National Library of Energy BETA

Sample records for uranium industry annual

  1. Uranium industry annual 1998

    SciTech Connect (OSTI)

    1999-04-22

    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.

  2. Uranium industry annual 1996

    SciTech Connect (OSTI)

    1997-04-01

    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.

  3. Uranium Industry Annual, 1992

    SciTech Connect (OSTI)

    Not Available

    1993-10-28

    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.

  4. 2015 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 thousand ...

  5. 2015 Uranium Marketing Annual Survey

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

    5 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  6. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Deliveries 2011 2012 2013 2014 2015 Purchases of ...

  7. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Delivery year Total purchased (weighted- average price) ...

  8. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Purchases Weighted- average price Purchases Weighted- ...

  9. 2015 Uranium Marketing Annual Report

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

    7 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  10. 2015 Uranium Marketing Annual Survey

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

    U.S. Energy Information Administration, Form EIA-858 ""Uranium Marketing Annual Survey"" (2015)." " U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 15

  11. 2015 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration, Form EIA-858 ""Uranium Marketing Annual Survey"" (2015)." " U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 25

  12. 2015 Uranium Marketing Annual Report

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

    1 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  13. 2015 Uranium Marketing Annual Report

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

    9 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual ...

  14. 2015 Uranium Marketing Annual Report

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

    3 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  15. 2015 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Origin of ...

  16. 2015 Uranium Marketing Annual Report

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

    3 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual ...

  17. 2015 Uranium Market Annual Report

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

    U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Purchase ...

  18. 2015 Uranium Marketing Annual Report

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

    2 U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 thousand ...

  19. 2015 Uranium Marketing Annual Report

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

    Energy Information Administration, Form EIA-858 ""Uranium Marketing Annual Survey"" (2013-15)." " U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 33

  20. 2015 Uranium Marketing Annual Report

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

    8 U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 ...

  1. 2015 Uranium Marketing Annual Report

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

    5 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  2. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Number of purchasers Quantity with reported price ...

  3. 2015 Uranium Market Annual Report

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

    U.S. Energy Information Administration, Form EIA-858 ""Uranium Marketing Annual Survey"" (2015)." "16 U.S. Energy Information Administration 2015 Uranium Marketing Annual Report

  4. 2015 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Minimum ...

  5. 2015 Uranium Marketing Annual Report

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

    7 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual ...

  6. 2015 Uranium Marketing Annual Report

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

    1 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual ...

  7. 2015 Uranium Marketing Annual Report

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

    9 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  8. 2015 Uranium Marketing Annual Report

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

    Energy Information Administration: Form EIA-858 ""Uranium Marketing Annual Survey"" (2013-15)." " U.S. Energy Information Administration 2015 Uranium Marketing Annual Report 1

  9. 2015 Uranium Marketing Annual Report

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

    Energy Information Administration: Form EIA-858 ""Uranium Marketing Annual Survey"" (2013-15)." "14 U.S. Energy Information Administration 2015 Uranium Marketing Annual Report

  10. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Table S3a. Foreign purchases, foreign sales, and uranium ...

  11. 2015 Uranium Marketing Annual Report

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

    7 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... Annual, Tables 28, 29, 30 and 31. 2003-15-Form EIA-858, "Uranium Marketing Annual Survey". ...

  12. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 2014 2015 2014 2015 2014 2015 Weighted-average price ...

  13. 2015 Uranium Marketing Annual Report

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

    2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 thousand pounds U 3 O 8 equivalent Year Maximum ...

  14. 2015 Uranium Marketing Annual Report

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

    2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... and 16. 2003-15-Form EIA-858, "Uranium Marketing Annual Survey". million pounds U 3 O 8 ...

  15. 2015 Uranium Marketing Annual Report

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

    5 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May ... and 27. 2003-15-Form EIA-858, "Uranium Marketing Annual Survey". - No data reported. 0 ...

  16. 2015 Uranium Marketing Annual Report

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

    2 U.S. Energy Information Administration / 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 2013 2014 2015 American Fuel Resources, LLC Advance Uranium Asset Management Ltd. AREVA / AREVA NC, Inc. AREVA NC, Inc. AREVA / AREVA NC, Inc. ARMZ (AtomRedMetZoloto) BHP Billiton Olympic Dam Corporation Pty Ltd ARMZ (AtomRedMetZoloto) BHP Billiton Olympic Dam Corporation Pty Ltd CAMECO BHP Billiton Olympic Dam Corporation Pty

  17. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    5. Shipments of uranium feed by owners and operators of U.S. civilian nuclear power reactors to domestic and foreign enrichment suppliers, 2015-24 thousand pounds U3O8 equivalent Amount of feed to be shipped Change from 2013 to 2014 Year of shipment As of December 31, 2013 As of December 31, 2014 Annual Cumulative 2015 45,498 48,206 2,708 2,708 2016 48,693 46,529 -2,164 544 2017 47,005 49,924 2,919 3,463 2018 52,138 51,169 -969 2,494 2019 50,041 46,184 -3,857 -1,363 2020 49,726 49,598 -128

  18. 2015 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report May 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | 2015 Uranium Marketing Annual Report i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States

  19. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    4. Uranium sellers to owners and operators of U.S. civilian nuclear power reactors, 2012-14 2012 2013 2014 Advance Uranium Asset Management Ltd. (was Uranium Asset Management) American Fuel Resources, LLC Advance Uranium Asset Management Ltd. American Fuel Resources, LLC AREVA NC, Inc. AREVA / AREVA NC, Inc. AREVA NC, Inc. BHP Billiton Olympic Dam Corporation Pty Ltd ARMZ (AtomRedMetZoloto) BHP Billiton Olympic Dam Corporation Pty Ltd CAMECO BHP Billiton Olympic Dam Corporation Pty Ltd CAMECO

  20. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    8. Uranium in fuel assemblies loaded into U.S. civilian nuclear power reactors by year, 2010-14 thousand pounds U3O8 equivalent Origin of uranium 2010 2011 2012 2013 P2014 Domestic-origin uranium 4,119 4,134 4,825 3,643 3,202 Foreign-origin uranium 40,187 46,809 44,657 39,000 47,281 Total 44,306 50,943 49,483 42,642 50,483 P = Preliminary data. Final 2013 fuel assembly data reported in the 2014 survey. Notes: Includes only unirradiated uranium in new fuel assemblies loaded into reactors during

  1. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    Uranium purchased by owners and operators of U.S. civilian nuclear power reactors, ... owners and operators of U.S. civilian nuclear power reactors, other U.S. suppliers, ...

  2. Uranium Marketing Annual Report -

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

    AREVA NC, Inc AREVA Enrichment Services, LLC AREVA NC, Inc. AREVA NC, Inc. .CNEIC (China Nuclear Energy Industry Corporation) CNEIC (China Nuclear Energy Industry Corporation) ...

  3. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    . Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2010-14 thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries 2010 2011 2012 2013 2014 U.S.-Origin Uranium Purchases 3,687 5,205 9,807 9,484 3,316 Weighted-Average Price 45.25 52.12 59.44 56.37 48.11 Foreign-Origin Uranium Purchases 42,895 49,626 47,713 47,919 50,033 Weighted-Average Price 49.64 55.98 54.07 51.13 46.03 Total Purchases 46,582 54,831 57,520

  4. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    0. U.S. broker and trader purchases of uranium by origin, supplier, and delivery year, 2010-14 thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries 2010 2011 2012 2013 2014 Received U.S.-origin uranium Purchases 2,226 1,668 1,194 W 410 Weighted-average price 43.36 54.85 51.78 W 33.55 Received foreign-origin uranium Purchases 27,186 24,695 24,606 W 28,743 Weighted-average price 41.42 49.69 47.75 W 38.42 Total received by U.S. brokers and traders Purchases 29,412 26,363

  5. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    1. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2010-14 thousands pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries to foreign suppliers and utilities 2010 2011 2012 2013 2014 U.S.-origin uranium Foreign sales 3,440 4,387 4,798 4,148 4,210 Weighted-average price 37.82 53.08 47.53 43.10 32.91 Foreign-origin uranium Foreign sales 19,708 12,297 13,185 14,717 15,794 Weighted-Average Price

  6. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    2. Inventories of natural and enriched uranium by material type as of end of year, 2010-14 thousand pounds U3O8 equivalent Inventories at the end of the year Type of uranium inventory owned by 2010 2011 2012 2013 P2014 Owners and operators of U.S. civilian nuclear power reactors inventories 86,527 89,835 97,647 113,077 116,047 Uranium concentrate (U3O8) 13,076 14,718 15,963 18,131 20,501 Natural UF6 35,767 35,883 29,084 38,332 40,972 Enriched UF6 25,392 19,596 38,428 40,841 44,605 Fabricated

  7. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    a. Foreign purchases, foreign sales, and uranium inventories owned by U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors, 1994-2014 million pounds U3O8 equivalent Delivery year Foreign purchases by U.S. suppliers Foreign purchases by owners and operators of U.S. civilian nuclear power reactors Total foreign purchases U.S. broker and trader purchases from foreign suppliers Foreign sales U.S. supplier owned uranium inventories Owners and operators of U.S. civilian

  8. 2015 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration / 2015 Uranium Marketing Annual Report 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 thousand pounds U 3 O 8 equivalent 2011 2012 2013 2014 P2015 Owners and operators of U.S. civilian nuclear power reactors inventories 89,835 97,647 113,077 114,046 120,857 Uranium concentrate (U 3 O 8 ) 14,718 15,963 18,131 19,060 20,635 Natural UF 6 35,883 29,084 38,332 40,803 47,253 Enriched UF 6 19,596 38,428 40,841 43,382

  9. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    3. Inventories of uranium by owner as of end of year, 2010-14 thousand pounds U3O8 equivalent Inventories at the end of the year Owner of uranium inventory 2010 2011 2012 2013 P2014 Owners and operators of U.S. civilian nuclear power reactors 86,527 89,835 97,647 113,007 116,047 U.S. brokers and traders 11,125 6,841 5,677 7,926 5,798 U.S. converter, enrichers, fabricators, and producers 13,608 15,428 17,611 13,416 12,766 Total commercial inventories 111,259 112,104 120,936 134,418 134,611 P =

  10. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    b. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors ranked by price and distributed by purchaser, 2012-14 deliveries thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries in 2012 Deliveries in 2013 Deliveries in 2014 Distribution of purchasers Number of purchasers Quantity with reported price Weighted-average price Number of purchasers Quantity with reported price Weighted-average price Number of purchasers Quantity with reported price

  11. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    0. Contracted purchases of uranium from suppliers by owners and operators of U.S. civilian nuclear power reactors, in effect at the end of 2014, by delivery year, 2015-24 thousand pounds U3O8 equivalent Contracted purchases from U.S. suppliers Contracted purchases from foreign suppliers Contracted purchases from all suppliers Year of delivery Minimum Maximum Minimum Maximum Minimum Maximum 2015 8,405 8,843 31,468 34,156 39,873 42,999 2016 7,344 7,757 29,660 31,787 37,004 39,544 2017 5,980 6,561

  12. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    4. Deliveries of uranium feed for enrichment by owners and operators of U.S. civilian nuclear power reactors by origin country and delivery year, 2012-14 thousand pounds U3O8 equivalent Deliveries in 2012 Deliveries in 2013 Deliveries in 2014 Origin country of feed U.S. enrichment Foreign enrichment Total U.S. enrichment Foreign enrichment Total U.S. enrichment Foreign enrichment Total Australia 3,195 3,352 6,547 2,417 2,476 4,893 910 4,467 5,377 Brazil 0 0 0 0 W W 0 W W Canada 6,741 5,007

  13. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    3. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by origin country and delivery year, 2010-14 thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries in 2010 Deliveries in 2011 Deliveries in 2012 Deliveries in 2013 Deliveries in 2014 Origin country Purchases Weighted-average price Purchases Weighted-average price Purchases Weighted-average price Purchases Weighted-average price Purchases Weighted-average price Australia 7,112 51.35 6,001

  14. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    5. Average price and quantity for uranium purchased by owners and operators of U.S. civilian nuclear power reactors by pricing mechanisms and delivery year, 2013-14 dollars per pound U3O8 equivalent; thousand pounds U3O8 equivalent Pricing mechanisms Domestic purchases1 Foreign purchases2 Total purchases 2013 2014 2013 2014 2013 2014 Contract-specified (fixed and base-escalated) pricing Weighted-average price 54.95 41.87 55.03 49.87 54.99 45.47 Quantity with reported price 14,530 15,711 14,732

  15. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    a. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors ranked by price and distributed by quantity, 2012-14 deliveries thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries in 2012 Deliveries in 2013 Deliveries in 2014 Quantity 1 distribution Quantity with reported price Weighted-average price Quantity with reported price Weighted-average price Quantity with reported price Weighted-average price First 7,119 38.24 7,175 34.24 6,665 30.26

  16. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    7. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by contract type and material type, 2014 deliveries thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Spot 1 Contracts Long-Term Contracts 2 Total Material Type Quantity with reported price Weighted-average price Quantity with reported price Weighted-average price Quantity with reported price Weighted-average price U3O8 8,440 38.38 20,820 47.57 29,260 44.92 Natural UF6 4,405 35.30 13,373 53.13

  17. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    9. Contracted purchases of uranium by owners and operators of U.S. civilian nuclear power reactors, signed in 2014, by delivery year, 2015-24 thousand pounds U3O8 equivalent Year of Delivery Minimum Maximum 2015 2,838 2,838 2016 3,573 3,573 2017 2,718 2,818 2018 W 2,628 2019 W W 2020 W W 2021 W W 2022 W W 2023 W W 2024 W W Total 13,991 15,591 W = Data withheld to avoid disclosure of individual company data. Note: Totals may not equal sum of components because of independent rounding

  18. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    2. Maximum anticipated uranium market requirements of owners and operators of U.S. civilian nuclear power reactors, 2015-24, as of December 31, 2014 thousand pounds U3O8 equivalent Year Maximum Under Purchase Contracts Unfilled Market Requirements Maximum Anticipated Market Requirements Enrichment Feed Deliveries 2015 42,999 3,496 46,494 48,206 2016 39,544 7,384 46,929 46,529 2017 31,257 10,351 41,608 49,924 2018 26,001 18,468 44,469 51,169 2019 19,096 29,929 49,025 46,184 2020 13,308 33,521

  19. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    9. Foreign purchases of uranium by U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by delivery year, 2010-14 thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries 2010 2011 2012 2013 2014 U.S. suppliers Foreign purchases 24,985 19,318 20,196 23,233 24,199 Weighted-average price 41.30 48.80 46.80 43.25 39.13 Owners and operators of U.S. civilian nuclear power reactors Foreign purchases 30,362 35,071 36,037 34,095 34,404 Weighted-average

  20. Coal industry annual 1997

    SciTech Connect (OSTI)

    1998-12-01

    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.

  1. 2015 Uranium Marketing Annual Report

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

    9 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Deliveries to foreign suppliers and utilities 2011 2012 2013 2014 2015 Foreign sales 4,387 4,798 4,148 4,210 4,258 Weighted-average price 53.08 47.53 43.10 32.91 37.85 Foreign sales 12,297 13,185 14,717 15,794 21,465 Weighted-average price 47.61 47.58 42.66 36.43 39.58 Foreign sales 16,683 17,982 18,864 20,004 25,723 Weighted-average price 49.05 47.57 42.75 35.69 39.29 Foreign sales 4,538 3,699 4,177

  2. 2015 Uranium Marketing Annual Report

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

    1 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 thousand pounds U 3 O 8 equivalent 2011 2012 2013 2014 P2015 Owners and operators of U.S. civilian nuclear power reactors 89,835 97,647 113,007 114,046 120,857 U.S. brokers and traders 6,841 5,677 7,926 5,916 5,678 U.S. converter, enrichers, fabricators, and producers 15,428 17,611 13,416 12,766 9,388 Total commercial inventories 112,104 120,936 134,418 132,728 135,923 thousand pounds U 3 O 8 equivalent

  3. 2015 Uranium Marketing Annual Report

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

    3 2015 Uranium Marketing Annual Report Release Date: May 24, 2016 Next Release Date: May 2017 Quantity with reported price Weighted-average price Quantity with reported price Weighted-average price Quantity with reported price Weighted- average price First 7,175 34.34 6,665 30.26 6,807 29.68 Second 7,175 41.29 6,665 35.11 6,807 36.03 Third 7,175 45.89 6,665 39.29 6,807 38.63 Fourth 7,175 49.84 6,665 43.36 6,807 41.80 Fifth 7,175 53.17 6,665 46.74 6,807 44.63 Sixth 7,175 57.24 6,665 50.65 6,807

  4. Uranium Marketing Annual Report - Energy Information Administration

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

    Uranium Marketing Annual Report With Data for 2015 | Release Date: May 24, 2016 | Next Release Date: May 2017 | full report Previous reports Year: 2014 2013 2012 2011 2010 2009 ...

  5. Coal industry annual 1993

    SciTech Connect (OSTI)

    Not Available

    1994-12-06

    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.

  6. 2014 Uranium Marketing Annual Report

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

    By law, EIA's data, analyses, and forecasts are independent ... on information reported on Form EIA-858, "Uranium Marketing ... nuclear power reactors by contract type and material type, ...

  7. 2015 Uranium Marketing Annual Report

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

    4. Uranium sellers to owners and operators of U.S. civilian nuclear power reactors, 2013-15" 2013,2014,2015 "American Fuel Resources, LLC","Advance Uranium Asset Management Ltd.","AREVA / AREVA NC, Inc." "AREVA NC, Inc.","AREVA / AREVA NC, Inc.","ARMZ (AtomRedMetZoloto)" "BHP Billiton Olympic Dam Corporation Pty Ltd","ARMZ (AtomRedMetZoloto)","BHP Billiton Olympic Dam Corporation Pty Ltd"

  8. Uranium Mining, Conversion, and Enrichment Industries

    Energy Savers [EERE]

    i Analysis of Potential Impacts of Uranium Transfers on the Domestic Uranium Mining, Conversion, and Enrichment Industries May 1, 2015 ii EXECUTIVE SUMMARY: The Department of Energy ("Department" or "DOE") plans to transfer the equivalent of up to 2,100 metric tons ("MTU") of natural uranium per year (with a higher total for calendar year 2015, mainly because of transfers already executed or under way before today's determination). These transfers would include

  9. Coal Industry Annual 1995

    SciTech Connect (OSTI)

    1996-10-01

    This report presents data on coal consumption, coal distribution, coal stocks, coal prices, coal quality, and emissions 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 does not include coal consumption data for nonutility power producers that are not in the manufacturing, agriculture, mining, construction, or commercial sectors. Consumption for nonutility power producers not included in this report is estimated to be 21 million short tons for 1995.

  10. Coal industry annual 1996

    SciTech Connect (OSTI)

    1997-11-01

    This report presents data on coal consumption, coal distribution, coal stocks, coal prices, and coal quality, and emissions 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 does not include coal consumption data for nonutility power producers that are not in the manufacturing, agriculture, mining, construction, or commercial sectors. Consumption for nonutility power producers not included in this report is estimated to be 24 million short tons for 1996. 14 figs., 145 tabs.

  11. Uranium Marketing Annual Report - Release Date: May 31, 2011

    Gasoline and Diesel Fuel Update (EIA)

    Note: Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual Survey" (2013-...

  12. 2013 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Scientific and Technical Information (OSTI)

    Control Act Title II Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act ...

  13. 2013 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Scientific and Technical Information (OSTI)

    Control Act Title I Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act ...

  14. Abandoned Uranium Mine Technical Services and Cleanup Industry...

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

    Abandoned Uranium Mine Technical Services and Cleanup Industry Day In January 2015, the United States (U.S.) and the Anadarko Litigation Trust ("Litigation Trust") entered into a...

  15. The US uranium industry: Regulatory and policy impediments

    SciTech Connect (OSTI)

    Drennen, T.E.; Glicken, J.

