self-generated power production for the mill and to increase wastewood utilization while decreasing fossil fuel use. Additional goals are to reduce boiler NOx and CO{sub 2} emissions. The current study was conducted to determine the technical and economic feasibility of an Advanced Power Generation System capable of meeting these goals so that a capital investment decision can be made regarding its implementation at a paper mill demonstration site in DeRidder, LA. Preliminary designs and cost estimates were developed for all major equipment, boiler modifications and balance of plant requirements including all utilities required for the project. A three-step implementation plan was developed to reduce technology risk. The plant design was found to meet the primary objectives of the project for increased bark utilization, decreased fossil fuel use, and increased self-generated power in the mill. Bark utilization for the modified plant is significantly higher (90-130%) than current operation compared to the 50% design goal. For equivalent steam production, the total gas usage for the fully implemented plant is 29% lower than current operation. While the current average steam production from No.2 Boiler is about 213,000 lb/h, the total steam production from the modified plant is 379,000 lb/h. This steam production increase will be accomplished at a grate heat release rate (GHRR) equal to the original boiler design. Boiler efficiencies (cogeneration-steam plus air) is increased from the original design value of 70% to 78.9% due to a combination of improved burnout, operation with lower excess air, and drier fuel. For the fully implemented plant, the thermal efficiency of fuel to electricity conversion is 79.8% in the cogeneration mode, 5% above the design goal. Finally, self-generated electricity will be increased from the 10.8 MW currently attributable to No.2 Boiler to 46.7MW, an increase of 332%. Environmental benefits derived from the system include a reduction in NOx emissions from the boiler of about 30-50% (90-130 tons/year) through syngas reburning, improved carbon burnout and lower excess air. This does not count NOx reduction that may be associated with replacement of purchased electricity. The project would reduce CO{sub 2} emissions from the generation of electricity to meet the mill's power requirements, including 50,000 tons/yr from a net reduction in gas usage in the mill and an additional 410,000 tons/yr reduction in CO{sub 2} emissions due to a 34 MW reduction of purchased electricity. The total CO{sub 2} reduction amounts to about 33% of the CO{sub 2} currently generated to meet the mills electricity requirement. The overall conclusion of the study is that while significant engineering challenges are presented by the proposed system, they can be met with operationally acceptable and cost effective solutions. The benefits of the system can be realized in an economic manner, with a simple payback period on the order of 6 years. The results of the study are applicable to many paper mills in the U.S. firing woodwastes and other solid fuels for steam and power production.

  2. Criticality safety concerns of uranium deposits in cascade equipment

    SciTech Connect (OSTI)

    Plaster, M.J. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States)

    1996-12-31T23:59:59.000Z

    The Paducah and Portsmouth Gaseous Diffusion Plants enrich uranium in the {sup 235}U isotope by diffusing gaseous uranium hexafluoride (UF{sub 6}) through a porous barrier. The UF{sub 6} gaseous diffusion cascade utilized several thousand {open_quotes}stages{close_quotes} of barrier to produce highly enriched uranium (HEU). Historically, Portsmouth has enriched the Paducah Gaseous Diffusion Plant`s product (typically 1.8 wt% {sup 235}U) as well as natural enrichment feed stock up to 97 wt%. Due to the chemical reactivity of UF{sub 6}, particularly with water, the formation of solid uranium deposits occur at a gaseous diffusion plant. Much of the equipment operates below atmospheric pressure, and deposits are formed when atmospheric air enters the cascade. Deposits may also be formed from UF{sub 6} reactions with oil, UF{sub 6} reactions with the metallic surfaces of equipment, and desublimation of UF{sub 6}. The major deposits form as a result of moist air in leakage due to failure of compressor casing flanges, blow-off plates, seals, expansion joint convolutions, and instrument lines. This report describes criticality concerns and deposit disposition.

  3. Standard specification for uranium hexafluoride enriched to less than 5 % 235U

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any 235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the pro...

  4. H. R. 4934: This title may be cited as the Uranium Revitalization, Tailings Reclamation and Enrichment Act of 1988. Introduced in the House of Representatives, One Hundredth Congress, Second Session, June 28, 1988

    SciTech Connect (OSTI)

    Not Available

    1988-01-01T23:59:59.000Z

    H.R. 4934 is a bill to provide for a viable domestic uranium industry, to establish a program to fund reclamation and other remedial actions with respect to mill tailings at active uranium and thorium sites, to establish a wholly-owned Government corporation to manage the Nation's uranium enrichment enterprise, operating as a continuing, commercial enterprise on a profitable and efficient basis, and for other purposes.

  5. An Industry/DOE Program to Develop and Benchmark Advanced Diamond Product Drill Bits and HP/HT Drilling Fluids to Significantly Improve Rates of Penetration

    SciTech Connect (OSTI)

    TerraTek

    2007-06-30T23:59:59.000Z

    A deep drilling research program titled 'An Industry/DOE Program to Develop and Benchmark Advanced Diamond Product Drill Bits and HP/HT Drilling Fluids to Significantly Improve Rates of Penetration' was conducted at TerraTek's Drilling and Completions Laboratory. Drilling tests were run to simulate deep drilling by using high bore pressures and high confining and overburden stresses. The purpose of this testing was to gain insight into practices that would improve rates of penetration and mechanical specific energy while drilling under high pressure conditions. Thirty-seven test series were run utilizing a variety of drilling parameters which allowed analysis of the performance of drill bits and drilling fluids. Five different drill bit types or styles were tested: four-bladed polycrystalline diamond compact (PDC), 7-bladed PDC in regular and long profile, roller-cone, and impregnated. There were three different rock types used to simulate deep formations: Mancos shale, Carthage marble, and Crab Orchard sandstone. The testing also analyzed various drilling fluids and the extent to which they improved drilling. The PDC drill bits provided the best performance overall. The impregnated and tungsten carbide insert roller-cone drill bits performed poorly under the conditions chosen. The cesium formate drilling fluid outperformed all other drilling muds when drilling in the Carthage marble and Mancos shale with PDC drill bits. The oil base drilling fluid with manganese tetroxide weighting material provided the best performance when drilling the Crab Orchard sandstone.

  6. Coal industry annual 1997

    SciTech Connect (OSTI)

    NONE

    1998-12-01T23:59:59.000Z

    Coal Industry Annual 1997 provides comprehensive information about US coal production, number of mines, prices, productivity, employment, productive capacity, and recoverable reserves. US Coal production for 1997 and previous years is based on the annual survey EIA-7A, Coal Production Report. This report presents data on coal consumption, coal distribution, coal stocks, coal prices, and coal quality for Congress, Federal and State agencies, the coal industry, and the general public. Appendix A contains a compilation of coal statistics for the major coal-producing States. This report includes a national total coal consumption for nonutility power producers that are not in the manufacturing, agriculture, mining, construction, or commercial sectors. 14 figs., 145 tabs.

  7. Coal industry annual 1993

    SciTech Connect (OSTI)

    Not Available

    1994-12-06T23:59:59.000Z

    Coal Industry Annual 1993 replaces the publication Coal Production (DOE/FIA-0125). This report presents additional tables and expanded versions of tables previously presented in Coal Production, including production, number of mines, Productivity, employment, productive capacity, and recoverable reserves. This report also presents data on coal consumption, coal distribution, coal stocks, coal prices, coal quality, and emissions for a wide audience including the Congress, Federal and State agencies, the coal industry, and the general public. In addition, Appendix A contains a compilation of coal statistics for the major coal-producing States. This report does not include coal consumption data for nonutility Power Producers who are not in the manufacturing, agriculture, mining, construction, or commercial sectors. This consumption is estimated to be 5 million short tons in 1993.

  8. Potential incorporation of transuranics into uranium phases

    SciTech Connect (OSTI)

    Kim, C. W.; Wronkiewicz, D. J.; Buck, E. C.

    1999-12-07T23:59:59.000Z

    The UO{sub 2} in spent nuclear fuel is unstable under moist oxidizing conditions and will be altered to uranyl oxide hydrate phases. The transuranics released during the corrosion of spent fuel may also be incorporated into the structures of secondary U{sup 6+} phases. The incorporation of radionuclides into alteration products will affect their mobility. A series of precipitation tests were conducted at either 150 or 90 C for seven days to determine the potential incorporation of Ce{sup 4+} and Nd{sup 3+} (surrogates for Pu{sup 4+} and Am{sup 3+}, respectively) into uranium phases. Ianthinite ([U{sub 2}{sup 4+}(UO{sub 2}){sub 4}O{sub 6}(OH){sub 4}(H{sub 2}O){sub 4}](H{sub 2}O){sub 5}) was produced by dissolving uranium oxyacetate in a solution containing copper acetate monohydrate as a reductant. The leachant used in these tests were doped with either 2.1 ppm cerium or 399 ppm neodymium. Inductively coupled plasma-mass spectrometer (ICP-MS) analysis of the solid phase reaction products which were dissolved in a HNO{sub 3} solution indicates that about 306 ppm Ce (K{sub d} = 146) was incorporated into ianthinite, while neodymium contents were much higher, being approximately 24,800 ppm (K{sub d} = 62). Solid phase examinations using an analytical transmission electron microscope/electron energy-loss spectrometer (AEM/EELS) indicate a uniform distribution of Nd, while Ce contents were below detection. Becquerelite (Ca[(UO{sub 2}){sub 6}O{sub 4}(OH){sub 6}]{center_dot}8H{sub 2}O) was produced by dissolving uranium oxyacetate in a solution containing calcium acetate. The leachant in these tests was doped with either 2.1 ppm cerium or 277 ppm neodymium. ICP-MS results indicate that about 33 ppm Ce (K{sub d}=16) was incorporated into becquerelite, while neodymium contents were higher, being approximately 1,300 ppm (K{sub d}=5). Homogeneous distribution of Nd in the solid phase was noted during AEM/EELS examination, and Ce contents were also below detection.

  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 cultivation systems.