    1995-06-01

    The Energy Policy Act of 1992 required the DOE to develop recommendations and implement government programs to assist the domestic uranium industry in increasing export opportunities. In 1993, as part of that effort, the Office of Nuclear Energy identified several key factors that could (or have) significantly impact(ed) export opportunities for domestic uranium. This report addresses one of these factors: regulatory and policy impediments to the flow of uranium products between the US and other countries. It speaks primarily to the uranium market for civil nuclear power. Changes in the world political and economic order have changed US national security requirements, and the US uranium industry has found itself without the protected market it once enjoyed. An unlevel playing field for US uranium producers has resulted from a combination of geology, history, and a general US political philosophy of nonintervention that precludes the type of industrial policy practiced in other uranium-exporting countries. The US has also been hampered in its efforts to support the domestic uranium-producing industry by its own commitment to free and open global markets and by international agreements such as GATT and NAFTA. Several US policies, including the imposition of NRC fees and licensing costs and Harbor Maintenance fees, directly harm the competitiveness of the domestic uranium industry. Finally, requirements under US law, such as those in the 1979 Nuclear Nonproliferation Act, place very strict limits on the use of US-origin uranium, limitations not imposed by other uranium-producing countries. Export promotion and coordination are two areas in which the US can help the domestic uranium industry without violating existing trade agreements or other legal or policy constraints.

  16. Chemical Industry Vision 2020. Annual Report 2004 (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Chemical Industry Vision 2020. Annual Report 2004 Citation Details In-Document Search Title: Chemical Industry Vision 2020. Annual Report 2004 This publication is an annual report on the activities of the Chemical Industry Vision 2020 Technology Partnership. Authors: None, None Publication Date: 2005-06-01 OSTI Identifier: 1218618 Resource Type: Technical Report Research Org: EERE Publication and Product Library Sponsoring Org: USDOE Office of Energy Efficiency and Renewable

  17. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings

    Office of Scientific and Technical Information (OSTI)

    Radiation Control Act Title I Disposal Sites (Technical Report) | SciTech Connect Technical Report: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites This report, in fulfillment of a license requirement, presents the results of long-term surveillance and

  18. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings

    Office of Scientific and Technical Information (OSTI)

    Radiation Control Act Title II Disposal Sites (Technical Report) | SciTech Connect Technical Report: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites Citation Details In-Document Search Title: 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites This report, in fulfillment of a license requirement, presents the results of long-term surveillance and

  19. Asphalt emulsion sealing of uranium mill tailings. 1979 annual report

    SciTech Connect (OSTI)

    Hartley, J.N.; Koehmstedt, P.L.; Esterl, D.J.; Freeman, H.D.

    1980-06-01

    Uranium mill tailings are a source of low-level radiation and radioactive materials that may be released into the environment. Stabilization or disposal of these tailings in a safe and environmentally sound way is necessary to minimize radon exhalation and other radioactive releases. One of the most promising concepts for stabilizing uranium tailings is being investigated at the Pacific Northwest Laboratory: the use of asphalt emulsion to contain radon and other potentially hazardous materials in uranium tailings. Results of these studies indicate that radon flux from uranium tailings can be reduced by greater than 99% by covering the tailings with an asphalt emulsion that is poured on or sprayed on (3.0 to 7.0 mm thick), or mixed with some of the tailings and compacted to form an admixture seal (2.5 to 15.2 cm) containing 18 wt % residual asphalt.

  20. Uranium Marketing Annual Report - Release Date: May 31, 2011

    Gasoline and Diesel Fuel Update (EIA)

    4. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by origin and material type, 2014 deliveries thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries Uranium concentrate Natural UF6 Enriched UF6 Total U.S.-origin uranium Purchases 2,004 1,312 0 3,316 Weighted-average price 49.87 45.41 -- 48.11 Foreign-origin uranium Purchases 27,257 16,491 6,285 50,033 Weighted-average price 44.56 48.98 44.69 46.03 Total Purchases 29,260 17,803 6,285

  1. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... This encroachment presents no threat to the integrity of the disposal cell and occurred ... This encroachment is visually monitored annually and periodically documented with ...

  2. Uranium Mill Tailings Remedial Action Program. Annual status report

    SciTech Connect (OSTI)

    Not Available

    1983-12-01

    The FY 1983 project accomplishments are: completed the Remedial Action Plan and Phase I engineering design for the Canonsburg processing site; completed remedial action on an additional 52 vicinity properties and the inclusion of an additional 303 properties in the Uranium Mill Tailings Remedial Action Project; executed cooperative agreements with four states and the Navajo Nation; published the draft environmental impact statement for Salt Lake City site; and issued the approved Project Plan.

  3. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    DOE and the State complied with requirements for parcel ... for erosion, changes in land use, or other phenomena that ... A significant increase in oil and gas industry activity ...

  4. Advanced Industrial Materials (AIM) Program: Annual progress report FY 1995

    SciTech Connect (OSTI)

    1996-04-01

    In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This Annual Report for FY 1995 contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Areas covered here are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

  5. Industrial safety and applied health physics. Annual report for 1980

    SciTech Connect (OSTI)

    Not Available

    1981-11-01

    Information is reported in sections entitled: radiation monitoring; Environmental Management Program; radiation and safety surveys; industrial safety and special projects; Office of Operational Safety; and training, lectures, publications, and professional activities. There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 35 employees received whole body dose equivalents of 10 mSv (1 rem) or greater. There were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. The quantity of those radionuclides of primary concern in the Clinch River, based on the concentration measured at White Oak Dam and the dilution afforded by the Clinch River, averaged 0.16 percent of the concentration guide. The average background level at the Perimeter Air Monitoring (PAM) stations during 1980 was 9.0 ..mu..rad/h (0.090 ..mu..Gy/h). Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 1.5 Bq/kg (0.04 pCi/g), and the uranium-235 content ranged from 0.7 Bq/kg (0.02 pCi/g) to 16 Bq/kg (0.43 pCi/g). Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.04 Bq/kg (0.001 pCi/g) to 0.07 Bq/kg (0.002 pCi/g), and the uranium-235 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 12 Bq/kg (0.33 pCi/g).

  6. Uranium Mill Tailings Remedial Action Program. Annual status report

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

    The purpose, scope, history, requirements, and management organization of the UMTRA Program are summarized in the Introduction. The remainder of the report describes progress made during the past year (F 1980) and discusses future plants and activities. Early emphasis has been on the four highest-priority sites because of their proximity to population centers. These sites are: (1) Canonsburg, Pennsylvania; (2) Salt Lake City, Utah; (3) Durango, Colorado; and (4) Shiprock, New Mexico (Navajo Reservation). To date, twenty-five vicinity properties near the Canonsburg site and two such properties near the Salt Lake City site have been designated for remedial action. A research effort was undertaken at a major vicinity property, the Mountain States Supply Company in Salt Lake City, to study the effects of heating-and-ventilating-system modification on indoor radon-daughter concentrations. A cooperative agreement was executed between DOE and the Commonwealth of Pennsylvania. A similar agreement with the State of Utah is expected to be executed in early FY 1981. Further, it is expected that additional cooperative agreements will be negotiated during FY 1981 with the States of Colorado and Wyoming and the Navajo Nation. It is expected that the processing site at Canonsburg, PA (the Canonsburg Industrial Park) will be acquired during FY 1981. Draft Environmental Impact Statements for the four highest-priority sites will be completed during FY 1981.

  7. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    UMTRCA Title I Annual Report March 2016 Grand Junction, Colorado Page 6-1 6.0 Grand Junction, Colorado, Disposal Site 6.1 Compliance Summary The Grand Junction, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on December 8, 2015. A portion of the disposal cell remains open to receive low-level radioactive materials from various sources; the open cell and its supporting structures and facilities are not included in the annual inspection. Ongoing

  8. uranium

    National Nuclear Security Administration (NNSA)

    to prepare surplus plutonium for disposition, and readiness to begin the Second Uranium Cycle, to start processing spent nuclear fuel.

    H Canyon is also being...

  9. Industrial safety and applied health physics. Annual report, 1979

    SciTech Connect (OSTI)

    Not Available

    1980-09-01

    In connection with personnel monitoring, there were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 55 employees received whole-body dose equivalent of one rem or greater. The highest whole-body dose equivalent to an employee was 2.8 rem. The highest internal exposure was less than one-half of a maximum permissible dose for any calendar quarter. During 1979, 57 portable health physics instruments were added to the inventory and 75 retired. The total number in service on January 1, 1979, was 977. With regards to environmental monitoring, there were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.01 to 0.06 pCi/g, and the uranium-235 content ranged from 0.01 to 0.05 pCi/g. Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.001 to 0.010 pCi/g, and uranium-235 content ranged from 0.001 to 0.010 pCi/g. Two radiation incidents involving radioactive materials were recorded during 1979. This compares with 14 incidents in 1978. (ERB)

  10. Advanced Industrial Materials (AIM) Program annual progress report, FY 1997

    SciTech Connect (OSTI)

    1998-05-01

    The Advanced Industrial Materials (AIM) Program is a part of the Office of Industrial Technologies (OIT), Energy Efficiency and Renewable Energy, US Department of Energy (DOE). The mission of AIM is to support development and commercialization of new or improved materials to improve energy efficiency, productivity, product quality, and reduced waste in the major process industries. OIT has embarked on a fundamentally new way of working with industries--the Industries of the Future (IOF) strategy--concentrating on the major process industries that consume about 90% of the energy and generate about 90% of the waste in the industrial sector. These are the aluminum, chemical, forest products, glass, metalcasting, and steel industries. OIT has encouraged and assisted these industries in developing visions of what they will be like 20 or 30 years into the future, defining the drivers, technology needs, and barriers to realization of their visions. These visions provide a framework for development of technology roadmaps and implementation plans, some of which have been completed. The AIM Program supports IOF by conducting research and development on materials to solve problems identified in the roadmaps. This is done by National Laboratory/industry/university teams with the facilities and expertise needed to develop new and improved materials. Each project in the AIM Program has active industrial participation and support.

  11. United States transuranium and uranium registries. Annual report, October 1, 1995--September 30, 1996

    SciTech Connect (OSTI)

    Kathren, R.L.; Ehrhart, S.M.

    1997-04-01

    This Annual Report covers the period October 1, 1995 through September 30, 1996, and includes both scientific and administrative activities. As of September 30, 1996, the Registries had a total of 886 registrants of whom 350 were deceased and 292 classified as active. An anticipated funding cut of approximately 35% for the period beginning October 1, 1996, necessitated some staff cuts, but it is anticipated that the Registries core research will be maintained albeit at a somewhat slower pace. The Registries received approximately 60 public information requests or inquiries ranging over a wide range of topics, about a third of which came from the media or official agencies, including Congress. Specific noteworthy inquiries were received from the President`s Advisory Committee on the Gulf War Veterans with regard to uranium biokinetics and toxicity, and from the County of Los Angeles and the State of California with regard to the management and dosimetry of two separate instances of acute accidental intakes of {sup 241}Am.

  12. Advanced Industrial Materials Program. Annual progress report, FY 1993

    SciTech Connect (OSTI)

    Stooksbury, F.

    1994-06-01

    Mission of the AIM program is to commercialize new/improved materials and materials processing methods that will improve energy efficiency, productivity, and competitiveness. Program investigators in the DOE national laboratories are working with about 100 companies, including 15 partners in CRDAs. Work is being done on intermetallic alloys, ceramic composites, metal composites, polymers, engineered porous materials, and surface modification. The program supports other efforts in the Office of Industrial Technologies to assist the energy-consuming process industries. The aim of the AIM program is to bring materials from basic research to industrial application to strengthen the competitive position of US industry and save energy.

  13. Chemical Industry Vision 2020. Annual Report 2004 (Technical...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY Industry; ITP; AMO; Chemicals; Vision Word Cloud More ...

  14. Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2006

    SciTech Connect (OSTI)

    Primm, R. T.; Ellis, R. J.; Gehin, J. C.; Clarno, K. T.; Williams, K. A.; Moses, D. L.

    2006-11-01

    Neutronics and thermal-hydraulics studies show that, for equivalent operating power [85 MW(t)], a low-enriched uranium (LEU) fuel cycle based on uranium-10 wt % molybdenum (U-10Mo) metal foil with radially, “continuously graded” fuel meat thickness results in a 15% reduction in peak thermal flux in the beryllium reflector of the High Flux Isotope Reactor (HFIR) as compared to the current highly enriched uranium (HEU) cycle. The uranium-235 content of the LEU core is almost twice the amount of the HEU core when the length of the fuel cycle is kept the same for both fuels. Because the uranium-238 content of an LEU core is a factor of 4 greater than the uranium-235 content, the LEU HFIR core would weigh 30% more than the HEU core. A minimum U-10Mo foil thickness of 84 ?m is required to compensate for power peaking in the LEU core although this value could be increased significantly without much penalty. The maximum U-10Mo foil thickness is 457?m. Annual plutonium production from fueling the HFIR with LEU is predicted to be 2 kg. For dispersion fuels, the operating power for HFIR would be reduced considerably below 85 MW due to thermal considerations and due to the requirement of a 26-d fuel cycle. If an acceptable fuel can be developed, it is estimated that $140 M would be required to implement the conversion of the HFIR site at Oak Ridge National Laboratory from an HEU fuel cycle to an LEU fuel cycle. To complete the conversion by fiscal year 2014 would require that all fuel development and qualification be completed by the end of fiscal year 2009. Technological development areas that could increase the operating power of HFIR are identified as areas for study in the future.

  15. final ERI-2142 18-1501 Analysis of Potential Effects on Domestic Industries of DOE Excess Uranium Inventory 2015-2024.docx

    Energy Savers [EERE]

    ERI-2142.18-1501 Analysis of the Potential Effects on the Domestic Uranium Mining, Conversion and Enrichment Industries of the Introduction of DOE Excess Uranium Inventory During CY 2015 Through 2024 ENERGY RESOURCES INTERNATIONAL, INC. 1015 18 th Street, NW, Suite 650 Washington, DC 20036 USA Telephone: (202) 785-8833 Facsimile: (202) 785-8834 ERI-2142.18-1501 Analysis of the Potential Effects on the Domestic Uranium Mining, Conversion and Enrichment Industries of the Introduction of DOE

  16. Industrial Hygiene Group annual research report, FY 1981

    SciTech Connect (OSTI)

    Jackson, J.O.; Ettinger, H.J. (comps.)

    1982-10-01

    Field studies have been performed at several oil shale facilities to identify unique industrial hygiene problems and provide input to inhalation toxicology studies aimed at evaluating the hazards of materials associated with this developing technology. Aerosol physics support has also been provided to develop aerosol generation and animal exposure techniques for evaluating the toxicity of oil shale materials and manmade mineral fibers. As part of the effort to assure a safe, orderly, and timely development of various synfuels, field evaluation of indicator-sampling procedures was perfomed, and industrial hygiene work practices for two synfuel technologies are being prepared. Respirator studies are used to evaluate the performances of special devices (some of which are not in the existing government approval schedules) and of a proposed test procedures for self-contained breathing apparatus. An approval procedure is being developed for air-purifying respirators required for protection against radioiodine, evaluating the adequacy of respirator programs at the Nuclear Regulatory Commission licensee facilities, and developing a program for respirator use under emergency situations. A new aerosol size-characterization stack sampler has been designed, and potential instrument changes to aerosol size monitoring for filter testing are being evaluated. Material permeability tests have identified the protection afforded by protective clothing materials, and improved analytical procedures have been developed for pentachlorophenol and plutonium.

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

    SciTech Connect (OSTI)

    Demuth, Scott F; Grice, Thomas; Lockwood, Dunbar

    2010-01-01

    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.

  18. United States Transuranium and Uranium Registries. Annual report February 1, 2000--January 31, 2001

    SciTech Connect (OSTI)

    Ehrhart, Susan M.; Filipy, Ronald E.

    2001-07-01

    The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 2000 through January 2001.

  19. The United States Transuranium and Uranium Registries. Revision 1, [Annual] report, October 1, 1990--April 1992

    SciTech Connect (OSTI)

    Kathren, R.L.

    1992-09-01

    This paper describes the history, organization, activities and recent scientific accomplishments of the United States Transuranium and Uranium Registries. Through voluntary donations of tissue obtained at autopsies, the Registries carry out studies of the concentration, distribution and biokinetics of plutonium in occupationally exposed persons. Findings from tissue analyses from more than 200 autopsies include the following: a greater proportion of the americium intake, as compared with plutonium, was found in the skeleton; the half-time of americium in liver is significantly shorter than that of plutonium; the concentration of actinide in the skeleton is inversely proportional to the calcium and ash content of the bone; only a small percentage of the total skeletal deposition of plutonium is found in the marrow, implying a smaller risk from irradiation of the marrow relative to the bone surfaces; estimates of plutonium body burden made from urinalysis typically exceed those made from autopsy data; pathologists were unable to discriminate between a group of uranium workers and persons without known occupational exposure on the basis of evaluation of microscopic kidney slides; the skeleton is an important long term depot for uranium, and that the fractional uptake by both skeleton and kidney may be greater than indicated by current models. These and other findings and current studies are discussed in depth.

  20. Design Study for a Low-enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2007

    SciTech Connect (OSTI)

    Primm, Trent; Ellis, Ronald James; Gehin, Jess C; Ilas, Germina; Miller, James Henry; Sease, John D

    2007-11-01

    This report documents progress made during fiscal year 2007 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low enriched uranium fuel (LEU). Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. A high volume fraction U/Mo-in-Al fuel could attain the same neutron flux performance as with the current, HEU fuel but materials considerations appear to preclude production and irradiation of such a fuel. A diffusion barrier would be required if Al is to be retained as the interstitial medium and the additional volume required for this barrier would degrade performance. Attaining the high volume fraction (55 wt. %) of U/Mo assumed in the computational study while maintaining the current fuel plate acceptance level at the fuel manufacturer is unlikely, i.e. no increase in the percentage of plates rejected for non-compliance with the fuel specification. Substitution of a zirconium alloy for Al would significantly increase the weight of the fuel element, the cost of the fuel element, and introduce an as-yet untried manufacturing process. A monolithic U-10Mo foil is the choice of LEU fuel for HFIR. Preliminary calculations indicate that with a modest increase in reactor power, the flux performance of the reactor can be maintained at the current level. A linearly-graded, radial fuel thickness profile is preferred to the arched profile currently used in HEU fuel because the LEU fuel media is a metal alloy foil rather than a powder. Developments in analysis capability and nuclear data processing techniques are underway with the goal of verifying the preliminary calculations of LEU flux performance. A conceptual study of the operational cost of an LEU fuel fabrication facility yielded the conclusion that the annual fuel cost to the HFIR would increase significantly from the current, HEU fuel cycle. Though manufacturing can be accomplished with existing technology, several engineering proof-of-principle tests would be required. The RERTR program is currently conducting a series of generic fuel qualification tests at the Advanced Test Reactor. A review of these tests and a review of the safety basis for the current, HEU fuel cycle led to the identification of a set of HFIR-specific fuel qualification tests. Much additional study is required to formulate a HFIR-specific fuel qualification plan from this set. However, one such test - creating a graded fuel profile across a flat foil - has been initiated with promising results.

  1. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    SciTech Connect (OSTI)

    2014-03-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

  2. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    SciTech Connect (OSTI)

    2013-11-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

  3. United States Transuranium and Uranium Registries. Annual report, February 1, 2003 - January 31, 2004

    SciTech Connect (OSTI)

    Alldredge, J. R.; Brumbaugh, T. L.; Ehrhart, Susan M.; Elliston, J. T.; Filipy, R. E.; James, A. C.; Pham, M. V.; Wood, T. G.; Sasser, L. B.

    2004-01-31

    This year was my fourteenth year with the U. S. Transuranium and Uranium Registries (USTUR). How time flies! Since I became the director of the program five years ago, one of my primary goals was to increase the usefulness of the large USTUR database that consists of six tables containing personal information, medical histories, radiation exposure histories, causes of death, and the results of radiochemical analysis of organ samples collected at autopsy. It is essential that a query of one or more of these tables by USTUR researchers or by collaborating researchers provides complete and reliable information. Also, some of the tables (those without personal identifiers) are destined to appear on the USTUR website for the use of the scientific community. I am pleased to report that most of the data in the database have now been verified and formatted for easy query. It is important to note that no data were discarded; copies of the original tables were retained and the original paper documents are still available for further verification of values as needed.

  4. Economic analysis of solar industrial process heat systems: a methodology to determine annual required revenue and internal rate of return

    SciTech Connect (OSTI)

    Dickinson, W.C.; Brown, K.C.

    1981-08-11

    To permit an economic evaluation of solar industrial process heat systems, a methodology was developed to determine the annual required revenue and the internal rate of return. First, a format is provided to estimate the solar system's installed cost, annual operating and maintenance expenses, and net annual solar energy delivered to the industrial process. Then an expression is presented that gives the annual required revenue and the price of solar energy. The economic attractiveness of the potential solar investment can be determined by comparing the price of solar energy with the price of fossil fuel, both expressed in levelized terms. This requires calculation of the internal rate of return on the solar investment or, in certain cases, the growth rate of return.

  5. Energy Conservation Program for Consumer Products and Commercial and Industrial Equipment-- AHRI Annual Meeting CCE Overview and Update Presenation, dated April 13, 2011

    Broader source: Energy.gov [DOE]

    This document is the Energy Conservation Program for Consumer Products and Commercial and Industrial Equipment-- AHRI Annual Meeting CCE Overview and Update Presenation, dated April 13, 2011

  6. Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual report for FY 2009

    SciTech Connect (OSTI)

    Chandler, David; Freels, James D; Ilas, Germina; Miller, James Henry; Primm, Trent; Sease, John D; Guida, Tracey; Jolly, Brian C

    2010-02-01

    This report documents progress made during FY 2009 in studies of converting the High Flux Isotope Reactor (HFIR) from high enriched uranium (HEU) fuel to low enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in reactor performance from the current level. Results of selected benchmark studies imply that calculations of LEU performance are accurate. Studies are reported of the application of a silicon coating to surrogates for spheres of uranium-molybdenum alloy. A discussion of difficulties with preparing a fuel specification for the uranium-molybdenum alloy is provided. A description of the progress in developing a finite element thermal hydraulics model of the LEU core is provided.

  7. DESIGN STUDY FOR A LOW-ENRICHED URANIUM CORE FOR THE HIGH FLUX ISOTOPE REACTOR, ANNUAL REPORT FOR FY 2010

    SciTech Connect (OSTI)

    Cook, David Howard; Freels, James D; Ilas, Germina; Jolly, Brian C; Miller, James Henry; Primm, Trent; Renfro, David G; Sease, John D; Pinkston, Daniel

    2011-02-01

    This report documents progress made during FY 2010 in studies of converting the High Flux Isotope Reactor (HFIR) from high enriched uranium (HEU) fuel to low enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in performance to users from the current level. Studies are reported of support to a thermal hydraulic test loop design, the implementation of finite element, thermal hydraulic analysis capability, and infrastructure tasks at HFIR to upgrade the facility for operation at 100 MW. A discussion of difficulties with preparing a fuel specification for the uranium-molybdenum alloy is provided. Continuing development in the definition of the fuel fabrication process is described.

  8. 2015 Domestic Uranium Production Report

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

    Domestic Uranium Production Report 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 Table 9. Summary production statistics of the U.S. uranium industry, 1993-2015 Exploration and Development Surface Exploration and Development Drilling Mine Production of Uranium Uranium Concentrate Production Uranium Concentrate Shipments Employment Year Drilling (million feet) Expenditures 1 (million dollars) (million pounds U 3 O 8 ) (million pounds U 3 O 8 )

  9. Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2008

    SciTech Connect (OSTI)

    Primm, Trent [ORNL; Chandler, David [ORNL; Ilas, Germina [ORNL; Miller, James Henry [ORNL; Sease, John D [ORNL; Jolly, Brian C [ORNL

    2009-03-01

    This report documents progress made during FY 2008 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in reactor performance from the current level. Results of selected benchmark studies imply that calculations of LEU performance are accurate. Scoping experiments with various manufacturing methods for forming the LEU alloy profile are presented.

  10. Uranium Marketing Annual Report -

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

    Foreign-origin Total U.S.-origin Foreign-origin Total U.S.-origin Foreign-origin Total China 0 W W 0 W W W W W France 0 4,578 4,578 0 1,606 1,606 0 3.055 3,055 Germany W W 1,904 W ...

  11. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    work units (SWU) Country of enrichment service (SWU-origin) 2010 2011 2012 2013 2014 China 0 W W W 636 France W W 0 0 0 Germany 681 1,539 1,075 753 1,005 Netherlands 2,292 1,506 ...

  12. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    by owners and operators of U.S. civilian nuclear power reactors by supplier and delivery ... Owners and Operators of U.S. Civilian Nuclear Power Reactors Purchases 0 0 0 0 0 ...

  13. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    by owners and operators of U.S. civilian nuclear power reactors, 1994-2014 dollars per ... owners and operators of U.S. civilian nuclear power reactors, other U.S. suppliers, ...

  14. Uranium Marketing Annual Report

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

    nuclear power reactors, 1994-2014 million pounds U3O8 equivalent million separative work units (SWU) Year Feed deliveries by owners and operators of U.S. civilian nuclear ...

  15. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    b. Weighted-average price of foreign purchases and foreign sales by U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors, 1994-2014 dollars per pound U3O8 equivalent Delivery year Foreign purchases by U.S. suppliers Foreign purchases by owners and operators of U.S. civilian nuclear power reactors Total foreign purchases (weighted-average price) U.S. broker and trader purchases from foreign suppliers (weighted-average price) Foreign sales (weighted-average price) 1994

  16. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    7. Purchases of enrichment services by owners and operators of U.S. civilian nuclear power reactors by contract type in delivery year, 2014 thousand separative work units (SWU) Enrichment service contract type U.S. enrichment Foreign enrichment Total Spot W W 628 Long-term W W 12,310 Total 3,773 9,165 12,939 W = Data withheld to avoid disclosure of individual company data. Note: Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information

  17. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    8. Contracts signed in 2014 by owners and operators of U.S. civilian nuclear power reactors by contract type thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Purchase contract type (Signed in 2014) Quantity of deliveries received in 2014 Weighted-average price Number of purchase contracts for deliveries in 2014 Spot W W 67 Long-term W W 2 Total 12,263 34.83 69 W = Data withheld to avoid disclosure of individual company data. Notes: Totals may not equal sum of components because

  18. Delivered Energy Consumption Projections by Industry in the Annual Energy Outlook 2002

    Reports and Publications (EIA)

    2002-01-01

    This paper presents delivered energy consumption and intensity projections for the industries included in the industrial sector of the National Energy Modeling System.

  19. Uranium Leasing Program Environmental Documents | Department of Energy

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

    Environmental Documents Uranium Leasing Program Environmental Documents Uranium Leasing Program 2015 Mitigation Action Plan Activity Summary Report (March 2016) The DOE Uranium Leasing Program's 2015 Mitigation Action Plan Activity Summary fulfills the mitigation plan's requirement to annually notify the public of mitigation activities completed by Uranium Leasing Program lessees. Uranium Leasing Program Mitigation Action Plan for the Final Uranium Leasing Program Programmatic Environmental

  20. Low-Enriched Uranium Fuel Conversion Activities for the High Flux Isotope Reactor, Annual Report for FY 2011

    SciTech Connect (OSTI)

    Renfro, David G; Cook, David Howard; Freels, James D; Griffin, Frederick P; Ilas, Germina; Sease, John D; Chandler, David

    2012-03-01

    This report describes progress made during FY11 in ORNL activities to support converting the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum (UMo) alloy. With both radial and axial contouring of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in performance to users from the current levels achieved with HEU fuel. Studies are continuing to demonstrate that the fuel thermal safety margins can be preserved following conversion. Studies are also continuing to update other aspects of the reactor steady state operation and accident response for the effects of fuel conversion. Technical input has been provided to Oregon State University in support of their hydraulic testing program. The HFIR conversion schedule was revised and provided to the GTRI program. In addition to HFIR conversion activities, technical support was provided directly to the Fuel Fabrication Capability program manager.

  1. Residential Demand Sector Data, Commercial Demand Sector Data, Industrial Demand Sector Data - Annual Energy Outlook 2006

    SciTech Connect (OSTI)

    2009-01-18

    Tables describing consumption and prices by sector and census division for 2006 - includes residential demand, commercial demand, and industrial demand

  2. United States Transuranium and Uranium Registries: Researching radiation protection. USTUR annual report for February 1, 1999 through January 31, 2000

    SciTech Connect (OSTI)

    Ehrhart, Susan M.; Filipy, Ronald E.

    2000-07-01

    The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 1999 through January 2000.

  3. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Office of Legacy Management (LM)

    Sherwood, Washington Page 5-1 5.0 Sherwood, Washington, Disposal Site 5.1 Compliance Summary The Sherwood, Washington, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on May 20, 2015. The tailings impoundment, dam, and diversion channel were in good condition. The dam inspection and associated piezometer water level measurements verified that the tailings dam is functioning as designed. A damaged perimeter sign was replaced in July 2015. Inspectors

  4. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Report March 2016 Canonsburg, Pennsylvania Page 3-1 3.0 Canonsburg, Pennsylvania, Disposal Site 3.1 Compliance Summary The Canonsburg, Pennsylvania, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on October 27, 2015. The site was in excellent condition. No evidence of erosion or slope instability was observed on the disposal cell. A trespass campsite was discovered hidden among the trees in the southwest corner of the property, outside the perimeter

  5. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Lakeview, Oregon Page 9-1 9.0 Lakeview, Oregon, Disposal Site 9.1 Compliance Summary The Lakeview, Oregon, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected September 16 and 17, 2015. Other than some ongoing concern with erosion-control rock riprap degradation, the disposal cell was in good condition. Some minor fence repairs and vegetation removal, and minor erosion repair work along the west site fence is planned. Inspectors identified no other

  6. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Office of Legacy Management (LM)

    Bluewater, New Mexico Page 1-1 1.0 Bluewater, New Mexico, Disposal Site 1.1 Compliance Summary The Bluewater, New Mexico, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on August 19 and 20, 2015. A significant pond was present on the top slope of the main tailings disposal cell cover in an area where shallow depressions are present; disposal cell performance is being evaluated to determine if additional monitoring or cover enhancement is necessary.

  7. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Gunnison, Colorado Page 8-1 8.0 Gunnison, Colorado, Disposal Site 8.1 Compliance Summary The Gunnison, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on July 1, 2015. The disposal cell and all associated surface water diversion and drainage structures were in excellent condition and functioning as designed. Six riprap test areas on the cell apron and diversion ditches were visually inspected; no rock degradation was noted when compared to 2012

  8. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Rifle, Colorado Page 14-1 14.0 Rifle, Colorado, Disposal Site 14.1 Compliance Summary The Rifle, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 30, 2015. The disposal cell and all associated surface-water diversion and drainage structures were in good condition and functioning as designed. Vegetation on the site was in excellent condition. Minor fence repairs and perimeter sign maintenance will be conducted prior to the next inspection.

  9. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Green River, Utah Page 7-1 7.0 Green River, Utah, Disposal Site 7.1 Compliance Summary The Green River, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on March 18, 2015. The disposal cell was in excellent condition. One missing perimeter sign was replaced during the inspection. Inspectors identified no other maintenance needs or cause for a follow-up or contingency inspection. 7.2 Compliance Requirements Requirements for the long-term surveillance

  10. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Durango, Colorado Page 4-1 4.0 Durango, Colorado, Disposal Site 4.1 Compliance Summary The Durango, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 2, 2015. The disposal cell was in good condition. Vegetation on top of the disposal cell was healthy, and several small shrubs growing on the side slopes will be controlled. A small depression observed in 2014 on the disposal cell side slope was no longer apparent. Inspectors identified no

  11. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Naturita, Colorado Page 13-1 13.0 Naturita, Colorado, Disposal Site 13.1 Compliance Summary The Naturita, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on May 12, 2015. The site was in excellent condition. A section of the perimeter fence had been trampled down and several loose fence strands were identified. The fence sections were repaired 2 weeks after the inspection. Inspectors identified no other needs or cause for a follow-up or

  12. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Salt Lake City, Utah Page 15-1 15.0 Salt Lake City, Utah, Disposal Site 15.1 Compliance Summary The Salt Lake City, Utah, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on June 22, 2015. The disposal cell was in good condition. Observations of rock quality monitoring plots indicated no obvious change from the previous year. Inspectors did note vegetation buildup along the access road that surrounds the cell. No waste debris or indication of windblown or

  13. 2015 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Office of Legacy Management (LM)

    Slick Rock, Colorado Page 17-1 17.0 Slick Rock, Colorado, Disposal Site 17.1 Compliance Summary The Slick Rock, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site was inspected on May 12, 2015. The site was in good condition. Inspectors identified contact information that needed updating on the entrance sign; no other maintenance needs or cause for a follow-up inspection was required. 17.2 Compliance Requirements Requirements for the long-term surveillance and

  14. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    David Frederick

    2012-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA-000160-01), for the wastewater reuse site at the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: (1) Facility and system description; (2) Permit required effluent monitoring data and loading rates; (3) Groundwater monitoring data; (4) Status of special compliance conditions; and (5) Discussion of the facility's environmental impacts. During the 2011 reporting year, an estimated 6.99 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. Using the dissolved iron data, the concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  15. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2013 through October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Groundwater monitoring data; Status of special compliance conditions; Noncompliance issues; and Discussion of the facility’s environmental impacts During the 2014 reporting year, an estimated 10.11 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  16. 2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2012 reporting year, an estimated 11.84 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  17. 2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    David B. Frederick

    2011-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from May 1, 2010 through October 31, 2010. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2010 partial reporting year, an estimated 3.646 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  18. "Annual Electric Power Industry Report (EIA-861 data file)

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

    1 DETAILED DATA Revisions \ Corrections for electric power sales, revenue, and energy efficiency Form EIA-861 detailed data files Annual data revisions: January 13, 2016 The re-release of the form EIA-861 survey data: January 13, 2016 Revenue data values were revised due to enhancements to the SEDAPs imputation system.

  19. "Annual Electric Power Industry Report (EIA-861 data file)

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

    Electric Sales, Revenue, and Average Price Correction/Update Annual data revisions: January 13, 2016 The re-release of the form EIA-861 survey data: January 13, 2016 Revenue data values were revised due to enhancements to the SEDAPs imputation system. Contact: Electricity data experts

  20. United States transuranium and uranium registries - 25 years of growth, research, and service. Annual report, April 1992--September 1993

    SciTech Connect (OSTI)

    Kathren, R.L.; Harwick, L.A.; Toohey, R.E.; Russell, J.J.; Filipy, R.E.; Dietert, S.E.; Hunacek, M.M.; Hall, C.A.

    1994-10-01

    The Registries originated in 1968 as the National Plutonium Registry with the name changed to the United States Transuranium Registry the following year to reflect a broader concern with the heavier actinides as well. Initially, the scientific effort of the USTR was directed towards study of the distribution and dose of plutonium and americium in occupationally exposed persons, and to assessment of the effects of exposure to the transuranium elements on health. This latter role was reassessed during the 1970`s when it was recognized that the biased cohort of the USTR was inappropriate for epidemiologic analysis. In 1978, the administratively separate but parallel United States Uranium Registry was created to carry out similar work among persons exposed to uranium and its decay products. A seven member scientific advisory committee provided guidance and scientific oversight. In 1992, the two Registries were administratively combined and transferred from the purview of a Department of Energy contractor to Washington State University under the provisions of a grant. Scientific results for the first twenty-five years of the Registries are summarized, including the 1985 publication of the analysis of the first whole body donor. Current scientific work in progress is summarized along with administrative activities for the period.

  1. Industrial Energy-Efficiency Improvement Program. Annual report to the Congress and the President 1979

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

    The industrial energy efficiency improvement program to accelerate market penetration of new and emerging industrial technologies and practices which will improve energy efficiency; encourage substitution of more plentiful domestic fuels; and enhance recovery of energy and materials from industrial waste streams is described. The role of research, development, and demonstration; technology implementation; the reporting program; and progress are covered. Specific reports from the chemicals and allied products; primary metals; petroleum and coal products; stone, clay, and glass, paper and allied products; food and kindred products; fabricated metals; transportation equipment; machinery (except electrical); textile mill products; rubber and miscellaneous plastics; electrical and electronic equipment; lumber and wood; and tobacco products are discussed. Additional data from voluntary submissions, a summary on progress in the utilization of recovered materials, and an analysis of industrial fuel mix are briefly presented. (MCW)

  2. "Annual Electric Power Industry Report (EIA-861 data file)

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

    FILES Electric power sales, revenue, and energy efficiency Form EIA-861 detailed data files Release Date: October 21, 2015 Final 2014 data Next Release date: October 15, 2016 Annual data for 2014 re-released: January 13, 2016 (Revision\Correction) The Form EIA-861 and Form EIA-861S (Short Form) data files include information such as peak load, generation, electric purchases, sales, revenues, customer counts and demand-side management programs, green pricing and net metering programs, and

  3. 2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2012 through October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2013 reporting year, an estimated 9.64 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  4. Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    6. Employment in the U.S. uranium production industry by category, 2003-14 person-years Year Exploration Mining Milling Processing Reclamation Total 2003 W W W W 117 321 2004 18...

  5. Domestic Uranium Production Report

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

    7. Employment in the U.S. uranium production industry by state, 2003-14 person-years State(s) 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 Wyoming 134 139 181 195...

  6. 2015 Domestic Uranium Production Report

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

    9. Summary production statistics of the U.S. uranium industry, 1993-2015" ,"Exploration and Development Surface ","Exploration and Development Drilling","Mine Production of Uranium ","Uranium Concentrate Production ","Uranium Concentrate Shipments ","Employment " "Year","Drilling (million feet)"," Expenditures 1 (million dollars)","(million pounds U3O8)","(million pounds

  7. Industrial advanced turbine systems: Development and demonstration. Annual report, October 1, 1996--September 30, 1997

    SciTech Connect (OSTI)

    1997-12-31

    The US DOE has initiated a program for advanced turbine systems (ATS) that will serve industrial power generation markets. The ATS will provide ultra-high efficiency, environmental superiority, and cost competitiveness. The ATS will foster (1) early market penetration that enhances the global competitiveness of US industry, (2) public health benefits resulting from reduced exhaust gas emissions of target pollutants, (3) reduced cost of power used in the energy-intensive industrial marketplace and (4) the retention and expansion of the skilled US technology base required for the design, development and maintenance of state-of-the-art advanced turbine products. The Industrial ATS Development and Demonstration program is a multi-phased effort. Solar Turbines Incorporated (Solar) has participated in Phases 1 and 2 of the program. On September 14, 1995 Solar was awarded a Cooperative Agreement for Phases 3 and 4 of the program. Phase 3 of the work is separated into two subphases: Phase 3A entails Component Design and Development Phase 3B will involve Integrated Subsystem Testing. Phase 4 will cover Host Site Testing. Forecasts call for completion of the program within budget as originally estimated. Scheduled completion is forecasted to be approximately 3 years late to original plan. This delay has been intentionally planned in order to better match program tasks to the anticipated availability of DOE funds. To ensure the timely realization of DOE/Solar program goals, the development schedule for the smaller system (Mercury 50) and enabling technologies has been maintained, and commissioning of the field test unit is scheduled for May of 2000. As of the end of the reporting period work on the program is 22.80% complete based upon milestones completed. This measurement is considered quite conservative as numerous drawings on the Mercury 50 are near release. Variance information is provided in Section 4.0-Program Management.

  8. Industry Leaders, Research Experts Gather for Second Annual DOE Solid-State Lighting Workshop

    Broader source: Energy.gov [DOE]

    Technology leaders from industry, research institutions, universities, and national laboratories gathered in San Diego, California, on February 3 and 4, 2005 to attend a workshop focused on advancing solid-state lighting (SSL) technology from the laboratory to the marketplace. Sponsored by the U.S. Department of Energy (DOE) Building Technologies Office, the workshop provided an interactive forum for shaping and prioritizing DOE's SSL research and development activities.