  10. Investigation of Uranium Polymorphs

    SciTech Connect (OSTI)

    Sweet, Lucas E.; Henager, Charles H.; Hu, Shenyang Y.; Johnson, Timothy J.; Meier, David E.; Peper, Shane M.; Schwantes, Jon M.

    2011-08-01T23:59:59.000Z

    The UO3-water system is complex and has not been fully characterized, even though these species are common throughout the nuclear fuel cycle. As an example, most production schemes for UO3 result in a mixture of up to six or more different polymorphic phases, and small differences in these conditions will affect phase genesis that ultimately result in measureable changes to the end product. As a result, this feature of the UO3-water system may be useful as a means for determining process history. This research effort attempts to better characterize the UO3-water system with a variety of optical techniques for the purpose of developing some predictive capability for estimating process history in polymorphic phases of unknown origin. Three commercially relevant preparation methods for the production of UO3 were explored. Previously unreported low temperature routes to ?- and ?-UO3 were discovered. Raman and fluorescence spectroscopic libraries were established for pure and mixed polymorphic forms of UO3 in addition to the common hydrolysis products of UO3. An advantage of the sensitivity of optical fluorescence microscopy over XRD has been demonstrated. Preliminary aging studies of the ? and ? forms of UO3 have been conducted. In addition, development of a 3-D phase field model used to predict phase genesis of the system was initiated. Thermodynamic and structural constants that will feed the model have been gathered from the literature for most of the UO3 polymorphic phases.

  11. Fabrication of Cerium Oxide and Uranium Oxide Microspheres for Space Nuclear Power Applications

    SciTech Connect (OSTI)

    Jeffrey A. Katalenich; Michael R. Hartman; Robert C. O'Brien

    2013-02-01T23:59:59.000Z

    Cerium oxide and uranium oxide microspheres are being produced via an internal gelation sol-gel method to investigate alternative fabrication routes for space nuclear fuels. Depleted uranium and non-radioactive cerium are being utilized as surrogates for plutonium-238 (Pu-238) used in radioisotope thermoelectric generators and for enriched uranium required by nuclear thermal rockets. While current methods used to produce Pu-238 fuels at Los Alamos National Laboratory (LANL) involve the generation of fine powders that pose a respiratory hazard and have a propensity to contaminate glove boxes, the sol-gel route allows for the generation of oxide microsphere fuels through an aqueous route. The sol-gel method does not generate fine powders and may require fewer processing steps than the LANL method with less operator handling. High-quality cerium dioxide microspheres have been fabricated in the desired size range and equipment is being prepared to establish a uranium dioxide microsphere production capability.

  12. Influence of zirconium and niobium on cathodic deposition of uranium dioxide from alkali chloride melts

    SciTech Connect (OSTI)

    Komarov, V.E.; Borodina, N.P.; Martem`yanova, Z.S. [Institute of High-Temperature Electrochemistry, Ekaterinburg (Russian Federation)

    1995-07-01T23:59:59.000Z

    Electrocrystallization of uranium dioxide from molten chloride electrolytes in the presence of zirconium(IV) and niobium(V) was studied by voltammetry. Zirconium(IV) was found to react with uranium dioxide according to exchange mechanism to form (1 - x)UO{sub 2}{center_dot}xZrO{sub 2} solid solutions. Niobium(IV), a product of cathodic reduction of niobium(V), enters into the exchange reaction with uranium dioxide to yield (1 - y)UO{sub 2{center_dot}y}NbO{sub 2} solid solutions. In the case of simultaneous presence of Nb(V) and Zr(IV) in electrolyte, ternary (1 - x - y)UO{sub 2 {center_dot}x}ZrO{sub 2{center_dot}y}NbO{sub 2} solid solutions are obtained at the cathode surface. Nucleation of the solid solutions phase was shown to occurs at the most active sites of the crystalline precipitate of uranium dioxide.

  13. Criteria for the safe storage of enriched uranium at the Y-12 Plant

    SciTech Connect (OSTI)

    Cox, S.O.

    1995-07-01T23:59:59.000Z

    Uranium storage practices at US Department of Energy (DOE) facilities have evolved over a period spanning five decades of programmatic work in support of the nuclear deterrent mission. During this period, the Y-12 Plant in Oak Ridge, Tennessee has served as the principal enriched uranium facility for fabrication, chemical processing, metallurgical processing and storage. Recent curtailment of new nuclear weapons production and stockpile reduction has created significant amounts of enriched uranium available as a strategic resource which must be properly and safely stored. This standard specifies criteria associated with the safe storage of enriched uranium at the Y-12 Plant. Because programmatic needs, compliance regulations and desirable materials of construction change with time, it is recommended that these standards be reviewed and amended periodically to ensure that they continue to serve their intended purpose.

  14. Target and method for the production of fission product molybdenum-99

    DOE Patents [OSTI]

    Vandegrift, G.F.; Vissers, D.R.; Marshall, S.L.; Varma, R.

    1987-10-26T23:59:59.000Z

    A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm/sup 2/ of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99. 2 figs.