  9. Industry Leaders, Research Experts Gather for Fourth Annual DOE Solid-State Lighting Workshop

    Broader source: Energy.gov [DOE]

    More than 250 attendees gathered in Phoenix, Arizona, to participate in the 2007 DOE Solid-State Lighting (SSL) Program Planning Workshop on January 31-February 2, 2007. Lighting industry leaders, fixture manufacturers, researchers, academia, trade associations, lighting designers, energy efficiency organizations, and utilities joined DOE to share perspectives on the rapidly evolving SSL market. The workshop provided a forum for building partnerships and strategies to accelerate technology advances and guide market introduction of high efficiency, high-performance SSL products.

  10. file://\\fs-f1\shared\uranium\uranium.html

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

    Glossary Home > Nuclear > U.S. Uranium Reserves Estimates U.S. Uranium Reserves Estimates Data for: 2008 Report Released: July 2010 Next Release Date: 2012 Summary The U.S. Energy Information Administration (EIA) has updated its estimates of uranium reserves for year-end 2008. This represents the first revision of the estimates since 2004. The update is based on analysis of company annual reports, any additional information reported by companies at conferences and in news releases,

  11. Applications of Genome-based Science in Shaping Citrus Industries of the World (JGI Seventh Annual User Meeting, 2012: Genomics of Energy and Environment)

    ScienceCinema (OSTI)

    Gmitter Jr, Fred [University of Florida

    2013-01-15

    Fred Gmitter from the University of Florida on "Applications of Genome-based Science in Shaping the Future of the World's Citrus Industries" at the 7th Annual Genomics of Energy & Environment Meeting on March 21, 2012 in Walnut Creek, California.

  12. Applications of Genome-based Science in Shaping Citrus Industries of the World (JGI Seventh Annual User Meeting, 2012: Genomics of Energy and Environment)

    SciTech Connect (OSTI)

    Gmitter Jr, Fred [University of Florida

    2012-03-21

    Fred Gmitter from the University of Florida on "Applications of Genome-based Science in Shaping the Future of the World's Citrus Industries" at the 7th Annual Genomics of Energy & Environment Meeting on March 21, 2012 in Walnut Creek, California.

  13. Advanced coal-fueled industrial cogeneration gas turbine system. Annual report, June 1991--June 1992

    SciTech Connect (OSTI)

    LeCren, R.T.; Cowell, L.H.; Galica, M.A.; Stephenson, M.D.; When, C.S.

    1992-06-01

    This report covers the activity during the period from 2 June 1991 to 1 June 1992. The major areas of work include: the combustor sub-scale and full size testing, cleanup, coal fuel specification and processing, the Hot End Simulation rig and design of the engine parts required for use with the coal-fueled combustor island. To date Solar has demonstrated: Stable and efficient combustion burning coal-water mixtures using the Two Stage Slagging Combustor; Molten slag removal of over 97% using the slagging primary and the particulate removal impact separator; and on-site preparation of CWM is feasible. During the past year the following tasks were completed: The feasibility of on-site CWM preparation was demonstrated on the subscale TSSC. A water-cooled impactor was evaluated on the subscale TSSC; three tests were completed on the full size TSSC, the last one incorporating the PRIS; a total of 27 hours of operation on CWM at design temperature were accumulated using candle filters supplied by Refraction through Industrial Pump & Filter; a target fuel specification was established and a fuel cost model developed which can identify sensitivities of specification parameters; analyses of the effects of slag on refractory materials were conducted; and modifications continued on the Hot End Simulation Rig to allow extended test times.

  14. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  15. 2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance issues Discussion of the facility’s environmental impacts During the 2012 permit year, approximately 183 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  16. 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

    2007-12-01

    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.

  17. 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

    2006-09-29

    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.

  18. Coal industry annual 1994

    SciTech Connect (OSTI)

    1995-10-01

    This report presents data on coal consumption, distribution, coal stocks, quality, prices, coal production information, and emissions for a wide audience.

  19. U.S. Energy Information Administration | Electric Power Annual

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

    Annual

  20. 2015 Uranium Marketing Annual Report

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

    +1 Year","+1 Year" "+2 Years","+2 Years" "+3 Years","+3 Years" "+4 Years","+4 Years" "+5 Years","+5 Years" "+6 Years","+6 Years" "+7 Years","+7 Years" "+8 Years","+8 Years" "+9 ...

  1. 2015 Uranium Marketing Annual Report

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

    Feed Deliveries in 2013","Feed Deliveries in 2013" "Feed Deliveries in 2014","Feed Deliveries in 2014" "Feed Deliveries in 2015","Feed Deliveries in 2015

  2. 2015 Uranium Marketing Annual Report

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

    893,5377,5470 9562,9738,15910 3307,3868,7662 3142,2941,2551 18220,12486,5509 211,431,445 4409,2719,2541 1007,823,108

  3. 2015 Uranium Marketing Annual Report

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

    8.281,5.442,15.284,16.463 43.441,5.289,16.202,21.389 47.333,5.766,13.322,26.36 41.961,5.732,9.89,23.361 42.743,6.488,10.467,21.252 47.948,5.161,10.395,26.767 51.81,3.56,9.095,30.35...

  4. 2015 Uranium Marketing Annual Report

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

    001,6724,10741,10511,9678 10832,13584,7808,9789,16876 9728,6234,6454,12032,10723 6199,5986,5677,4603,3456 1744,2133,1666,1316,922 10199,7643,10580,6859,9063 1524,1243,186,938,826 ...

  5. 2015 Uranium Marketing Annual Report

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

    2013,2013 ,,2014,2014 ,,2015,2015 ,,2016,2016 ,,2017,2017 ,,2018,2018 ,,2019,2019 ,,2020,2020 ,,2021,2021 ,,2022,2022

  6. Title I Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    I Disposal Sites Annual Report Title I Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) More Documents & Publications Title II

  7. Title II Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    II Disposal Sites Annual Report Title II Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) More Documents & Publications Title I

  8. DOE - Office of Legacy Management -- Climax Uranium Co Grand...

    Office of Legacy Management (LM)

    LMSGRJS0809. October 2009 2015 Annual Site Inspection and Monitoring Report for Uranium ... LMSGRJS00813. November 2013. August 2015 Groundwater Sampling at the Grand Junction, ...

  9. Domestic Uranium Production Report - Energy Information Administration

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

    Domestic Uranium Production Report - Annual With Data for 2015 | Release Date: May 5, 2016 | Next Release Date: May 2017 | full report Previous domestic uranium production reports Year: 2014 2013 2012 2011 2010 2009 2008 2007 2006 2005 2004 Go Drilling Total uranium drilling was 1,518 holes covering 0.9 million feet, 13% fewer holes than in 2015. Expenditures for uranium drilling in the United States were $29 million in 2015, an increase of 2% compared with 2014. Figure 1. U.S. Uranium drilling

  10. Uranium hexafluoride handling. Proceedings

    SciTech Connect (OSTI)

    Not Available

    1991-12-31

    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.

  11. An Industrial-Based Consortium to Develop Premium Carbon Products from Coal, Annual Progress Report, October 1, 2003 through September 30, 2004

    SciTech Connect (OSTI)

    Andresen, John; Schobert, Harold; Miller, Bruce G

    2006-03-01

    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 10 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 various subcontractors on March 1, 2004.

  12. 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

    2006-03-01

    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.

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

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

    Uranium Leasing Program » Uranium Leasing Program: Program Summary Uranium Leasing Program: Program Summary Uranium Leasing Program: Program Summary The Atomic Energy Act and other legislative actions authorized the U.S. Atomic Energy Commission (AEC), predecessor agency to the DOE, to withdraw lands from the public domain and 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

  14. URANIUM COMPOSITIONS

    DOE Patents [OSTI]

    Allen, N.P.; Grogan, J.D.

    1959-05-12

    This patent relates to high purity uranium alloys characterized by improved stability to thermal cycling and low thermal neutron absorption. The high purity uranium alloy contains less than 0.1 per cent by weight in total amount of any ore or more of the elements such as aluminum, silicon, phosphorous, tin, lead, bismuth, niobium, and zinc.

  15. Table 3. Annual commercial spent fuel discharges and burnup

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

    3. Annual commercial spent fuel discharges and burnup, 1968 - June 30, 2013 Number of assemblies a Initial uranium content (MTU) Average burnup (GWDtMTU) All discharged assemblies...

  16. recycled_uranium.cdr

    Office of Legacy Management (LM)

    supply of natural uranium. The chemical reprocessing of spent nuclear fuel for uranium was very efficient, but trace quantities of impurities accompanied the uranium product. ...

  17. JACKETING URANIUM

    DOE Patents [OSTI]

    Saller, H.A.; Keeler, J.R.

    1959-07-14

    The bonding to uranium of sheathing of iron or cobalt, or nickel, or alloys thereof is described. The bonding is accomplished by electro-depositing both surfaces to be joined with a coating of silver and amalgamating or alloying the silver layer with mercury or indium. Then the silver alloy is homogenized by exerting pressure on an assembly of the uranium core and the metal jacket, reducing the area of assembly and heating the assembly to homogenize by diffusion.

  18. Biomass as Feedstock for a Bioenergy and Bioproducts Industry: The Technical Feasability of a Billion-Ton Annual Supply

    SciTech Connect (OSTI)

    Perlack, R.D.

    2005-12-15

    The U.S. Department of Energy (DOE) and the U.S. Department of Agriculture (USDA) are both strongly committed to expanding the role of biomass as an energy source. In particular, they support biomass fuels and products as a way to reduce the need for oil and gas imports; to support the growth of agriculture, forestry, and rural economies; and to foster major new domestic industries--biorefineries--making a variety of fuels, chemicals, and other products. As part of this effort, the Biomass R&D Technical Advisory Committee, a panel established by the Congress to guide the future direction of federally funded biomass R&D, envisioned a 30 percent replacement of the current U.S. petroleum consumption with biofuels by 2030. Biomass--all plant and plant-derived materials including animal manure, not just starch, sugar, oil crops already used for food and energy--has great potential to provide renewable energy for America's future. Biomass recently surpassed hydropower as the largest domestic source of renewable energy and currently provides over 3 percent of the total energy consumption in the United States. In addition to the many benefits common to renewable energy, biomass is particularly attractive because it is the only current renewable source of liquid transportation fuel. This, of course, makes it invaluable in reducing oil imports--one of our most pressing energy needs. A key question, however, is how large a role could biomass play in responding to the nation's energy demands. Assuming that economic and financial policies and advances in conversion technologies make biomass fuels and products more economically viable, could the biorefinery industry be large enough to have a significant impact on energy supply and oil imports? Any and all contributions are certainly needed, but would the biomass potential be sufficiently large to justify the necessary capital replacements in the fuels and automobile sectors? The purpose of this report is to determine whether the land resources of the United States are capable of producing a sustainable supply of biomass sufficient to displace 30 percent or more of the country's present petroleum consumption--the goal set by the Advisory Committee in their vision for biomass technologies. Accomplishing this goal would require approximately 1 billion dry tons of biomass feedstock per year.

  19. Annual Reports - SRSCRO

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

    reports Annual Reports Annual Report 2015 Annual Report 2014 Annual Report 2013 Annual Report 2012 Annual Report 2011 Annual Report 2010 Annual Report 2009 Annual Report 2008...

  20. Uranium metal reactions with hydrogen and water vapour and the reactivity of the uranium hydride produced

    SciTech Connect (OSTI)

    Godfrey, H.; Broan, C.; Goddard, D.; Hodge, N.; Woodhouse, G.; Diggle, A.; Orr, R.

    2013-07-01

    Within the nuclear industry, metallic uranium has been used as a fuel. If this metal is stored in a hydrogen rich environment then the uranium metal can react with the hydrogen to form uranium hydride which can be pyrophoric when exposed to air. The UK National Nuclear Laboratory has been carrying out a programme of research for Sellafield Limited to investigate the conditions required for the formation and persistence of uranium hydride and the reactivity of the material formed. The experimental results presented here have described new results characterising uranium hydride formed from bulk uranium at 50 and 160 C. degrees and measurements of the hydrolysis kinetics of these materials in liquid water. It has been shown that there is an increase in the proportion of alpha-uranium hydride in material formed at lower temperatures and that there is an increase in the rate of reaction with water of uranium hydride formed at lower temperatures. This may at least in part be attributable to a difference in the reaction rate between alpha and beta-uranium hydride. A striking observation is the strong dependence of the hydrolysis reaction rate on the temperature of preparation of the uranium hydride. For example, the reaction rate of uranium hydride prepared at 50 C. degrees was over ten times higher than that prepared at 160 C. degrees at 20% extent of reaction. The decrease in reaction rate with the extent of reaction also depended on the temperature of uranium hydride preparation.

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

    Energy Savers [EERE]

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

  2. Electric power annual 1994. Volume 1

    SciTech Connect (OSTI)

    1995-07-21

    The Electric Power Annual presents a summary of electric power industry statistics at national, regional, and State levels.

  3. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2013–October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Permit required groundwater monitoring data; Status of compliance activities; Noncompliance issues; and Discussion of the facility’s environmental impacts. During the 2014 permit year, approximately 238 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the downgradient monitoring wells.

  4. 2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2012–October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Noncompliance issues • Discussion of the facility’s environmental impacts. During the 2013 permit year, approximately 238 million gallons of wastewater was discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  5. Reactor Physics Methods and Preconceptual Core Design Analyses for Conversion of the Advanced Test Reactor to Low-Enriched Uranium Fuel Annual Report for Fiscal Year 2012

    SciTech Connect (OSTI)

    David W. Nigg; Sean R. Morrell

    2012-09-01

    Under the current long-term DOE policy and planning scenario, both the ATR and the ATRC will be reconfigured at an appropriate time within the next several years to operate with low-enriched uranium (LEU) fuel. This will be accomplished under the auspices of the Reduced Enrichment Research and Test Reactor (RERTR) Program, administered by the DOE National Nuclear Security Administration (NNSA). At a minimum, the internal design and composition of the fuel element plates and support structure will change, to accommodate the need for low enrichment in a manner that maintains total core excess reactivity at a suitable level for anticipated operational needs throughout each cycle while respecting all control and shutdown margin requirements and power distribution limits. The complete engineering design and optimization of LEU cores for the ATR and the ATRC will require significant multi-year efforts in the areas of fuel design, development and testing, as well as a complete re-analysis of the relevant reactor physics parameters for a core composed of LEU fuel, with possible control system modifications. Ultimately, revalidation of the computational physics parameters per applicable national and international standards against data from experimental measurements for prototypes of the new ATR and ATRC core designs will also be required for Safety Analysis Report (SAR) changes to support routine operations with LEU. This report is focused on reactor physics analyses conducted during Fiscal Year (FY) 2012 to support the initial development of several potential preconceptual fuel element designs that are suitable candidates for further study and refinement during FY-2013 and beyond. In a separate, but related, effort in the general area of computational support for ATR operations, the Idaho National Laboratory (INL) is conducting a focused multiyear effort to introduce modern high-fidelity computational reactor physics software and associated validation protocols to replace several obsolete components of the current analytical tool set used for ATR neutronics support. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF). It will also greatly facilitate the LEU conversion effort, since the upgraded computational capabilities are now at a stage where they can be, and in fact have been, used for the required physics analysis from the beginning. In this context, extensive scoping neutronics analyses were completed for six preconceptual candidate LEU fuel element designs for the ATR (and for its companion critical facility, ATRC). Of these, four exhibited neutronics performance in what is believed to be an acceptable range. However, there are currently some concerns with regard to fabricability and mechanical performance that have emerged for one of the four latter concepts. Thus three concepts have been selected for more comprehensive conceptual design analysis during the upcoming fiscal year.

  6. NARUC 127th Annual Meeting

    Broader source: Energy.gov [DOE]

    The National Association of Regulatory Utility Commissioners (NARUC) is hosting its annual meeting to set policy, share best practices, and discuss crucial industry issues.

  7. Inherently safe in situ uranium recovery.

    SciTech Connect (OSTI)

    Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

    2009-05-01

    Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

  8. Industry Partnerships

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

    Industry Partnerships

  9. Uranium in the Savannah River Site environment

    SciTech Connect (OSTI)

    Evans, A.G.; Bauer, L.R.; Haselow, J.S.; Hayes, D.W.; Martin, H.L.; McDowell, W.L.; Pickett, J.B.

    1992-12-09

    The purpose of this report is to consolidate the history of environmental uranium studies conducted by SRS and to describe the status of uranium in the environment. The report is intended to be a living document'' that will be updated periodically. This draft issue, February 1992, documents studies that occurred from 1954 to 1989. Data in this report are taken primarily from annual and semiannual environmental reports for SRS. Semiannual reports were published from 1954 through 1962. Annual reports have been published since 1963. Occasionally unpublished data are included in this report for completeness.

  10. Uranium in the Savannah River Site environment

    SciTech Connect (OSTI)

    Evans, A.G.; Bauer, L.R.; Haselow, J.S.; Hayes, D.W.; Martin, H.L.; McDowell, W.L.; Pickett, J.B.

    1992-12-09

    The purpose of this report is to consolidate the history of environmental uranium studies conducted by SRS and to describe the status of uranium in the environment. The report is intended to be a ``living document`` that will be updated periodically. This draft issue, February 1992, documents studies that occurred from 1954 to 1989. Data in this report are taken primarily from annual and semiannual environmental reports for SRS. Semiannual reports were published from 1954 through 1962. Annual reports have been published since 1963. Occasionally unpublished data are included in this report for completeness.

  11. Uranium enrichment

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    This book presents the GAO's views on the Department of Energy's (DOE) program to develop a new uranium enrichment technology, the atomic vapor laser isotope separation process (AVLIS). Views are drawn from GAO's ongoing review of AVLIS, in which the technical, program, and market issues that need to be addressed before an AVLIS plant is built are examined.

  12. Potentiometric determination of uranium in organic extracts

    SciTech Connect (OSTI)

    Bodnar, L.Z.

    1980-05-01

    The potentimetric determination of uranium in organic extracts was studied. A mixture of 30% TBP, (tributylphosphate), in carbon tetrachloride was used, with the NBL (New Brunswick Laboratory) titrimetric procedure. Results include a comparative analysis performed on organic extracts of fissium alloys vs those performed on aqueous samples of the same alloys which had been treated to remove interfering elements. Also comparative analyses were performed on sample solutions from a typical scrap recovery operation common in the uranium processing industry. A limited number of residue type materials, calciner products, and presscakes were subjected to analysis by organic extraction. The uranium extraction was not hindered by 30% TBP/CCl/sub 4/. To fully demonstrate the capabilities of the extraction technique and its compatibility with the NBL potentiometric uranium determination, a series of uranium standards was subjected to uranium extraction with 30% TBP/CCl/sub 4/. The uranium was then stripped out of the organic phase with 40 mL of H/sub 3/PO/sub 4/, 15 mL of H/sub 2/0, and 1 mL of 1M FeSO/sub 4/ solution. The uranium was then determined in the aqueous phosphoric phase by the regular NBL potentiometric method, omitting only the addition of another 40 mL of H/sub 3/PO/sub 4/. Uranium determinations ranging from approximately 20 to 150 mg of U were successfully made with the same accuracy and precision normally achieved. 8 tables. (DP)

  13. Uranium enrichment

    SciTech Connect (OSTI)

    Not Available

    1991-08-01

    This paper reports that in 1990 the Department of Energy began a two-year project to illustrate the technical and economic feasibility of a new uranium enrichment technology-the atomic vapor laser isotope separation (AVLIS) process. GAO believes that completing the AVLIS demonstration project will provide valuable information about the technical viability and cost of building an AVLIS plant and will keep future plant construction options open. However, Congress should be aware that DOE still needs to adequately demonstrate AVLIS with full-scale equipment and develop convincing cost projects. Program activities, such as the plant-licensing process, that must be completed before a plant is built, could take many years. Further, an updated and expanded uranium enrichment analysis will be needed before any decision is made about building an AVLIS plant. GAO, which has long supported legislation that would restructure DOE's uranium enrichment program as a government corporation, encourages DOE's goal of transferring AVLIS to the corporation. This could reduce the government's financial risk and help ensure that the decision to build an AVLIS plant is based on commercial concerns. DOE, however, has no alternative plans should the government corporation not be formed. Further, by curtailing a planned public access program, which would have given private firms an opportunity to learn about the technology during the demonstration project, DOE may limit its ability to transfer AVLIS to the private sector.

  14. COPPER COATED URANIUM ARTICLE

    DOE Patents [OSTI]

    Gray, A.G.

    1958-10-01

    Various techniques and methods for obtaining coppercoated uranium are given. Specifically disclosed are a group of complex uranium coatings having successive layers of nickel, copper, lead, and tin.

  15. Microsoft Word - S02459_2006Annual GW Rpt.doc

    Office of Legacy Management (LM)

    Ground Water Model-Predicted Uranium Concentrations This page intentionally left blank U.S. Department of Energy Monticello Mill Tailings Site OU III Annual Ground Water Report October 2005-April 2006 September 2006 Doc. No. S0245900 Page G-3 Table G-1. Uranium Concentration Variation: Background Locations Observations Loc 92-01 Loc 92-03 Loc 92-05 Loc MW00-01 Loc MW00-02 Date Sampled Uranium (mg/L) Uranium (mg/L) Uranium (mg/L) Uranium (mg/L) Uranium (mg/L) 11/12/1992 0.0058 0.0048 03/08/1993

  16. Annual Report | Y-12 National Security Complex

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

    About / Annual Report Annual Report View Annual Report Fiscal 2013 marked the 70th anniversary of the Y-12 National Security Complex, located in Oak Ridge, Tenn. Originally part of the Manhattan Project, Y-12 was constructed to enrich uranium for an atomic weapon to end World War II. For seven decades, Y-12 has met evolving national security needs - from separating lithium-6 for thermonuclear weapons during the Cold War to Y-12's modern missions: maintaining the safety, security and

  17. URANIUM EXTRACTION

    DOE Patents [OSTI]

    Harrington, C.D.; Opie, J.V.

    1958-07-01

    The recovery of uranium values from uranium ore such as pitchblende is described. The ore is first dissolved in nitric acid, and a water soluble nitrate is added as a salting out agent. The resulting feed solution is then contacted with diethyl ether, whereby the bulk of the uranyl nitrate and a portion of the impurities are taken up by the ether. This acid ether extract is then separated from the aqueous raffinate, and contacted with water causing back extractioa of the uranyl nitrate and impurities into the water to form a crude liquor. After separation from the ether extract, this crude liquor is heated to about 118 deg C to obtain molten uranyl nitrate hexahydratc. After being slightly cooled the uranyl nitrate hexahydrate is contacted with acid free diethyl ether whereby the bulk of the uranyl nitrate is dissolved into the ethcr to form a neutral ether solution while most of the impurities remain in the aqueous waste. After separation from the aqueous waste, the resultant ether solution is washed with about l0% of its volume of water to free it of any dissolved impurities and is then contacted with at least one half its volume of water whereby the uranyl nitrate is extracted into the water to form an aqueous product solution.

  18. PRODUCTION OF URANIUM TETRACHLORIDE

    DOE Patents [OSTI]

    Calkins, V.P.

    1958-12-16

    A process is descrlbed for the production of uranium tetrachloride by contacting uranlum values such as uranium hexafluoride, uranlum tetrafluoride, or uranium oxides with either aluminum chloride, boron chloride, or sodium alumlnum chloride under substantially anhydrous condltlons at such a temperature and pressure that the chlorldes are maintained in the molten form and until the uranium values are completely converted to uranlum tetrachloride.

  19. Microsoft Word - L15 01-22 Uranium Tranfers

    Energy Savers [EERE]

    To: Office of Nuclear Energy Department of Energy 1000 Independence Ave., SW Washington, DC 20585 From: Nan Swift Federal Affairs Manager National Taxpayers Union 108 N. Alfred Street Alexandria, VA 22314 Subject: Request for Information: Excess Uranium Management: Effects of DOE Transfers of Excess Uranium on Domestic Uranium Mining, Conversion, and Enrichment Industries To whom it may concern: On behalf of the members of the National Taxpayers Union (NTU), I write to express our concerns

  20. Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

    SciTech Connect (OSTI)

    Baalman, R.W.; Hays, I.D.

    1981-02-01

    Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications. (DLS)

  1. Domestic Uranium Production Report - Quarterly

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

    2. Number of uranium mills and plants producing uranium concentrate in the United States Uranium concentrate processing facilities End of Mills - conventional milling 1 Mills -...

  2. URANIUM DECONTAMINATION

    DOE Patents [OSTI]

    Buckingham, J.S.; Carroll, J.L.

    1959-12-22

    A process is described for reducing the extractability of ruthenium, zirconium, and niobium values into hexone contained in an aqueous nitric acid uranium-containing solution. The solution is made acid-deficient, heated to between 55 and 70 deg C, and at that temperature a water-soluble inorganic thiosulfate is added. By this, a precipitate is formed which carries the bulk of the ruthenium, and the remainder of the ruthenium as well as the zirconium and niobium are converted to a hexone-nonextractable form. The rutheniumcontaining precipitate can either be removed from the solu tion or it can be dissolved as a hexone-non-extractable compound by the addition of sodium dichromate prior to hexone extraction.

  3. Natural gas annual 1995

    SciTech Connect (OSTI)

    1996-11-01

    The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1995 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1991 to 1995 for each Census Division and each State. Annual historical data are shown at the national level.

  4. Natural gas annual 1994

    SciTech Connect (OSTI)

    1995-11-17

    The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1994 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1990 to 1994 for each Census Division and each State. Annual historical data are shown at the national level.

  5. Uranium hexafluoride bibliography

    SciTech Connect (OSTI)

    Burnham, S.L.

    1988-01-01

    This bibliography is a compilation of reports written about the transportation, handling, safety, and processing of uranium hexafluoride. An on-line literature search was executed using the DOE Energy files and the Nuclear Science Abstracts file to identify pertinent reports. The DOE Energy files contain unclassified information that is processed at the Office of Scientific and Technical Information of the US Department of Energy. The reports selected from these files were published between 1974 and 1983. Nuclear Science Abstracts contains unclassified international nuclear science and technology literature published from 1948 to 1976. In addition, scientific and technical reports published by the US Atomic Energy Commission and the US Energy Research and Development Administration, as well as those published by other agencies, universities, and industrial and research organizations, are included in the Nuclear Science Abstracts file. An alphabetical listing of the acronyms used to denote the corporate sponsors follows the bibliography.

  6. PRODUCTION OF PURIFIED URANIUM

    DOE Patents [OSTI]

    Burris, L. Jr.; Knighton, J.B.; Feder, H.M.

    1960-01-26

    A pyrometallurgical method for processing nuclear reactor fuel elements containing uranium and fission products and for reducing uranium compound; to metallic uranium is reported. If the material proccssed is essentially metallic uranium, it is dissolved in zinc, the sulution is cooled to crystallize UZn/sub 9/ , and the UZn/sub 9/ is distilled to obtain uranium free of fission products. If the material processed is a uranium compound, the sollvent is an alloy of zinc and magnesium and the remaining steps are the same.

  7. URANIUM RECOVERY PROCESS

    DOE Patents [OSTI]

    Bailes, R.H.; Long, R.S.; Olson, R.S.; Kerlinger, H.O.

    1959-02-10

    A method is described for recovering uranium values from uranium bearing phosphate solutions such as are encountered in the manufacture of phosphate fertilizers. The solution is first treated with a reducing agent to obtain all the uranium in the tetravalent state. Following this reduction, the solution is treated to co-precipitate the rcduced uranium as a fluoride, together with other insoluble fluorides, thereby accomplishing a substantially complete recovery of even trace amounts of uranium from the phosphate solution. This precipitate usually takes the form of a complex fluoride precipitate, and after appropriate pre-treatment, the uranium fluorides are leached from this precipitate and rccovered from the leach solution.

  8. Industrial Carbon Management Initiative

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

    Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Small- and medium-sized manufacturers may be eligible to receive a no-cost assessment provided by DOE Industrial Assessment Centers (IACs). Teams located at 24 universities around the country conduct the energy audits to identify opportunities to improve productivity, reduce waste, and save energy. IACs typically identify more than $130,000 in potential annual savings opportunities for

  9. Annual Energy Outlook 2015 - Appendix A

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

    3 U.S. Energy Information Administration | Annual Energy Outlook 2015 Reference case Table A6. Industrial sector key indicators and consumption Energy Information Administration ...

  10. 2014 Geothermal Resources Council Annual Meeting

    Broader source: Energy.gov [DOE]

    The Annual Meeting attracts geothermal industry stakeholders worldwide and provides opportunity to participate in presentations on geothermal research, exploration, development, and utilization.

  11. Laboratory Directed Research Development (LDRD) Annual Reports

    Broader source: Energy.gov [DOE]

    DOE’s national laboratories annual reports of long-term national missions and unique scientific and technical capabilities beyond the scope of academic and industrial institutions.

  12. Depleted uranium: A DOE management guide

    SciTech Connect (OSTI)

    1995-10-01

    The U.S. Department of Energy (DOE) has a management challenge and financial liability 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. The annual storage and maintenance cost is approximately $10 million. This report summarizes several studies undertaken by the DOE Office of Technology Development (OTD) to evaluate options for long-term depleted uranium management. Based on studies conducted to date, the most likely use of the depleted uranium is for shielding of spent nuclear fuel (SNF) or vitrified high-level waste (HLW) containers. The alternative to finding a use for the depleted uranium is disposal as a radioactive waste. Estimated disposal costs, utilizing existing technologies, range between $3.8 and $11.3 billion, depending on factors such as applicability of the Resource Conservation and Recovery Act (RCRA) and the location of the disposal site. The cost of recycling the depleted uranium in a concrete based shielding in SNF/HLW containers, although substantial, is comparable to or less than the cost of disposal. Consequently, the case can be made that if DOE invests in developing depleted uranium shielded containers instead of disposal, a long-term solution to the UF{sub 6} problem is attained at comparable or lower cost than disposal as a waste. Two concepts for depleted uranium storage casks were considered in these studies. The first is based on standard fabrication concepts previously developed for depleted uranium metal. The second converts the UF{sub 6} to an oxide aggregate that is used in concrete to make dry storage casks.

  13. Inherently Safe In-Situ Uranium Recovery - Energy Innovation Portal

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

    Industrial Technologies Industrial Technologies Advanced Materials Advanced Materials Find More Like This Return to Search Inherently Safe In-Situ Uranium Recovery Sandia National Laboratories Contact SNL About This Technology Publications: PDF Document Publication Market Sheet (1,140 KB) Technology Marketing SummaryAs uranium mining continues to grow in the United States, so does the concerns over its environmental impact. An approach that may alleviate some of these problems may be in situ

  14. 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.

    1980-06-01

    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.

  15. METHOD FOR PURIFYING URANIUM

    DOE Patents [OSTI]

    Knighton, J.B.; Feder, H.M.

    1960-04-26

    A process is given for purifying a uranium-base nuclear material. The nuclear material is dissolved in zinc or a zinc-magnesium alloy and the concentration of magnesium is increased until uranium precipitates.

  16. NICKEL COATED URANIUM ARTICLE

    DOE Patents [OSTI]

    Gray, A.G.

    1958-10-01

    Nickel coatings on uranium and various methods of obtaining such coatings are described. Specifically disclosed are such nickel or nickel alloy layers as barriers between uranium and aluminum- silicon, chromium, or copper coatings.

  17. Uranium-233 Signatures (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Search Results Conference: Uranium-233 Signatures Citation Details In-Document Search Title: Uranium-233 Signatures Authors: Worrall, Louise G [1] ; McElroy, Robert Dennis [1] ; Krichinsky, Alan M [1] ; Cleveland, Steven L [1] ; Croft, Stephen [1] + Show Author Affiliations ORNL Publication Date: 2014-01-01 OSTI Identifier: 1154847 DOE Contract Number: DE-AC05-00OR22725 Resource Type: Conference Resource Relation: Conference: Institute of Nuclear Materials Management 55th Annual

  18. Uranium accountancy in Atomic Vapor Laser Isotope Separation

    SciTech Connect (OSTI)

    Carver, R.D.

    1986-01-01

    The AVLIS program pioneers the large scale industrial application of lasers to produce low cost enriched uranium fuel for light water reactors. In the process developed at Lawrence Livermore National Laboratory, normal uranium is vaporized by an electron beam, and a precisely tuned laser beam selectively photo-ionizes the uranium-235 isotopes. These ions are moved in an electromagnetic field to be condensed on the product collector. All other uranium isotopes remain uncharged and pass through the collector section to condense as tails. Tracking the three types of uranium through the process presents special problems in accountancy. After demonstration runs, the uranium on the collector was analyzed for isotopic content by Battelle Pacific Northwest Laboratory. Their results were checked at LLNL by analysis of parallel samples. The differences in isotopic composition as reported by the two laboratories were not significant.

  19. PRODUCTION OF URANIUM TETRAFLUORIDE

    DOE Patents [OSTI]

    Shaw, W.E.; Spenceley, R.M.; Teetzel, F.M.

    1959-08-01

    A method is presented for producing uranium tetrafluoride from the gaseous hexafluoride by feeding the hexafluoride into a high temperature zone obtained by the recombination of molecularly dissociated hydrogen. The molal ratio of hydrogen to uranium hexnfluoride is preferably about 3 to 1. Uranium tetrafluoride is obtained in a finely divided, anhydrous state.

  20. Uranium Mining, Conversion, and Enrichment Industries

    Office of Environmental Management (EM)

    ... Down-blending of HEU NNSA contracts with WesDyne International for down-blending of HEU to ... Under the terms of the contract with WesDyne, DOE can use a mix of money and ...

  1. U.S. Uranium Reserves Estimates

    Gasoline and Diesel Fuel Update (EIA)

    Major U.S. Uranium Reserves

  2. URANIUM RECOVERY PROCESS

    DOE Patents [OSTI]

    Yeager, J.H.

    1958-08-12

    In the prior art processing of uranium ores, the ore is flrst digested with nitric acid and filtered, and the uranium values are then extracted tom the filtrate by contacting with an organic solvent. The insoluble residue has been processed separately in order to recover any uranium which it might contain. The improvement consists in contacting a slurry, composed of both solution and residue, with the organic solvent prior to filtration. Tbe result is that uranium values contained in the residue are extracted along with the uranium values contained th the solution in one step.

  3. URANIUM SEPARATION PROCESS

    DOE Patents [OSTI]

    Hyde, E.K.; Katzin, L.I.; Wolf, M.J.

    1959-07-14

    The separation of uranium from a mixture of uranium and thorium by organic solvent extraction from an aqueous solution is described. The uranium is separrted from an aqueous mixture of uranium and thorium nitrates 3 N in nitric acid and containing salting out agents such as ammonium nitrate, so as to bring ihe total nitrate ion concentration to a maximum of about 8 N by contacting the mixture with an immiscible aliphatic oxygen containing organic solvent such as diethyl carbinol, hexone, n-amyl acetate and the like. The uranium values may be recovered from the organic phase by back extraction with water.

  4. PROCESS OF RECOVERING URANIUM

    DOE Patents [OSTI]

    Carter, J.M.; Larson, C.E.

    1958-10-01

    A process is presented for recovering uranium values from calutron deposits. The process consists in treating such deposits to produce an oxidlzed acidic solution containing uranium together with the following imparities: Cu, Fe, Cr, Ni, Mn, Zn. The uranium is recovered from such an impurity-bearing solution by adjusting the pH of the solution to the range 1.5 to 3.0 and then treating the solution with hydrogen peroxide. This results in the precipitation of uranium peroxide which is substantially free of the metal impurities in the solution. The peroxide precipitate is then separated from the solution, washed, and calcined to produce uranium trioxide.

  5. Method for converting uranium oxides to uranium metal

    DOE Patents [OSTI]

    Duerksen, Walter K.

    1988-01-01

    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.

  6. C:\\ANNUAL\\Vol2chps.v8\\ANNUAL2.VP

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

    89 Energy Information Administration Historical Natural Gas Annual 1930 Through 2000 State Residential Commercial Industrial Vehicle Fuel Consumption (thousand cubic feet) Cost ...

  7. C:\\ANNUAL\\Vol2chps.v8\\ANNUAL2.VP

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

    44 Energy Information Administration Historical Natural Gas Annual 1930 Through 2000 33. Prices of Natural Gas Deliveries to Industrial Consumers by State, 1993-1998 (Dollars per ...

  8. About the Uranium Mine Team | Department of Energy

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

    Uranium Mine Team About the Uranium Mine Team Text coming

  9. Natural gas annual 1997

    SciTech Connect (OSTI)

    1998-10-01

    The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1997 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1993 to 1997 for each Census Division and each State. Annual historical data are shown at the national level. 27 figs., 109 tabs.

  10. Preparation of uranium compounds

    DOE Patents [OSTI]

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

    2013-02-19

    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.

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

    DOE Patents [OSTI]

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

    1995-06-06

    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.

  12. 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)

    1995-01-01

    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.

  13. Domestic Uranium Production Report

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

    1993-2014 Year Exploration and development surface drilling (million feet) Exploration and development drilling expenditures 1 (million dollars) Mine production of uranium ...

  14. Domestic Uranium Production Report

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

    1. U.S. uranium drilling activities, 2003-14 Exploration drilling Development drilling Exploration and development drilling Year Number of holes Feet (thousand) Number of holes ...

  15. METHOD OF ROLLING URANIUM

    DOE Patents [OSTI]

    Smith, C.S.

    1959-08-01

    A method is described for rolling uranium metal at relatively low temperatures and under non-oxidizing conditions. The method involves the steps of heating the uranium to 200 deg C in an oil bath, withdrawing the uranium and permitting the oil to drain so that only a thin protective coating remains and rolling the oil coated uranium at a temperature of 200 deg C to give about a 15% reduction in thickness at each pass. The operation may be repeated to accomplish about a 90% reduction without edge cracking, checking or any appreciable increase in brittleness.

  16. highly enriched uranium

    National Nuclear Security Administration (NNSA)

    and radioisotope supply capabilities of MURR and Nordion with General Atomics' selective gas extraction technology-which allows their low-enriched uranium (LEU) targets to remain...

  17. Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    or dissolving-out from mined rock, of the soluble uranium constituents by the natural action of percolating a prepared chemical solution through mounded (heaped) rock material. ...

  18. Uranium Dispersion & Dosimetry Model.

    Energy Science and Technology Software Center (OSTI)

    2002-03-22

    The Uranium Dispersion and Dosimetry (UDAD) program provides estimates of potential radiation exposure to individuals and to the general population in the vicinity of a uranium processing facility such as a uranium mine or mill. Only transport through the air is considered. Exposure results from inhalation, external irradiation from airborne and ground-deposited activity, and ingestion of foodstuffs. Individual dose commitments, population dose commitments, and environmental dose commitments are computed. The program was developed for applicationmore » to uranium mining and milling; however, it may be applied to dispersion of any other pollutant.« less

  19. Uranium Purchases Report

    Reports and Publications (EIA)

    1996-01-01

    Final issue. This report details natural and enriched uranium purchases as reported by owners and operators of commercial nuclear power plants. 1996 represents the most recent publication year.

  20. COATING URANIUM FROM CARBONYLS

    DOE Patents [OSTI]

    Gurinsky, D.H.; Storrs, S.S.

    1959-07-14

    Methods are described for making adherent corrosion resistant coatings on uranium metal. According to the invention, the uranium metal is heated in the presence of an organometallic compound such as the carbonyls of nickel, molybdenum, chromium, niobium, and tungsten at a temperature sufficient to decompose the metal carbonyl and dry plate the resultant free metal on the surface of the uranium metal body. The metal coated body is then further heated at a higher temperature to thermally diffuse the coating metal within the uranium bcdy.

  1. URANIUM RECOVERY PROCESS

    DOE Patents [OSTI]

    Kaufman, D.