  15. Target and method for the production of fission product molybdenum-99

    DOE Patents [OSTI]

    Vandegrift, George F. (Bolingbrook, IL); Vissers, Donald R. (Naperville, IL); Marshall, Simon L. (Woodridge, IL); Varma, Ravi (Hinsdale, IL)

    1989-01-01T23:59:59.000Z

    A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm.sup.2 of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99.

  16. March market review. [Spot market prices for uranium (1993)

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    The spot market price for uranium in unrestricted markets weakened further during March, and at month end, the NUEXCO Exchange Value had fallen $0.15, to $7.45 per pound U3O8. The Restricted American Market Penalty (RAMP) for concentrates increased $0.15, to $2.55 per pound U3O8. Ample UF6 supplies and limited demand led to a $0.50 decrease in the UF6 Value, to $25.00 per kgU as UF6, while the RAMP for UF6 increased $0.75, to $5.25 per kgU. Nine near-term uranium transactions were reported, totalling almost 3.3 million pounds equivalent U3O8. This is the largest monthly spot market volume since October 1992, and is double the volume reported in January and February. The March 31 Conversion Value was $4.25 per kgU as UF6. Beginning with the March 31 Value, NUEXCO now reports its Conversion Value in US dollars per kilogram of uranium (US$/kgU), reflecting current industry practice. The March loan market was inactive with no transactions reported. The Loan Rate remained unchanged at 3.0 percent per annum. Low demand and increased competition among sellers led to a one-dollar decrease in the SWU Value, to $65 per SWU, and the RAMP for SWU declined one dollar, to $9 per SWU.

  17. Development of floating-type system for uranium extraction from seawater using sea current and wave power

    SciTech Connect (OSTI)

    Nobukawa, Hisashi; Kitamura, Mitsuru [Hiroshima Univ., Higashi-Hiroshima (Japan); Swilem, S.A.M. [Univ. of Alexandria (Egypt); Ishibashi, Kozo [Marine Technology Inst. Co., Ltd., Imari (Japan)

    1994-12-31T23:59:59.000Z

    The concept of a system for extracting uranium from seawater utilizing sea current and wave power is presented in this paper. The uranium absorption tests using model bed units whose size is 1/4 of the real absorbent system were carried out based on the concept design of the system. The model units are towed in the seawater with the velocity of about 2 knots for 30 hours. After the towing, the units were moored for 36 days in Imari Bay. Another absorption test, hanging the model bed units from a mooring ship in an open sea, was performed for 40 hours for assessing the effect of wave power in the uranium absorption. Based on the data obtained from the above tests, the production cost of uranium extraction was also calculated. It becomes about 34,000 yen/kg-uranium for extraction period of 60 days.

  18. Uranium Pyrophoricity Phenomena and Prediction (FAI/00-39)

    SciTech Connect (OSTI)

    PLYS, M.G.

    2000-10-10T23:59:59.000Z

    The purpose of this report is to provide a topical reference on the phenomena and prediction of uranium pyrophoricity for the Hanford Spent Nuclear Fuel (SNF) Project with specific applications to SNF Project processes and situations. Spent metallic uranium nuclear fuel is currently stored underwater at the K basins in the Hanford 100 area, and planned processing steps include: (1) At the basins, cleaning and placing fuel elements and scrap into stainless steel multi-canister overpacks (MCOs) holding about 6 MT of fuel apiece; (2) At nearby cold vacuum drying (CVD) stations, draining, vacuum drying, and mechanically sealing the MCOs; (3) Shipping the MCOs to the Canister Storage Building (CSB) on the 200 Area plateau; and (4) Welding shut and placing the MCOs for interim (40 year) dry storage in closed CSB storage tubes cooled by natural air circulation through the surrounding vault. Damaged fuel elements have exposed and corroded fuel surfaces, which can exothermically react with water vapor and oxygen during normal process steps and in off-normal situations, A key process safety concern is the rate of reaction of damaged fuel and the potential for self-sustaining or runaway reactions, also known as uranium fires or fuel ignition. Uranium metal and one of its corrosion products, uranium hydride, are potentially pyrophoric materials. Dangers of pyrophoricity of uranium and its hydride have long been known in the U.S. Department of Energy (Atomic Energy Commission/DOE) complex and will be discussed more below; it is sufficient here to note that there are numerous documented instances of uranium fires during normal operations. The motivation for this work is to place the safety of the present process in proper perspective given past operational experience. Steps in development of such a perspective are: (1) Description of underlying physical causes for runaway reactions, (2) Modeling physical processes to explain runaway reactions, (3) Validation of the method against experimental data, (4) Application of the method to plausibly explain operational experience, and (5) Application of the method to present process steps to demonstrate process safety and margin. Essentially, the logic above is used to demonstrate that runaway reactions cannot occur during normal SNF Project process steps, and to illustrate the depth of the technical basis for such a conclusion. Some off-normal conditions are identified here that could potentially lead to runaway reactions. However, this document is not intended to provide an exhaustive analysis of such cases. In summary, this report provides a ''toolkit'' of models and approaches for analysis of pyrophoricity safety issues at Hanford, and the technical basis for the recommended approaches. A summary of recommended methods appears in Section 9.0.