    1958-04-15

    A process of recovering uranium from very low-grade ore residues is described. These low-grade uraniumcontaining hydroxide precipitates, which also contain hydrated silica and iron and aluminum hydroxides, are subjected to multiple leachings with aqueous solutions of sodium carbonate at a pH of at least 9. This leaching serves to selectively extract the uranium from the precipitate, but to leave the greater part of the silica, iron, and aluminum with the residue. The uranium is then separated from the leach liquor by the addition of an acid in sufficient amount to destroy the carbonate followed by the addition of ammonia to precipitate uranium as ammonium diuranate.

  2. U.S.Uranium Reserves

    Gasoline and Diesel Fuel Update (EIA)

    Uranium Reserves Data for: 2003 Release Date: June 2004 Next Release: Not determined Uranium Reserves Estimates The Energy Information Administration (EIA) has reported the...

  3. PROCESS FOR MAKING URANIUM HEXAFLUORIDE

    DOE Patents [OSTI]

    Rosen, R.

    1959-07-14

    A process is described for producing uranium hexafluoride by reacting uranium hexachloride with hydrogen fluoride at a temperature below about 150 deg C, under anhydrous conditions.

  4. Annual Reports

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

    Status & Schedules » Annual Planning Summaries Annual Planning Summaries Background DOE Order 451.1B, National Environmental Compliance Program, Section 4.d, requires that an annual NEPA planning summary will describe briefly: (1) the status of ongoing NEPA compliance activities, (2) any environmental assessments expected to be prepared in the next 12 months, (3) any environmental impact statements expected to be prepared in the next 24 months, and (4) the planned cost and schedule for

  5. Steel Industry Profile | Department of Energy

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

    ... billion in energy costs for heat and power.7 The industry has made significant ... Iron and Steel Institute, Annual Statistical Report 2009 3 U.S. Geological Survey, ...

  6. URANIUM SEPARATION PROCESS

    DOE Patents [OSTI]

    McVey, W.H.; Reas, W.H.

    1959-03-10

    The separation of uranium from an aqueous solution containing a water soluble uranyl salt is described. The process involves adding an alkali thiocyanate to the aqueous solution, contacting the resulting solution with methyl isobutyl ketons and separating the resulting aqueous and organic phase. The uranium is extracted in the organic phase as UO/sub 2/(SCN)/sub/.

  7. DECONTAMINATION OF URANIUM

    DOE Patents [OSTI]

    Spedding, F.H.; Butler, T.A.

    1962-05-15

    A process is given for separating fission products from uranium by extracting the former into molten aluminum. Phase isolation can be accomplished by selectively hydriding the uranium at between 200 and 300 deg C and separating the hydride powder from coarse particles of fissionproduct-containing aluminum. (AEC)

  8. 2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2009 through October 31, 2010. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Discussion of the facility’s environmental impacts During the 2010 permit year, approximately 164 million gallons of wastewater were discharged to the Cold Waste Pond. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  9. METHOD FOR PURIFYING URANIUM

    DOE Patents [OSTI]

    Kennedy, J.W.; Segre, E.G.

    1958-08-26

    A method is presented for obtaining a compound of uranium in an extremely pure state and in such a condition that it can be used in determinations of the isotopic composition of uranium. Uranium deposited in calutron receivers is removed therefrom by washing with cold nitric acid and the resulting solution, coataining uranium and trace amounts of various impurities, such as Fe, Ag, Zn, Pb, and Ni, is then subjected to various analytical manipulations to obtain an impurity-free uranium containing solution. This solution is then evaporated on a platinum disk and the residue is ignited converting it to U2/sub 3//sub 8/. The platinum disk having such a thin film of pure U/sub 2/O/sub 8/ is suitable for use with isotopic determination techaiques.

  10. URANIUM PRECIPITATION PROCESS

    DOE Patents [OSTI]

    Thunaes, A.; Brown, E.A.; Smith, H.W.; Simard, R.

    1957-12-01

    A method for the recovery of uranium from sulfuric acid solutions is described. In the present process, sulfuric acid is added to the uranium bearing solution to bring the pH to between 1 and 1.8, preferably to about 1.4, and aluminum metal is then used as a reducing agent to convert hexavalent uranium to the tetravalent state. As the reaction proceeds, the pH rises amd a selective precipitation of uranium occurs resulting in a high grade precipitate. This process is an improvement over the process using metallic iron, in that metallic aluminum reacts less readily than metallic iron with sulfuric acid, thus avoiding consumption of the reducing agent and a raising of the pH without accomplishing the desired reduction of the hexavalent uranium in the solution. Another disadvantage to the use of iron is that positive ferric ions will precipitate with negative phosphate and arsenate ions at the pH range employed.

  11. Uranium dioxide electrolysis

    DOE Patents [OSTI]

    Willit, James L.; Ackerman, John P.; Williamson, Mark A.

    2009-12-29

    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.

  12. PROCESS OF RECOVERING URANIUM

    DOE Patents [OSTI]

    Kilner, S.B.

    1959-12-29

    A method is presented for separating and recovering uranium from a complex mixure of impurities. The uranium is dissolved to produce an aqueous acidic solution including various impurities. In accordance with one method, with the uranium in the uranyl state, hydrogen cyanide is introduced into the solution to complex the impurities. Subsequently, ammonia is added to the solution to precipitate the uraniunn as ammonium diuranate away from the impurities in the solution. Alternatively, the uranium is precipitated by adding an alkaline metal hydroxide. In accordance with the second method, the uranium is reduced to the uranous state in the solution. The reduced solution is then treated with solid alkali metal cyanide sufficient to render the solution about 0.1 to 1.0 N in cyanide ions whereat cyanide complex ions of the metal impurities are produced and the uranium is simultaneously precipituted as uranous hydroxide. Alternatively, hydrogen cyanide may be added to the reduced solution and the uranium precipitated subsequently by adding ammonium hydroxide or an alkali metal hydroxide. Other refinements of the method are also disclosed.

  13. India's Worsening Uranium Shortage

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2007-01-15

    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.

  14. The Nation's Expert in All Things Uranium | Y-12 National Security Complex

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

    The Nation's Expert in ... The Nation's Expert in All Things Uranium Posted: July 22, 2013 - 3:47pm | Y-12 Report | Volume 10, Issue 1 | 2013 Y-12 was the first site in the world to electromagnetically separate uranium on an industrial scale, but that was only the beginning. Since then, the site has amassed a wealth of know-how in machining, recycling and reprocessing; securing and storing; handling and transporting; analyzing and detecting; and training others in safeguarding uranium. The

  15. Depleted uranium management alternatives

    SciTech Connect (OSTI)

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

    1994-08-01

    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.

  16. Geothermal Resources Council Annual Meeting

    Broader source: Energy.gov [DOE]

    Reno, Nevada The 2015 Geothermal Resources Council (GRC) Annual Meeting and the Geothermal Energy Association (GEA) Geothermal Energy Expo will be held in Reno, Nevada, on September 20–23. As the world’s largest annual geothermal conference and expo, this year’s event will bring together leaders in the geothermal industry; showcase the latest in geothermal research, exploration, development, and utilization; and feature workshops on important industry topics and field trips to nearby geothermal sites. Register today to reserve your spot.

  17. Uranium Processing Facility | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Gallery Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home Uranium Processing Facility Uranium Processing Facility Uranium Processing Facility Site...

  18. 2006 Annual Inspection for the

    Office of Legacy Management (LM)

    3 UMTRCA Title I Annual Report March 2014 Durango, Colorado Page 4-1 4.0 Durango, Colorado, Disposal Site 4.1 Compliance Summary The Durango, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site, inspected on May 21, 2013, was in excellent condition. Vegetation on top of the disposal cell remains healthy, and the top and side slopes remain relatively free of deep-rooted species. A gap in the retention pond fence was repaired. No additional maintenance needs or

  19. 2006 Annual Inspection for the

    Office of Legacy Management (LM)

    4 UMTRCA Title I Annual Report March 2015 Durango, Colorado Page 4-1 4.0 Durango, Colorado, Disposal Site 4.1 Compliance Summary The Durango, Colorado, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I Disposal Site, inspected on June 3, 2014, was in good condition. Vegetation on top of the disposal cell was healthy, and the top and side slopes were relatively free of deep-rooted species. Perimeter sign P1 was missing and will be replaced. One witness corner monument associated with

  20. Innovative Elution Processes for Recovering Uranium from Seawater

    SciTech Connect (OSTI)

    Wai, Chien; Tian, Guoxin; Janke, Christopher

    2014-05-29

    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.

  1. Domestic Uranium Production Report

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

    3. U.S. uranium concentrate production, shipments, and sales, 2003-14 Activity at U.S. mills and In-Situ-Leach plants 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014...

  2. PURIFICATION OF URANIUM FUELS

    DOE Patents [OSTI]

    Niedrach, L.W.; Glamm, A.C.

    1959-09-01

    An electrolytic process of refining or decontaminating uranium is presented. The impure uranium is made the anode of an electrolytic cell. The molten salt electrolyte of this cell comprises a uranium halide such as UF/sub 4/ or UCl/sub 3/ and an alkaline earth metal halide such as CaCl/sub 2/, BaF/sub 2/, or BaCl/sub 2/. The cathode of the cell is a metal such as Mn, Cr, Co, Fe, or Ni which forms a low melting eutectic with U. The cell is operated at a temperature below the melting point of U. In operation the electrodeposited uranium becomes alloyed with the metal of the cathode, and the low melting alloy thus formed drips from the cathode.

  3. U.S. Energy Information Administration | Annual Coal Distribution...

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

    ...... 1 U.S. Energy Information Administration | Annual Coal ... Coal Origin State Transportation Mode Electric Power Sector Coke Plants Industrial Plants ...

  4. ANODIC TREATMENT OF URANIUM

    DOE Patents [OSTI]

    Kolodney, M.

    1959-02-01

    A method is presented for effecting eloctrolytic dissolution of a metallic uranium article at a uniform rate. The uranium is made the anode in an aqueous phosphoric acid solution containing nitrate ions furnished by either ammonium nitrate, lithium nitrate, sodium nitrate, or potassium nitrate. A stainless steel cathode is employed and electrolysls carried out at a current density of about 0.1 to 1 ampere per square inch.

  5. URANIUM EXTRACTION PROCESS

    DOE Patents [OSTI]

    Baldwin, W.H.; Higgins, C.E.

    1958-12-16

    A process is described for recovering uranium values from acidic aqueous solutions containing hexavalent uranium by contacting the solution with an organic solution comprised of a substantially water-immiscible organlc diluent and an organic phosphate to extract the uranlum values into the organic phase. Carbon tetrachloride and a petroleum hydrocarbon fraction, such as kerosene, are sultable diluents to be used in combination with organlc phosphates such as dibutyl butylphosphonate, trlbutyl phosphine oxide, and tributyl phosphate.

  6. 2015 Domestic Uranium Production Report

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

    7. Employment in the U.S. uranium production industry by state, 2003-15" "person-years" "State(s)",2003,2004,2005,2006,2007,2008,2009,2010,2011,2012,2013,2014,2015 "Wyoming",134,139,181,195,245,301,308,348,424,512,531,416,343 "Colorado and Texas",48,140,269,263,557,696,340,292,331,248,198,105,79 "Nebraska and New Mexico",92,102,123,160,149,160,159,134,127,"W","W","W","W" "Arizona, Utah, and

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

    DOE Patents [OSTI]

    Kreuzmann, Alvin B. (Cincinnati, OH)

    1983-01-01

    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.

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

    DOE Patents [OSTI]

    Kreuzmann, A.B.

    1982-10-27

    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.

  9. Uranium exploration of the Colorado Plateau: interim staff report

    SciTech Connect (OSTI)

    Not Available

    1980-10-01

    This report is an issue of the original draft copy of the Interim Staff Report on Uranium Exploration on the Colorado Plateau, dated June 1951. The original draft copy was only recently located and is being published at this time because of the interest in the contained historical content. The table of contents of this report lists: history of uranium mining; geology; proposed program for the geologic investigations section; general activities of industry and government; and future exploration of sedimentary uranium deposits and anticipated results. Under the proposed program section are: future of the copper-uranium deposits as a source of uranium; uraniferous asphaltite deposits; and commission exploration and future possibilities. The section on general activities of industry and government includes: exploratory and development drilling; field investigations and mapping; early geologic investigations and investigations by the US geological survey; and geophysical exploration. Tables are also presented on: uranium production by districts; US Geological survey drilling statistics; Colorado Exploration Branch drilling statistics; summary of drilling projects; and comparative yearly core-drill statistics on the Colorado Plateau.

  10. EUCI 16th Annual Integrated Resource Planning

    Broader source: Energy.gov [DOE]

    EUCI is hosting an annual conference about integrated resource planning to showcase best practices that properly recognize and address changes in the grid. The program features leading utility, power resource planning professional and related industry experts addressing these key issues.

  11. Nuclear Fuel Facts: Uranium | Department of Energy

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

    Facts: Uranium Nuclear Fuel Facts: Uranium Nuclear Fuel Facts: Uranium Uranium is a silvery-white metallic chemical element in the periodic table, with atomic number 92. It is assigned the chemical symbol U. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Uranium has the highest atomic weight (19 kg m) of all naturally occurring elements. Uranium occurs naturally in low concentrations in soil, rock and water, and is commercially extracted from uranium-bearing

  12. Renewable energy annual 1995

    SciTech Connect (OSTI)

    1995-12-01

    The Renewable Energy Annual 1995 is the first in an expected series of annual reports the Energy Information Administration (EIA) intends to publish to provide a comprehensive assessment of renewable energy. This report presents the following information on the history, status, and prospects of renewable energy data: estimates of renewable resources; characterizations of renewable energy technologies; descriptions of industry infrastructures for individual technologies; evaluations of current market status; and assessments of near-term prospects for market growth. An international section is included, as well as two feature articles that discuss issues of importance for renewable energy as a whole. The report also contains a number of technical appendices and a glossary. The renewable energy sources included are biomass (wood), municipal solid waste, biomass-derived liquid fuels, geothermal, wind, and solar and photovoltaic.

  13. Petroleum marketing annual 1994

    SciTech Connect (OSTI)

    1995-08-24

    The Petroleum Marketing Annual (PMA) provides information and statistical data on a variety of crude oils and refined petroleum products. The publication presents statistics on crude oil costs and refined petroleum products sales for use by industry, government, private sector analysis, educational institutions, and consumers. Data on crude oil include the domestic first purchase price, the fob and landed cost of imported crude oil, and the refiners` acquisition cost of crude oil. Refined petroleum product sales data include motor gasoline, distillates, residuals, aviation fuels, kerosene, and propane. The Petroleum Marketing Division, Office of Oil and Gas, Energy Information Administration ensures the accuracy, quality, and confidentiality of the published data in the Petroleum Marketing Annual. For this production, all estimates have been recalculated since their earlier publication in the Petroleum Marketing Monthly (PMM). These calculations made use of additional data and corrections that were received after the PMM publication date.

  14. Electric power annual 1992

    SciTech Connect (OSTI)

    Not Available

    1994-01-06

    The Electric Power Annual presents a summary of electric utility statistics at national, regional and State levels. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts and the general public with historical data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. ``The US Electric Power Industry at a Glance`` section presents a profile of the electric power industry ownership and performance, and a review of key statistics for the year. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; retail sales; revenue; financial statistics; environmental statistics; electric power transactions; demand-side management; and nonutility power producers. In addition, the appendices provide supplemental data on major disturbances and unusual occurrences in US electricity power systems. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter. Monetary values in this publication are expressed in nominal terms.

  15. Influence of uranium hydride oxidation on uranium metal behaviour

    SciTech Connect (OSTI)

    Patel, N.; Hambley, D.; Clarke, S.A.; Simpson, K.

    2013-07-01

    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)

  16. Process for electrolytically preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A.

    1989-01-01

    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.

  17. Annual Report

    Energy Savers [EERE]

    1 2011 Annual Report to the Oak Ridge Community Annual Report to the Oak Ridge Community DOE/ORO/2399 Progress Cleanup P Progress Cleanup P 2 This report was produced by URS | CH2M Oak Ridge LLC, DOE's Environmental Management contractor for the Oak Ridge Reservation. About the Cover After recontouring and revegetation, the P1 Pond at East Tennessee Technology Park is flourishing. The contaminated pond was drained, recontoured, and restocked with fish that would not disturb the pond sediment. 1

  18. DOE/IG Annual Performance Report FY 2008, Annual Performance...

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

    DOEIG Annual Performance Report FY 2008, Annual Performance Plan FY 2009 DOEIG Annual Performance Report FY 2008, Annual Performance Plan FY 2009 DOEIG Annual Performance Report ...

  19. PRODUCTION OF URANIUM HEXAFLUORIDE

    DOE Patents [OSTI]

    Fowler, R.D.

    1957-08-27

    A process for the production of uranium hexafluoride from the oxides of uranium is reported. In accordance with the method, the higher oxides of uranium may be reduced to uranium dioxide (UO/sub 2/), the latter converted into uranium tetrafluoride by reaction with hydrogen fluoride, and the UF/sub 4/ converted to UF/sub 6/ by reaction with a fluorinating agent, such as CoF/sub 3/. The UO/sub 3/ or U/sub 3/O/sub 8/ is placed in a reac tion chamber in a copper boat or tray enclosed in a copper oven, and heated to 500 to 650 deg C while hydrogen gas is passed through the oven. After nitrogen gas is used to sweep out the hydrogen and the water vapor formed, and while continuing to inaintain the temperature between 400 deg C and 600 deg C, anhydrous hydrogen fluoride is passed through. After completion of the conversion of UO/sub 2/ to UF/sub 4/ the temperature of the reaction chamber is lowered to about 400 deg C or less, the UF/sub 4/ is mixed with the requisite quantity of CoF/sub 3/, and after evacuating the chamber, the mixture is heated to 300 to 400 deg C, and the resulting UF/sub 6/ is led off and delivered to a condenser.

  20. Uranium-titanium-niobium alloy

    DOE Patents [OSTI]

    Ludtka, Gail M.; Ludtka, Gerard M.

    1990-01-01

    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.

  1. METHOD OF RECOVERING URANIUM COMPOUNDS

    DOE Patents [OSTI]

    Poirier, R.H.

    1957-10-29

    S>The recovery of uranium compounds which have been adsorbed on anion exchange resins is discussed. The uranium and thorium-containing residues from monazite processed by alkali hydroxide are separated from solution, and leached with an alkali metal carbonate solution, whereby the uranium and thorium hydrorides are dissolved. The carbonate solution is then passed over an anion exchange resin causing the uranium to be adsorbed while the thorium remains in solution. The uranium may be recovered by contacting the uranium-holding resin with an aqueous ammonium carbonate solution whereby the uranium values are eluted from the resin and then heating the eluate whereby carbon dioxide and ammonia are given off, the pH value of the solution is lowered, and the uranium is precipitated.

  2. METHOD OF SINTERING URANIUM DIOXIDE

    DOE Patents [OSTI]

    Henderson, C.M.; Stavrolakis, J.A.

    1963-04-30

    This patent relates to a method of sintering uranium dioxide. Uranium dioxide bodies are heated to above 1200 nif- C in hydrogen, sintered in steam, and then cooled in hydrogen. (AEC)

  3. Petroleum Marketing Annual Archives

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

    Petrolem Reports Petroleum Marketing Annual Archives The Petroleum Marketing Annual was discontinued in 2010. Choose the year from the archive Petroleum Marketing Annual you wish...

  4. Renewable energy annual 1996

    SciTech Connect (OSTI)

    1997-03-01

    This report presents summary data on renewable energy consumption, the status of each of the primary renewable technologies, a profile of each of the associated industries, an analysis of topical issues related to renewable energy, and information on renewable energy projects worldwide. It is the second in a series of annual reports on renewable energy. The renewable energy resources included in the report are biomass (wood and ethanol); municipal solid waste, including waste-to-energy and landfill gas; geothermal; wind; and solar energy, including solar thermal and photovoltaic. The report also includes various appendices and a glossary.

  5. PROCESS FOR RECOVERING URANIUM

    DOE Patents [OSTI]

    MacWood, G.E.; Wilder, C.D.; Altman, D.

    1959-03-24

    A process is described for recovering uranium from deposits on stainless steel liner surfaces of calutrons. The deposit is removed from the stainless steel surface by washing with aqueous nitric acid. The solution obtained containing uranium, chromium, nickels copper, and iron is treated with excess of ammonium hydroxide to precipitatc the uranium, irons and chromium and convert thc nickel and copper to soluble ammonia complexions. The precipitated material is removed, dried, and treated with carbon tetrachloride at an elevated temperature of about 500 to 600 deg C to form a vapor mixture of UCl/sub 4/, UCl/sub 5/, FeCl/ sub 3/, and CrCl/sub 4/. The UCl/sub 4/ is separated from this vapor mixture by selective fractional condensation at a temprrature of about 300 to400 deg C.

  6. EXTRACTION OF URANIUM

    DOE Patents [OSTI]

    Kesler, R.D.; Rabb, D.D.

    1959-07-28

    An improved process is presented for recovering uranium from a carnotite ore. In the improved process U/sub 2/O/sub 5/ is added to the comminuted ore along with the usual amount of NaCl prior to roasting. The amount of U/sub 2/O/ sub 5/ is dependent on the amount of free calcium oxide and the uranium in the ore. Specifically, the desirable amount of U/sub 2/O/sub 5/ is 3.2% for each 1% of CaO, and 5 to 6% for each 1% of uranium. The mixture is roasted at about 1560 deg C for about 30 min and then leached with a 3 to 9% aqueous solution of sodium carbonate.

  7. Process for recovering uranium

    DOE Patents [OSTI]

    MacWood, G. E.; Wilder, C. D.; Altman, D.

    1959-03-24

    A process useful in recovering uranium from deposits on stainless steel liner surfaces of calutrons is presented. The deposit is removed from the stainless steel surface by washing with aqueous nitric acid. The solution obtained containing uranium, chromium, nickel, copper, and iron is treated with an excess of ammonium hydroxide to precipitnte the uranium, iron, and chromium and convert the nickel and copper to soluble ammonio complexions. The precipitated material is removed, dried and treated with carbon tetrachloride at an elevated temperature of about 500 to 600 deg C to form a vapor mixture of UCl/ sub 4/, UCl/sub 5/, FeCl/sub 3/, and CrCl/sub 4/. The UCl/sub 4/ is separated from this vapor mixture by selective fractional condensation at a temperature of about 500 to 400 deg C.

  8. Uranium immobilization and nuclear waste

    SciTech Connect (OSTI)

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

    1982-02-01

    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.

  9. PROCESS OF PREPARING URANIUM CARBIDE

    DOE Patents [OSTI]

    Miller, W.E.; Stethers, H.L.; Johnson, T.R.

    1964-03-24

    A process of preparing uranium monocarbide is de scribed. Uranium metal is dissolved in cadmium, zinc, cadmium-- zinc, or magnesium-- zinc alloy and a small quantity of alkali metal is added. Addition of stoichiometric amounts of carbon at 500 to 820 deg C then precipitates uranium monocarbide. (AEC)

  10. Uranium Transport Modeling

    SciTech Connect (OSTI)

    Bostick, William D.

    2008-01-15

    Uranium contamination is prevalent at many of the U.S. DOE facilities and at several civilian sites that have supported the nuclear fuel cycle. The potential off-site mobility of uranium depends on the partitioning of uranium between aqueous and solid (soil and sediment) phases. Hexavalent U (as uranyl, UO{sub 2}{sup 2+}) is relatively mobile, forming strong complexes with ubiquitous carbonate ion which renders it appreciably soluble even under mild reducing conditions. In the presence of carbonate, partition of uranyl to ferri-hydrate and select other mineral phases is usually maximum in the near-neutral pH range {approx} 5-8. The surface complexation reaction of uranyl with iron-containing minerals has been used as one means to model subsurface migration, used in conjunction with information on the site water chemistry and hydrology. Partitioning of uranium is often studied by short-term batch 'equilibrium' or long-term soil column testing ; MCLinc has performed both of these methodologies, with selection of method depending upon the requirements of the client or regulatory authority. Speciation of uranium in soil may be determined directly by instrumental techniques (e.g., x-ray photoelectron spectroscopy, XPS; x-ray diffraction, XRD; etc.) or by inference drawn from operational estimates. Often, the technique of choice for evaluating low-level radionuclide partitioning in soils and sediments is the sequential extraction approach. This methodology applies operationally-defined chemical treatments to selectively dissolve specific classes of macro-scale soil or sediment components. These methods recognize that total soil metal inventory is of limited use in understanding bioavailability or metal mobility, and that it is useful to estimate the amount of metal present in different solid-phase forms. Despite some drawbacks, the sequential extraction method can provide a valuable tool to distinguish among trace element fractions of different solubility related to mineral phases. Four case studies are presented: Water and Soil Characterization, Subsurface Stabilization of Uranium and other Toxic Metals, Reductive Precipitation (in situ bioremediation) of Uranium, and Physical Transport of Particle-bound Uranium by Erosion.

  11. TREATMENT OF URANIUM SURFACES

    DOE Patents [OSTI]

    Slunder, C.J.

    1959-02-01

    An improved process is presented for prcparation of uranium surfaces prior to electroplating. The surfacc of the uranium to be electroplated is anodized in a bath comprising a solution of approximately 20 to 602 by weight of phosphoric acid which contains about 20 cc per liter of concentrated hydrochloric acid. Anodization is carried out for approximately 20 minutes at a current density of about 0.5 amperes per square inch at a temperature of about 35 to 45 C. The oxidic film produced by anodization is removed by dipping in strong nitric acid, followed by rinsing with water just prior to electroplating.

  12. Corrosion-resistant uranium

    DOE Patents [OSTI]

    Hovis, Jr., Victor M.; Pullen, William C.; Kollie, Thomas G.; Bell, Richard T.

    1983-01-01

    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.

  13. METHOD OF ELECTROPOLISHING URANIUM

    DOE Patents [OSTI]

    Walker, D.E.; Noland, R.A.

    1959-07-14

    A method of electropolishing the surface of uranium articles is presented. The process of this invention is carried out by immersing the uranium anticle into an electrolyte which contains from 35 to 65% by volume sulfuric acid, 1 to 20% by volume glycerine and 25 to 50% by volume of water. The article is made the anode in the cell and polished by electrolyzing at a voltage of from 10 to 15 volts. Discontinuing the electrolysis by intermittently withdrawing the anode from the electrolyte and removing any polarized film formed therein results in an especially bright surface.

  14. PREPARATION OF URANIUM TRIOXIDE

    DOE Patents [OSTI]

    Buckingham, J.S.

    1959-09-01

    The production of uranium trioxide from aqueous solutions of uranyl nitrate is discussed. The uranium trioxide is produced by adding sulfur or a sulfur-containing compound, such as thiourea, sulfamic acid, sulfuric acid, and ammonium sulfate, to the uranyl solution in an amount of about 0.5% by weight of the uranyl nitrate hexahydrate, evaporating the solution to dryness, and calcining the dry residue. The trioxide obtained by this method furnished a dioxide with a considerably higher reactivity with hydrogen fluoride than a trioxide prepared without the sulfur additive.

  15. PROCESS OF RECOVERING URANIUM

    DOE Patents [OSTI]

    Price, T.D.; Jeung, N.M.

    1958-06-17

    An improved precipitation method is described for the recovery of uranium from aqueous solutions. After removal of all but small amounts of Ni or Cu, and after complexing any iron present, the uranium is separated as the peroxide by adding H/sub 2/O/sub 2/. The improvement lies in the fact that the addition of H/sub 2/O/sub 2/ and consequent precipitation are carried out at a temperature below the freezing; point of the solution, so that minute crystals of solvent are present as seed crystals for the precipitation.

  16. Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    5. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status at end of the year, 2011-15 In-Situ-Leach plant owner In-Situ-Leach plant name County, state (existing and planned locations) Production capacity (pounds U3O8 per year) Operating status at end of the year 2011 2012 2013 2014 2015 AUC LLC Reno Creek Campbell, Wyoming 2,000,000 - - Developing Developing Partially Permitted and Licensed Azarga Uranium Corp Dewey Burdock Project Fall River and Custer, South

  17. Corrosion-resistant uranium

    DOE Patents [OSTI]

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

    1981-10-21

    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.

  18. Industrial Buildings

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

    Industrial Industrial Manufacturing Buildings Industrialmanufacturing buildings are not considered commercial, but are covered by the Manufacturing Energy Consumption Survey...

  19. Recent developments: Industry briefs

    SciTech Connect (OSTI)

    1990-04-01

    Recent nuclear industry briefs are presented. These briefs include: Soviet Union to build Iran nuclear plant; Dension announces cuts in Elliot Lake production; Soviet environmental study delays Rostov startup; Cogema closes two mines; Namibian sanctions lifted by USA and Canada; US Energy and Kennecott restructors joint venture; Australians reelect Hawke; China to buy Soviet nuclear plant; Olympic Dam`s first sale of concentrates to USA; Uranevz buys one-third of Cogema`s Rabbit Lake operations; East and West Germany forming joint nuclear law; and Nova Scotia extends uranium exploration plan.

  20. Uranium Mill Tailings Remedial Action Project. 1995 Environmental Report

    SciTech Connect (OSTI)

    1996-06-01

    In accordance with U.S. Department of Energy (DOE) Order 23 1. 1, Environment, Safety and Health Reporting, the DOE prepares an annual report to document the activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring program. This monitoring must comply with appropriate laws, regulations, and standards, and it must identify apparent and meaningful trends in monitoring results. The results of all monitoring activities must be communicated to the public. The UMTRA Project has prepared annual environmental reports to the public since 1989.

  1. Uranium Lease Tracts Location Map | Department of Energy

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

    Uranium Lease Tracts Location Map Uranium Lease Tracts Location Map Uranium Lease Tracts Location Map PDF icon Uranium Lease Tracts Location Map More Documents & Publications ...

  2. Colorado Industrial Energy Challenge | Department of Energy

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

    State and Utility Engagement Activities » Colorado Industrial Energy Challenge Colorado Industrial Energy Challenge Colorado The U.S. Department of Energy's (DOE's) Advanced Manufacturing Office (AMO; formerly the Industrial Technologies Program) has developed multiple resources and a Best Practices suite of tools to help industrial manufacturers reduce their energy intensity. AMO adopted the Energy Policy Act of 2005 objective of reducing industrial energy intensity 2.5% annually over the next

  3. High loading uranium fuel plate

    DOE Patents [OSTI]

    Wiencek, Thomas C.; Domagala, Robert F.; Thresh, Henry R.

    1990-01-01

    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.

  4. Annual Training Plan Template

    Broader source: Energy.gov [DOE]

    The Annual Training Plan Template is used by an organization's training POC to draft their organization's annual training plan.

  5. STRIPPING OF URANIUM FROM ORGANIC EXTRACTANTS

    DOE Patents [OSTI]

    Crouse, D.J. Jr.

    1962-09-01

    A liquid-liquid extraction method is given for recovering uranium values from uranium-containing solutions. Uranium is removed from a uranium-containing organic solution by contacting said organic solution with an aqueous ammonium carbonate solution substantially saturated in uranium values. A uranium- containing precipitate is thereby formed which is separated from the organic and aqueous phases. Uranium values are recovered from this separated precipitate. (AE C)

  6. Report on the Effect the Low Enriched Uranium Delivered Under the Highly Enriched Uranium Agreement Between the Government of the United States and the Government of the Russian Federation has on the

    Energy Savers [EERE]

    Report on the Effect the Low Enriched Uranium Delivered Under the Highly Enriched Uranium Agreement Between the Government of the United States of America and the Government of the Russian Federation has on the Domestic Uranium Mining, Conversion, and Enrichment Industries and the Operation of the Gaseous Diffusion Plant 2008 Information Date: December 31, 2008 1 Introduction The Agreement Between the Government of the United States of America and the Government of the Russian Federation

  7. URANIUM RECOVERY PROCESS

    DOE Patents [OSTI]

    Hyman, H.H.; Dreher, J.L.

    1959-07-01

    The recovery of uranium from the acidic aqueous metal waste solutions resulting from the bismuth phosphate carrier precipitation of plutonium from solutions of neutron irradiated uranium is described. The waste solutions consist of phosphoric acid, sulfuric acid, and uranium as a uranyl salt, together with salts of the fission products normally associated with neutron irradiated uranium. Generally, the process of the invention involves the partial neutralization of the waste solution with sodium hydroxide, followed by conversion of the solution to a pH 11 by mixing therewith sufficient sodium carbonate. The resultant carbonate-complexed waste is contacted with a titanated silica gel and the adsorbent separated from the aqueous medium. The aqueous solution is then mixed with sufficient acetic acid to bring the pH of the aqueous medium to between 4 and 5, whereby sodium uranyl acetate is precipitated. The precipitate is dissolved in nitric acid and the resulting solution preferably provided with salting out agents. Uranyl nitrate is recovered from the solution by extraction with an ether such as diethyl ether.

  8. Uranium Reduction by Clostridia

    SciTech Connect (OSTI)

    Francis, A.J.; Dodge, Cleveland J.; Gillow, Jeffrey B.

    2006-04-05

    The FRC groundwater and sediment contain significant concentrations of U and Tc and are dominated by low pH, and high nitrate and Al concentrations where dissimilatory metal reducing bacterial activity may be limited. The presence of Clostridia in Area 3 at the FRC site has been confirmed and their ability to reduce uranium under site conditions will be determined. Although the phenomenon of uranium reduction by Clostridia has been firmly established, the molecular mechanisms underlying such a reaction are not very clear. The authors are exploring the hypothesis that U(VI) reduction occurs through hydrogenases and other enzymes (Matin and Francis). Fundamental knowledge of metal reduction using Clostridia will allow us to exploit naturally occurring processes to attenuate radionuclide and metal contaminants in situ in the subsurface. The outline for this report are as follows: (1) Growth of Clostridium sp. under normal culture conditions; (2) Fate of metals and radionuclides in the presence of Clostridia; (3) Bioreduction of uranium associated with nitrate, citrate, and lepidocrocite; and (4) Utilization of Clostridium sp. for immobilization of uranium at the FRC Area 3 site.

  9. C:\\ANNUAL\\Vol2chps.v8\\ANNUAL2.VP

    Gasoline and Diesel Fuel Update (EIA)

    8 Energy Information Administration Historical Natural Gas Annual 1930 Through 2000 31. Average Price of Natural Gas Delivered to U.S. Industrial Consumers by State, 1967-1992 ...

  10. Method of preparation of uranium nitride

    DOE Patents [OSTI]

    Kiplinger, Jaqueline Loetsch; Thomson, Robert Kenneth James

    2013-07-09

    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.

  11. Status of Uranium Atomic Vapor Laser Isotope Separation Program

    SciTech Connect (OSTI)

    Chen, Hao-Lin; Feinberg, R.M.

    1993-06-01

    This report discusses demonstrations of plant-scale hardware embodying AVLIS technology which were completed in 1992. These demonstrations, designed to provide key economic and technical bases for plant deployment, produced significant quantities of low enriched uranium which could be used for civilian power reactor fuel. We are working with industry to address the integration of AVLIS into the fuel cycle. To prepare for deployment, a conceptual design and cost estimate for a uranium enrichment plant were also completed. The U-AVLIS technology is ready for commercialization.

  12. Annual Report

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

    09 THROUGH 09/30/2010 The following Annual Freedom of Information Act report covers the Period 10/01/2009, through 09/30/2010, as required by 5 U.S.C. 552. I. BASIC INFORMATION REGARDING REPORT 1. Kevin T. Hagerty, Director Office of Information Resources, MA-90 U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 202-586-5955 Alexander Morris, FOIA Officer Sheila Jeter, FOIA/Privacy Act Specialist FOIA Office, MA-90 Office of Information Resources U.S. Department of Energy

  13. Method of preparing uranium nitride or uranium carbonitride bodies

    DOE Patents [OSTI]

    Wilhelm, Harley A.; McClusky, James K.

    1976-04-27

    Sintered uranium nitride or uranium carbonitride bodies having a controlled final carbon-to-uranium ratio are prepared, in an essentially continuous process, from U.sub.3 O.sub.8 and carbon by varying the weight ratio of carbon to U.sub.3 O.sub.8 in the feed mixture, which is compressed into a green body and sintered in a continuous heating process under various controlled atmospheric conditions to prepare the sintered bodies.

  14. Survey of lands held for uranium exploration, development, and production in fourteen western states in the six month period ending June 30, 1979

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    The statistics set forth for the period covered by this report are based on data gathered from records available to the public. These data were derived from public county records of mining claim locations, from the public reports of state and Federal land offices, from commercial reporting services, and from annual reports to stockholders of land companies. Accordingly, if any fee land has been acquired in a private transaction which has not been entered into a public record or report, that land will not be accounted for in this report. The figures for the acreage controlled at the beginning of the calendar year are those that were published for that date in the publication entitled Statistical Data of the Uranium Industry GJO-100(78).

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

    SciTech Connect (OSTI)

    Not Available

    1993-12-31

    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.

  16. Method for fabricating uranium foils and uranium alloy foils

    DOE Patents [OSTI]

    Hofman, Gerard L.; Meyer, Mitchell K.; Knighton, Gaven C.; Clark, Curtis R.

    2006-09-05

    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. Disposition of Uranium Oxide From Conversion of Depleted Uranium Hexafluoride

    Broader source: Energy.gov [DOE]

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

  18. METHOD OF PRODUCING URANIUM

    DOE Patents [OSTI]

    Foster, L.S.; Magel, T.T.

    1958-05-13

    A modified process is described for the production of uranium metal by means of a bomb reduction of UF/sub 4/. Difficulty is sometimes experienced in obtaining complete separation of the uranium from the slag when the process is carried out on a snnall scale, i.e., for the production of 10 grams of U or less. Complete separation may be obtained by incorporating in the reaction mixture a quantity of MnCl/sub 2/, so that this compound is reduced along with the UF/sub 4/ . As a result a U--Mn alloy is formed which has a melting point lower than that of pure U, and consequently the metal remains molten for a longer period allowing more complete separation from the slag.

  19. ELECTROLYSIS OF THORIUM AND URANIUM

    DOE Patents [OSTI]

    Hansen, W.N.

    1960-09-01

    An electrolytic method is given for obtaining pure thorium, uranium, and thorium-uranium alloys. The electrolytic cell comprises a cathode composed of a metal selected from the class consisting of zinc, cadmium, tin, lead, antimony, and bismuth, an anode composed of at least one of the metals selected from the group consisting of thorium and uranium in an impure state, and an electrolyte composed of a fused salt containing at least one of the salts of the metals selected from the class consisting of thorium, uranium. zinc, cadmium, tin, lead, antimony, and bismuth. Electrolysis of the fused salt while the cathode is maintained in the molten condition deposits thorium, uranium, or thorium-uranium alloys in pure form in the molten cathode which thereafter may be separated from the molten cathode product by distillation.

  20. PROCESS FOR PRODUCING URANIUM TETRAFLUORIDE

    DOE Patents [OSTI]

    Harvey, B.G.

    1954-09-14

    >This patent relates to improvements in the method for producing uranium tetrafluoride by treating an aqueous solutlon of a uranyl salt at an elevated temperature with a reducing agent effective in acld solutlon in the presence of hydrofluoric acid. Uranium tetrafluoride produced this way frequentiy contains impurities in the raw material serving as the source of uranium. Uranium tetrafluoride much less contaminated with impurities than when prepared by the above method can be prepared from materials containing such impurities by first adding a small proportion of reducing agent so as to cause a small fraction, for example 1 to 5% of the uranium tetrafluoride to be precipitated, rejecting such precipitate, and then precipitating and recovering the remainder of the uranium tetrafluoride.

  1. METHOD OF DISSOLVING URANIUM METAL

    DOE Patents [OSTI]

    Slotin, L.A.

    1958-02-18

    This patent relates to an economicai means of dissolving metallic uranium. It has been found that the addition of a small amount of perchloric acid to the concentrated nitric acid in which the uranium is being dissolved greatly shortens the time necessary for dissolution of the metal. Thus the use of about 1 or 2 percent of perchioric acid based on the weight of the nitric acid used, reduces the time of dissolution of uranium by a factor of about 100.