  19. Reports on investigations of uranium anomalies. National Uranium Resource Evaluation

    SciTech Connect (OSTI)

    Goodknight, C.S.; Burger, J.A. (comps.) [comps.

    1982-10-01T23:59:59.000Z

    During the National Uranium Resource Evaluation (NURE) program, conducted for the US Department of Energy (DOE) by Bendix Field Engineering Corporation (BFEC), radiometric and geochemical surveys and geologic investigations detected anomalies indicative of possible uranium enrichment. Data from the Aerial Radiometric and Magnetic Survey (ARMS) and the Hydrogeochemical and Stream-Sediment Reconnaissance (HSSR), both of which were conducted on a national scale, yielded numerous anomalies that may signal areas favorable for the occurrence of uranium deposits. Results from geologic evaluations of individual 1/sup 0/ x 2/sup 0/ quadrangles for the NURE program also yielded anomalies, which could not be adequately checked during scheduled field work. Included in this volume are individual reports of field investigations for the following six areas which were shown on the basis of ARMS, HSSR, and (or) geologic data to be anomalous: (1) Hylas zone and northern Richmond basin, Virginia; (2) Sischu Creek area, Alaska; (3) Goodman-Dunbar area, Wisconsin; (4) McCaslin syncline, Wisconsin; (5) Mt. Withington Cauldron, Socorro County, New Mexico; (6) Lake Tecopa, Inyo County, California. Field checks were conducted in each case to verify an indicated anomalous condition and to determine the nature of materials causing the anomaly. The ultimate objective of work is to determine whether favorable conditions exist for the occurrence of uranium deposits in areas that either had not been previously evaluated or were evaluated before data from recent surveys were available. Most field checks were of short duration (2 to 5 days). The work was done by various investigators using different procedures, which accounts for variations in format in their reports. All papers have been abstracted and indexed.

  20. Laser Isotope Enrichment for Medical and Industrial Applications

    SciTech Connect (OSTI)

    Leonard Bond

    2006-07-01T23:59:59.000Z

    Laser Isotope Enrichment for Medical and Industrial Applications by Jeff Eerkens (University of Missouri), Jay Kunze (Idaho State University), and Leonard Bond (Idaho National Laboratory) The principal isotope enrichment business in the world is the enrichment of uranium for commercial power reactor fuels. However, there are a number of other needs for separated isotopes. Some examples are: 1) Pure isotopic targets for irradiation to produce medical radioisotopes. 2) Pure isotopes for semiconductors. 3) Low neutron capture isotopes for various uses in nuclear reactors. 4) Isotopes for industrial tracer/identification applications. Examples of interest to medicine are targets to produce radio-isotopes such as S-33, Mo-98, Mo-100, W-186, Sn-112; while for MRI diagnostics, the non-radioactive Xe-129 isotope is wanted. For super-semiconductor applications some desired industrial isotopes are Si-28, Ga-69, Ge-74, Se-80, Te-128, etc. An example of a low cross section isotope for use in reactors is Zn-68 as a corrosion inhibitor material in nuclear reactor primary systems. Neutron activation of Ar isotopes is of interest in industrial tracer and diagnostic applications (e.g. oil-logging). . In the past few years there has been a sufficient supply of isotopes in common demand, because of huge Russian stockpiles produced with old electromagnetic and centrifuge separators previously used for uranium enrichment. Production of specialized isotopes in the USA has been largely accomplished using old ”calutrons” (electromagnetic separators) at Oak Ridge National Laboratory. These methods of separating isotopes are rather energy inefficient. Use of lasers for isotope separation has been considered for many decades. None of the proposed methods have attained sufficient proof of principal status to be economically attractive to pursue commercially. Some of the authors have succeeded in separating sulfur isotopes using a rather new and different method, known as condensation repression. In this scheme a gas, of the selected isotopes for enrichment, is irradiated with a laser at a particular wavelength that would excite only one of the isotopes. The entire gas is subject to low temperatures sufficient to cause condensation on a cold surface. Those molecules in the gas that the laser excited are not as likely to condense as are the unexcited molecules. Hence the gas drawn out of the system will be enriched in the isotope that was excited by the laser. We have evaluated the relative energy required in this process if applied on a commercial scale. We estimate the energy required for laser isotope enrichment is about 20% of that required in centrifuge separations, and 2% of that required by use of "calutrons".

  1. OTHER INDUSTRIES

    Broader source: Energy.gov [DOE]

    AMO funded research results in novel technologies in diverse industries beyond the most energy intensive ones within the U.S. Manufacturing sector. These technologies offer quantifiable energy...

  2. Selection of a management strategy for depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Patton, S.E.; Hanrahan, E.J.; Bradley, C.E.

    1995-09-06T23:59:59.000Z

    A consequence of the uranium enrichment process used in the United States (US) is the accumulation of a significant amount of depleted uranium hexafluoride (UF{sub 6}). Currently, approximately 560,000 metric tons of the material are stored at three different sites. The US Department of Energy (DOE) has recently initiated a program to consider alternative strategies for the cost-effective and environmentally safe long-term management of this inventory of depleted UF{sub 6}. The program involves a technology and engineering assessment of proposed management options (use/reuse, conversion, storage, or disposal) and an analysis of the potential environmental impacts and life-cycle costs of alternative management strategies. The information obtained from the studies will be used by the DOE to select a preferred long-term management strategy. The selection and implementation of a management strategy will involve consideration of a number of important issues such as environmental, health, and safety effects; the balancing of risks versus costs in a context of reduced government spending; socioeconomic implications, including effects on the domestic and international uranium industry; the technical status of proposed uses or technologies; and public involvement in the decision making process. Because of its provisions for considering a wide range of relevant issues and involving the public, this program has become a model for future DOE materials disposition programs. This paper presents an overview of the Depleted Uranium Hexafluoride Management Program. Technical findings of the program to date are presented, and major issues involved in selecting and implementing a management strategy are discussed.

  3. Global terrestrial uranium supply and its policy implications : a probabilistic projection of future uranium costs

    E-Print Network [OSTI]

    Matthews, Isaac A

    2010-01-01T23:59:59.000Z

    An accurate outlook on long-term uranium resources is critical in forecasting uranium costresource relationships, and for energy policy planning as regards the development and deployment of nuclear fuel cycle alternatives. ...

  4. TRIMOLECULAR REACTIONS OF URANIUM HEXAFLUORIDE WITH WATER

    SciTech Connect (OSTI)

    Westbrook, M.; Becnel, J.; Garrison, S.

    2010-02-25T23:59:59.000Z

    The hydrolysis reaction of uranium hexafluoride (UF{sub 6}) is a key step in the synthesis of uranium dioxide (UO{sub 2}) powder for nuclear fuels. Mechanisms for the hydrolysis reactions are studied here with density functional theory and the Stuttgart small-core scalar relativistic pseudopotential and associated basis set for uranium. The reaction of a single UF{sub 6} molecule with a water molecule in the gas phase has been previously predicted to proceed over a relatively sizeable barrier of 78.2 kJ {center_dot} mol{sup -1}, indicating this reaction is only feasible at elevated temperatures. Given the observed formation of a second morphology for the UO{sub 2} product coupled with the observations of rapid, spontaneous hydrolysis at ambient conditions, an alternate reaction pathway must exist. In the present work, two trimolecular hydrolysis mechanisms are studied with density functional theory: (1) the reaction between two UF{sub 6} molecules and one water molecule, and (2) the reaction of two water molecules with a single UF{sub 6} molecule. The predicted reaction of two UF{sub 6} molecules with one water molecule displays an interesting 'fluorine-shuttle' mechanism, a significant energy barrier of 69.0 kJ {center_dot} mol{sup -1} to the formation of UF{sub 5}OH, and an enthalpy of reaction ({Delta}H{sub 298}) of +17.9 kJ {center_dot} mol{sup -1}. The reaction of a single UF{sub 6} molecule with two water molecules displays a 'proton-shuttle' mechanism, and is more favorable, having a slightly lower computed energy barrier of 58.9 kJ {center_dot} mol{sup -1} and an exothermic enthalpy of reaction ({Delta}H{sub 298}) of -13.9 kJ {center_dot} mol{sup -1}. The exothermic nature of the overall UF{sub 6} + 2 {center_dot} H{sub 2}O trimolecular reaction and the lowering of the barrier height with respect to the bimolecular reaction are encouraging; however, the sizable energy barrier indicates further study of the UF{sub 6} hydrolysis reaction mechanism is warranted to resolve the remaining discrepancies between the predicted mechanisms and experimental observations.

  5. Bacterial Community Succession During in situ Uranium Bioremediation: Spatial Similarities Along Controlled Flow Paths

    E-Print Network [OSTI]

    Hwang, Chiachi

    2009-01-01T23:59:59.000Z

    problem, and the use of depleted uranium and other heavyenvironmental hazard. Depleted uranium is weakly radioactive

  6. Selective Recovery of Enriched Uranium from Inorganic Wastes

    SciTech Connect (OSTI)

    Kimura, R. T.

    2003-02-26T23:59:59.000Z

    Uranium as U(IV) and U(VI) can be selectively recovered from liquids and sludge containing metal precipitates, inorganic salts, sand and silt fines, debris, other contaminants, and slimes, which are very difficult to de-water. Chemical processes such as fuel manufacturing and uranium mining generate enriched and natural uranium-bearing wastes. This patented Framatome ANP (FANP) uranium recovery process reduces uranium losses, significantly offsets waste disposal costs, produces a solid waste that meets mixed-waste disposal requirements, and does not generate metal-contaminated liquids. At the head end of the process is a floating dredge that retrieves liquids, sludge, and slimes in the form of a slurry directly from the floor of a lined surface impoundment (lagoon). The slurry is transferred to and mixed in a feed tank with a turbine mixer and re-circulated to further break down the particles and enhance dissolution of uranium. This process uses direct steam injection and sodium hypochlorite addition to oxidize and dissolves any U(IV). Cellulose is added as a non-reactive filter aid to help filter slimes by giving body to the slurry. The slurry is pumped into a large recessed-chamber filter press then de-watered by a pressure cycle-controlled double-diaphragm pump. U(VI) captured in the filtrate from this process is then precipitated by conversion to U(IV) in another Framatome ANP-patented process which uses a strong reducing agent to crystallize and settle the U(IV) product. The product is then dewatered in a small filter press. To-date, over 3,000 Kgs of U at 3% U-235 enrichment were recovered from a 8100 m2 hypalon-lined surface impoundment which contained about 10,220 m3 of liquids and about 757 m3 of sludge. A total of 2,175 drums (0.208 m3 or 55 gallon each) of solid mixed-wastes have been packaged, shipped, and disposed. In addition, 9463 m3 of low-U liquids at <0.001 KgU/m3 were also further processed and disposed.

  7. Depleted uranium disposal options evaluation

    SciTech Connect (OSTI)

    Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

    1994-05-01T23:59:59.000Z

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

  8. Magnetic Exchange Coupling in Chloride-Bridged 5f-3d Heterometallic Complexes Generated via Insertion into a Uranium(IV) Dimethylpyrazolate

    E-Print Network [OSTI]

    Insertion into a Uranium(IV) Dimethylpyrazolate Dimer Stosh A. Kozimor, Bart M. Bartlett, Jeffrey D. Rinehart, and Jeffrey R. Long* Department of Chemistry, UniVersity of California, Berkeley, California additional products were observed: a THF adduct, (Me2Pz)4U(THF), and a salt of the pentapyrazolate uranium

  9. L'URANIUM ET LES ARMES L'URANIUM APPAUVRI. Pierre Roussel*

    E-Print Network [OSTI]

    Boyer, Edmond

    L'URANIUM ET LES ARMES � L'URANIUM APPAUVRI. Pierre Roussel* Institut de Physique Nucléaire, CNRS massivement dans la guerre du Golfe, des obus anti- chars ont été utilisés, avec des "charges d'uranium, avec une charge de 300 g d'uranium et tiré par des avions, l'autre de 120 mm de diamètre avec une

  10. The U.S. Uranium Mill Tailings Radiation Control Act -- An environmental legacy of the Cold War

    SciTech Connect (OSTI)

    Watson, C.D.; Nelson, R.A. [Jacobs Engineering Group Inc., Albuquerque, NM (United States). Albuquerque Operations Office; Mann, P. [USDOE Albuquerque Operations Office, NM (United States)

    1993-12-31T23:59:59.000Z

    The US Department of Energy (DOE) has guided the Uranium Mill Tailings Remedial Action (UMTRA) Project through its first 10 years of successful remediation. The Uranium Mill Tailings Radiation Control Act (UMTRCA), passed in 1978, identified 24 uranium mill tailings sites in need of remediation to protect human health and the environment from the residual contamination resulting from the processing of uranium ore. The UMTRCA was promulgated in two titles: Title 1 and Title 2. This paper describes the regulatory structure, required documentation, and some of the technical approaches used to meet the Act`s requirements for managing and executing the $1.4 billion project under Title 1. Remedial actions undertaken by private industry under Title 2 of the Act are not addressed in this paper. Some of the lessons learned over the course of the project`s history are presented so that other countries conducting similar remedial action activities may benefit.

  11. Uranium in prehistoric Indian pottery 

    E-Print Network [OSTI]

    Filberth, Ernest William

    1976-01-01T23:59:59.000Z

    . 2 to 25 ppm (Katz 1951). From thermal equilibrium calculations on the earth's core, mantle, and crust, and through actual analysis of samples, uranium was found to be concentrated in the earth's crust. According to modern geological thought..., as the uniformly molten earth cooled, its matter became separated into one vapor phase and three concentric condensed phases: the siderosphere (the earth's core, probably primarily molten iron), the chalcosphere forming the intermediate shell (the mantle...

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2001-01-01T23:59:59.000Z

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

  13. Dry process fluorination of uranium dioxide using ammonium bifluoride

    E-Print Network [OSTI]

    Yeamans, Charles Burnett, 1978-

    2003-01-01T23:59:59.000Z

    An experimental study was conducted to determine the practicality of various unit operations for fluorination of uranium dioxide. The objective was to prepare ammonium uranium fluoride double salts from uranium dioxide and ...

  14. albarrana uranium ores: Topics by E-print Network

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

    and purified uranium ore into uranium hexafluoride (UF 6), or the reduction of depleted uranium tetrafluoride (UF 4) to UF 6. SFC contends that these unknown authors 7 A...

  15. Industry Partners Panel

    Broader source: Energy.gov [DOE]

    Industry Panel presenters include: Michael G. Andrew, Director - Academic and Technical Programs, Advanced Products and Materials, Johnson Controls Power Solutions Michael A. Fetcenko, Vice President and Managing Director, BASF Battery Materials – Ovonic, BASF Corporation Adam Kahn, Founder and CEO, AKHAN Technologies, Inc. Stephen E. Zimmer, Executive Director, United States Council for Automotive Research (USCAR)

  16. INTERMOUNTAIN INDUSTRIAL ASSESSMENT CENTER

    SciTech Connect (OSTI)

    MELINDA KRAHENBUHL

    2010-05-28T23:59:59.000Z

    The U. S. Department of Energy’s Intermountain Industrial Assessment Center (IIAC) at the University of Utah has been providing eligible small- and medium-sized manufacturers with no-cost plant assessments since 2001, offering cost-effective recommendations for improvements in the areas of energy efficiency, pollution prevention, and productivity improvement.

  17. Review of uranium bioassay techniques

    SciTech Connect (OSTI)

    Bogard, J.S.

    1996-04-01T23:59:59.000Z

    A variety of analytical techniques is available for evaluating uranium in excreta and tissues at levels appropriate for occupational exposure control and evaluation. A few (fluorometry, kinetic phosphorescence analysis, {alpha}-particle spectrometry, neutron irradiation techniques, and inductively-coupled plasma mass spectrometry) have also been demonstrated as capable of determining uranium in these materials at levels comparable to those which occur naturally. Sample preparation requirements and isotopic sensitivities vary widely among these techniques and should be considered carefully when choosing a method. This report discusses analytical techniques used for evaluating uranium in biological matrices (primarily urine) and limits of detection reported in the literature. No cost comparison is attempted, although references are cited which address cost. Techniques discussed include: {alpha}-particle spectrometry; liquid scintillation spectrometry, fluorometry, phosphorometry, neutron activation analysis, fission-track counting, UV-visible absorption spectrophotometry, resonance ionization mass spectrometry, and inductively-coupled plasma mass spectrometry. A summary table of reported limits of detection and of the more important experimental conditions associated with these reported limits is also provided.

  18. Uranium Tris-aryloxide Derivatives Supported by Triazacyclononane: Engendering a Reactive Uranium(III)

    E-Print Network [OSTI]

    Meyer, Karsten

    , we are currently investigating the coordina- tion chemistry of uranium metal centers with classicalUranium Tris-aryloxide Derivatives Supported by Triazacyclononane: Engendering a Reactive Uranium, and Karsten Meyer* Contribution from the Department of Chemistry and Biochemistry, UniVersity of California

  19. Evaluation of a RF-Based Approach for Tracking UF6 Cylinders at a Uranium Enrichment Plant

    SciTech Connect (OSTI)

    Pickett, Chris A [ORNL] [ORNL; Younkin, James R [ORNL] [ORNL; Kovacic, Donald N [ORNL] [ORNL; Laughter, Mark D [ORNL] [ORNL; Hines, Jairus B [ORNL] [ORNL; Boyer, Brian [Los Alamos National Laboratory (LANL)] [Los Alamos National Laboratory (LANL); Martinez, B. [Los Alamos National Laboratory (LANL)] [Los Alamos National Laboratory (LANL)

    2008-01-01T23:59:59.000Z

    Approved industry-standard cylinders are used globally to handle and store uranium hexafluoride (UF{sub 6}) feed, product, tails, and samples at uranium enrichment plants. The International Atomic Energy Agency (IAEA) relies on time-consuming physical inspections to verify operator declarations and detect possible diversion of UF{sub 6}. Development of a reliable, automated, and tamper-resistant system for near real-time tracking and monitoring UF{sub 6} cylinders (as they move within an enrichment facility) would greatly improve the inspector function. This type of system can reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a proof-of-concept approach that was designed to evaluate the feasibility of using radio frequency (RF)-based technologies to track individual UF{sub 6} cylinders throughout a portion of their life cycle, and thus demonstrate the potential for improved domestic accountability of materials, and a more effective and efficient method for application of site-level IAEA safeguards. The evaluation system incorporates RF-based identification devices (RFID) which provide a foundation for establishing a reliable, automated, and near real-time tracking system that can be set up to utilize site-specific, rules-based detection algorithms. This paper will report results from a proof-of-concept demonstration at a real enrichment facility that is specifically designed to evaluate both the feasibility of using RF to track cylinders and the durability of the RF equipment to survive the rigors of operational processing and handling. The paper also discusses methods for securely attaching RF devices and describes how the technology can effectively be layered with other safeguard systems and approaches to build a robust system for detecting cylinder diversion. Additionally, concepts for off-site tracking of cylinders are described.

  20. Progress toward uranium scrap recycling via electron beam cold hearth refining

    SciTech Connect (OSTI)

    McKoon, R.H.

    1994-12-15T23:59:59.000Z

    A 250 kW electron beam cold hearth refining (EBCHR) melt furnace at Lawrence Livermore National Laboratory (LLNL) has been in operation for over a year producing 5.5 in.-diameter ingots of various uranium alloys. Production of in-specification uranium-6%-niobium (U-6Nb) alloy ingots has been demonstrated using Virgin feedstock. A vibratory scrap feeder has been installed on the system and the ability to recycle chopped U-6Nb scrap has been established. A preliminary comparison of vacuum arc remelted (VAR) and electron beam (EB) melted product is presented.