  2. PROCESS FOR PREPARING URANIUM METAL

    DOE Patents [OSTI]

    Prescott, C.H. Jr.; Reynolds, F.L.

    1959-01-13

    A process is presented for producing oxygen-free uranium metal comprising contacting iodine vapor with crude uranium in a reaction zone maintained at 400 to 800 C to produce a vaporous mixture of UI/sub 4/ and iodine. Also disposed within the maction zone is a tungsten filament which is heated to about 1600 C. The UI/sub 4/, upon contacting the hot filament, is decomposed to molten uranium substantially free of oxygen.

  3. 2014 Domestic Uranium Production Report

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

    Domestic Uranium Production Report 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 2011 2012 2013 2014 2015 AUC LLC Reno Creek Campbell, Wyoming 2,000,000 - - Developing Developing Partially Permitted and Licensed Azarga Uranium Corp Dewey Burdock Project Fall River and Custer, South Dakota 1,000,000 Undeveloped Developing Developing Partially Permitted And Licensed Partially Permitted And Licensed Cameco Crow Butte Operation Dawes, Nebraska

  4. VANE Uranium One JV | Open Energy Information

    Open Energy Info (EERE)

    VANE Uranium One JV Jump to: navigation, search Name: VANE-Uranium One JV Place: London, England, United Kingdom Zip: EC4V 6DX Product: JV between VANE Minerals Plc & Uranium One....

  5. The strategy on rehabilitation of the former uranium facilities at the 'Pridneprovsky chemical plant' in Ukraine

    SciTech Connect (OSTI)

    Voitsekhovich, O.; Lavrova, T. [Ukrainian Hydrometeorological Institute, Kiev (Ukraine); Skalskiy, A.S. [Institute of Geological Sciences of Ac.of Sc., Kiev (Ukraine); Ryazantsev, V.F. [State Nuclear Regulatory Committee of Ukraine, 9/11 Arsenalna str., Kyiv-11, 01011 (Ukraine)

    2007-07-01

    This paper describes current status of the former Uranium Facilities at the Pridneprovsky Chemical Plant in Ukraine, which are currently under development of action plan for its territory rehabilitation. The monitoring data carried out during recent several years show its impact to the Environment and gives a basis for justification of the number of measures aiming to reduce radiological and ecological risks of the Uranium tailings situated at the territory of PChP. The monitoring data and strategy for its remediation are considered in the presentation. Uranium mining has been intensively conducted in Ukraine since the end of the 40-s. Most of the uranium deposits have been explored in the Dnieper river basin, while some smaller deposits can be found within the basins of the Southern Bug and Severskiy Donets rivers. There also several large Uranium Milling facilities were in operation since the end of the 40-s till 1991, when due to disintegration of the former Soviet Union system the own uranium production has been significantly declined. The Milling Plant and Uranium extraction Facilities in ZhevtiVody is still in operation with UkrAtomprom Industrial Consortium. Therefore rehabilitation programme for all Uranium facilities in this site are in duty of the East Mining Combine and the Consortium. The most difficult case is to provide rehabilitation Action Plan for Uranium tailings and number of other facilities situated in Dnieprodzerzhinsk town and which were in operation by the former State Industrial Enterprise Pridneprovskiy Chemical Plant (PChP). In past PChP was one of the largest Uranium Milling facilities of the Former Soviet Union and has been in operation since 1948 till 1991. During Soviet time the Uranium extraction at this legacy site has been carried out using the ore raw products delivered also from Central Asia, Germany and Checz Republic. After extraction the uranium residue has been putting to the nearest landscape depressions at the vicinity of the Milling facilities. This plant is being in the sanitation stage since 1991 with the 9 Uranium tailings dumps at its territory, containing about 42 million tonnes of Uranium Residues. There were no engineering barriers created at most of the tailings. After fulfilment of the tailing dumps capacity their surfaces usually were covering by the local soils, debris and other industrial wastes. (authors)

  6. Highly Enriched Uranium Materials Facility

    National Nuclear Security Administration (NNSA)

    Appropriations Subcommittee, is shown some of the technology in the Highly Enriched Uranium Materials Facility by Warehousing and Transportation Operations Manager Byron...

  7. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    or dissolving-out from mined rock, of the soluble uranium constituents by the natural action of percolating a prepared chemical solution through mounded (heaped) rock material. ...

  8. ELECTROLYTIC PRODUCTION OF URANIUM TETRAFLUORIDE

    DOE Patents [OSTI]

    Lofthouse, E.

    1954-08-31

    This patent relates to electrolytic methods for the production of uranium tetrafluoride. According to the present invention a process for the production of uranium tetrafluoride comprises submitting to electrolysis an aqueous solution of uranyl fluoride containing free hydrofluoric acid. Advantageously the aqueous solution of uranyl fluoride is obtained by dissolving uranium hexafluoride in water. On electrolysis, the uranyl ions are reduced to uranous tons at the cathode and immediately combine with the fluoride ions in solution to form the insoluble uranium tetrafluoride which is precipitated.

  9. SEPARATION OF THORIUM FROM URANIUM

    DOE Patents [OSTI]

    Bane, R.W.

    1959-09-01

    A description is given for the separation of thorium from uranium by forming an aqueous acidic solution containing ionic species of thorium, uranyl uranium, and hydroxylamine, flowing the solution through a column containing the phenol-formaldehyde type cation exchange resin to selectively adsorb substantially all the thorium values and a portion of the uranium values, flowing a dilute solution of hydrochloric acid through the column to desorb the uranium values, and then flowing a dilute aqueous acidic solution containing an ion, such as bisulfate, which has a complexing effect upon thortum through the column to desorb substantially all of the thorium.

  10. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... Vegetation encroachment continues on the top and side slopes of the disposal cell. Encroachment is a natural process operating at this location and will be allowed to continue in ...

  11. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... with the Long-Term Surveillance Plan (LTSP), the site is divided into four inspection areas (referred to as "transects" in the LTSP) to ensure a thorough and efficient inspection. ...

  12. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... Inspection Areas In accordance with the LTSP, the site is divided into four inspection areas (referred to as "transects" in the LTSP) to ensure a thorough and efficient inspection. ...

  13. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... Markers 5 and 5A replaced markers 4 and 4A. 16.4.2 Inspection Areas In accordance with the LTSP, the site is divided into three areas to ensure a thorough and efficient inspection. ...

  14. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... with the Long-Term Surveillance Plan (LTSP), the site is divided into five inspection areas (referred to as "transects" in the LTSP) to ensure a thorough and efficient inspection. ...

  15. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... monuments and signs will remain at their current locations. 18.4.2 Inspection Areas The site is divided into three inspection areas to ensure a thorough and efficient inspection. ...

  16. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    substantially compared to previous years due to above-average precipitation for the year. ... Groundwater monitoring is required every 3 years. The next monitoring event will be in ...

  17. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... property owner, erected a solar-powered electric fence ... Ur-Energy Inc., the adjacent landowner, will use these ... However, the well network does not provide sufficient data ...

  18. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... Report U.S. Department of Energy Tuba City, Arizona March ... a water treatment plant; a solar water-heating system; a ... This accounts for the data gaps in Figures 19-2 through ...

  19. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    to comply with the requirements of Title 10 Code of ... to the railroad tracks and several nearby natural gas wells. ... for erosion, changes in land use, or other phenomena ...

  20. 2015 Annual Site Inspection and Monitoring Report for Uranium...

    Office of Legacy Management (LM)

    ... Boundary monument BM-3 was not found and was apparently covered with soil. All of the other monuments were undisturbed and in good condition. Wind erosion has exposed the concrete ...

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

    SciTech Connect (OSTI)

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

    2010-08-01

    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.

  2. Annual Reports | Department of Energy

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

    Annual Reports Annual Reports Note: Some of the following documents are in PDF and will require Adobe Reader for viewing. Freedom of Information Act Annual Reports Annual Report for 2015 Annual Report for 2014 Annual Report for 2013 Annual Report for 2012 Annual Report for 2011 Annual Report for 2010 Annual Report for 2009 Annual Report for 2008 (pdf) Annual Report for 2007 (pdf) Annual Report for 2006 (pdf) Annual Report for 2005 (pdf) Annual Report for 2004 (pdf) Annual Report for 2003 (pdf)

  3. 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.

  4. Industrial Assessment Centers (IACs) | Department of Energy

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

    Technical Assistance » Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Small- and medium-sized manufacturers may be eligible to receive a no-cost assessment provided by DOE Industrial Assessment Centers (IACs). Teams located at 24 universities around the country conduct the energy audits to identify opportunities to improve productivity, reduce waste, and save energy. IACs typically identify more than $130,000 in potential annual

  5. PROCESS OF PRODUCING REFRACTORY URANIUM OXIDE ARTICLES

    DOE Patents [OSTI]

    Hamilton, N.E.

    1957-12-01

    A method is presented for fabricating uranium oxide into a shaped refractory article by introducing a uranium halide fluxing reagent into the uranium oxide, and then mixing and compressing the materials into a shaped composite mass. The shaped mass of uranium oxide and uranium halide is then fired at an elevated temperature so as to form a refractory sintered article. It was found in the present invention that the introduction of a uraninm halide fluxing agent afforded a fluxing action with the uranium oxide particles and that excellent cohesion between these oxide particles was obtained. Approximately 90% of uranium dioxide and 10% of uranium tetrafluoride represent a preferred composition.

  6. Highly Enriched Uranium Materials Facility | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home Highly Enriched Uranium Materials Facility Highly Enriched Uranium Materials Facility Congressmen tour Y-12...

  7. Final Uranium Leasing Program Programmatic Environmental Impact...

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

    for DOE's Uranium Leasing Program, under which DOE administers tracts of land in western Colorado for exploration, development, and the extraction of uranium and vanadium ores. ...

  8. Nuclear radiation cleanup and uranium prospecting (Patent) |...

    Office of Scientific and Technical Information (OSTI)

    Nuclear radiation cleanup and uranium prospecting Citation Details In-Document Search Title: Nuclear radiation cleanup and uranium prospecting Apparatus, systems, and methods for...

  9. Nuclear radiation cleanup and uranium prospecting (Patent) |...

    Office of Scientific and Technical Information (OSTI)

    Nuclear radiation cleanup and uranium prospecting Citation Details In-Document Search Title: Nuclear radiation cleanup and uranium prospecting You are accessing a document from...

  10. Calculating Atomic Number Densities for Uranium

    Energy Science and Technology Software Center (OSTI)

    1993-01-01

    Provides method to calculate atomic number densities of selected uranium compounds and hydrogenous moderators for use in nuclear criticality safety analyses at gaseous diffusion uranium enrichment facilities.

  11. Uranium Resources Inc URI | Open Energy Information

    Open Energy Info (EERE)

    exploring, developing and mining uranium properties using the in situ recovery (ISR) or solution mining process. References: Uranium Resources, Inc. (URI)1 This article...

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

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

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

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

    DOE Patents [OSTI]

    Rothman, Alan B.; Graczyk, Donald G.; Essling, Alice M.; Horwitz, E. Philip

    2001-01-01

    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.

  14. "Annual Coal Report

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

    Annual Coal Report Data Released: January 20, 2015 Data for: 2013 Re-Release Date: April 23, 2015 (CORRECTION) Annual Coal Report 2013 CorrectionUpdate April 23, 2015 The Annual ...

  15. Paducah Site 1997 annual environmental report

    SciTech Connect (OSTI)

    1998-12-01

    The Paducah Gaseous Diffusion Plant, located in McCracken County, Kentucky, has been producing enriched uranium since 1952. In July 1993, the US Department of Energy (DOE) leased the production areas of the site to the US Enrichment Corporation (USEC). A subsidiary of Lockheed Martin Corporation, Lockheed Martin Utility Services, manages the leased facilities for USEC. The DOE maintains responsibility for the environmental restoration, waste management, and depleted uranium hexafluoride cylinder program activities at the plant through its management contractor. The purpose of this document is to summarize calendar year 1997 environmental monitoring activities for DOE activities at the Paducah Site managed by Lockheed Martin Energy Systems. The DOE requires all of its facilities to conduct and document such activities annually. This report does not include USEC environmental activities.

  16. Paducah site annual environmental for 1996

    SciTech Connect (OSTI)

    Belcher, G.

    1997-12-01

    The Paducah Gaseous Diffusion Plant, located in McCracken County, Kentucky, has been producing enriched uranium since 1952. In July 1993, the US Department of Energy (DOE) leased the production areas of the site to the United States Enrichment Corporation (USEC). A subsidiary of Lockheed Martin Corporation, Lockheed Martin Utility Services, manages the leased facilities for USEC. The DOE maintains responsibility for the environmental restoration, waste management, and depleted uranium hexafluoride cylinder program activities at the plant through its management contractor, Lockheed Martin Energy Systems. The purpose of this document is to summarize calendar year 1996 environmental monitoring activities for DOE activities at the Paducah Site. The DOE requires all of its facilities to conduct and document such activities annually. This report does not include USEC environmental activities.

  17. Petroleum supply annual 1995: Volume 1

    SciTech Connect (OSTI)

    1996-05-01

    The {ital Petroleum Supply Annual} contains information on supply and disposition of crude oil and petroleum products. It reflects data collected from the petroleum industry during 1995 through monthly surveys, and it is divided into 2 volumes. This volume contains three sections: summary statistics, detailed statistics, and selected refinery statistics, each with final annual data. (The other volume contains final statistics for each month and replaces data previously published in the {ital Petroleum Supply Monthly}).

  18. Annual energy review 1994

    SciTech Connect (OSTI)

    1995-07-01

    This 13th edition presents the Energy Information Administration`s historical energy statistics. For most series, statistics are given for every year from 1949 through 1994; thus, this report is well-suited to long-term trend analyses. It covers all major energy activities, including consumption, production, trade, stocks, and prices for all major energy commodities, including fossil fuels and electricity. Statistics on renewable energy sources are also included: this year, for the first time, usage of renewables by other consumers as well as by electric utilities is included. Also new is a two-part, comprehensive presentation of data on petroleum products supplied by sector for 1949 through 1994. Data from electric utilities and nonutilities are integrated as ``electric power industry`` data; nonutility power gross generation are presented for the first time. One section presents international statistics (for more detail see EIA`s International Energy Annual).

  19. Petroleum marketing annual 1993

    SciTech Connect (OSTI)

    Not Available

    1995-01-01

    The Petroleum Marketing Annual (PMA) contains statistical data on a variety of crude oils and refined petroleum products. The publication provides statistics on crude oil costs and refined petroleum products sales for use by industry, government, private sector analysts, educational institutions, and consumers. Data on crude oil include the domestic first purchase price, the free-on-board (f.o.b.) and landed cost of imported crude oil, and the refiners acquisition cost of crude oil. Sales data for motor gasoline, distillates, residuals, aviation fuels, kerosene, and propane are presented. For this publication, all estimates have been recalculated since their earlier publication in the Petroleum Marketing Monthly (PMM). These calculations made use of additional data and corrections that were received after the PMM publication dates.

  20. Petroleum Marketing Annual 2009

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

    Petroleum Marketing Annual 2009 Released: August 6, 2010 Next Release Date: Discontinued find annual data in Petroleum Marketing Monthly Monthly price and volume statistics on...

  1. Petroleum Marketing Annual

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

    PDF 1.2MB . Front Matter . Petroleum Marketing Annual Cover Page, Preface, and Table of Contents PDF . Highlights . Petroleum Marketing Annual Highlights PDF . . Summary Statistics ...

  2. Petroleum Marketing Annual

    Gasoline and Diesel Fuel Update (EIA)

    PDF 2.9MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights . Petroleum Marketing Annual Highlights PDF . . ...

  3. Petroleum Marketing Annual 1997

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

    PDF 1.2MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights . Petroleum Marketing Annual Highlights PDF . . ...

  4. Annual Coal Distribution Report

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

    Annual Coal Distribution Report Release Date: April 16, 2015 | Next Release Date: March 2016 | full report | RevisionCorrection Revision to the Annual Coal Distribution Report ...

  5. ELECTRODEPOSITION OF NICKEL ON URANIUM

    DOE Patents [OSTI]

    Gray, A.G.

    1958-08-26

    A method is described for preparing uranium objects prior to nickel electroplating. The process consiats in treating the surface of the uranium with molten ferric chloride hexahydrate, at a slightiy elevated temperature. This treatment etches the metal surface providing a structure suitable for the application of adherent electrodeposits and at the same time plates the surface with a thin protective film of iron.

  6. SOLVENT EXTRACTION OF URANIUM VALUES

    DOE Patents [OSTI]

    Feder, H.M.; Ader, M.; Ross, L.E.

    1959-02-01

    A process is presented for extracting uranium salt from aqueous acidic solutions by organic solvent extraction. It consists in contacting the uranium bearing solution with a water immiscible dialkylacetamide having at least 8 carbon atoms in the molecule. Mentioned as a preferred extractant is dibutylacetamide. The organic solvent is usually used with a diluent such as kerosene or CCl/sub 4/.

  7. PLUTONIUM-URANIUM-TITANIUM ALLOYS

    DOE Patents [OSTI]

    Coffinberry, A.S.

    1959-07-28

    A plutonium-uranium alloy suitable for use as the fuel element in a fast breeder reactor is described. The alloy contains from 15 to 60 at.% titanium with the remainder uranium and plutonium in a specific ratio, thereby limiting the undesirable zeta phase and rendering the alloy relatively resistant to corrosion and giving it the essential characteristic of good mechanical workability.

  8. Petroleum supply annual 1994. Volume 1

    SciTech Connect (OSTI)

    1995-05-22

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1994 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1994, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Below is a description of each section in Volume 1 of the PSA.

  9. Petroleum supply annual 1993. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1993 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1993, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Below is a description of each section in Volume 1 of the PSA.

  10. Petroleum supply annual, 1997. Volume 1

    SciTech Connect (OSTI)

    1998-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 48 tabs.

  11. Petroleum supply annual 1998: Volume 1

    SciTech Connect (OSTI)

    1999-06-01

    The ``Petroleum Supply Annual`` (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1998, and replaces data previously published in the PSA. The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 59 tabs.

  12. METHOD OF ELECTROPLATING ON URANIUM

    DOE Patents [OSTI]

    Rebol, E.W.; Wehrmann, R.F.

    1959-04-28

    This patent relates to a preparation of metallic uranium surfaces for receiving coatings, particularly in order to secure adherent electroplated coatings upon uranium metal. In accordance with the invention the uranium surface is pretreated by degreasing in trichloroethylene, followed by immersion in 25 to 50% nitric acid for several minutes, and then rinsed with running water, prior to pickling in trichloroacetic acid. The last treatment is best accomplished by making the uranium the anode in an aqueous solution of 50 per cent by weight trichloroacetic acid until work-distorted crystals or oxide present on the metal surface have been removed and the basic crystalline structure of the base metal has been exposed. Following these initial steps the metallic uranium is rinsed in dilute nitric acid and then electroplated with nickel. Adnerent firmly-bonded coatings of nickel are obtained.

  13. ANNUAL REPORT FY2010 I N D U S T R I A L S A N D I A N A T I

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

    ... Annual Report * 2010 Industry Partner R&D Focus Key ... science technology, manufacturing technologies ... research & engineering Energy efficiency, renewable energy, ...

  14. Uranium Mill Tailings Remedial Action Project 1993 Environmental Report

    SciTech Connect (OSTI)

    Not Available

    1994-10-01

    This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

  15. PREPARATION OF URANIUM-ALUMINUM ALLOYS

    DOE Patents [OSTI]

    Moore, R.H.

    1962-09-01

    A process is given for preparing uranium--aluminum alloys from a solution of uranium halide in an about equimolar molten alkali metal halide-- aluminum halide mixture and excess aluminum. The uranium halide is reduced and the uranium is alloyed with the excess aluminum. The alloy and salt are separated from each other. (AEC)

  16. Process for removing carbon from uranium

    DOE Patents [OSTI]

    Powell, George L.; Holcombe, Jr., Cressie E.

    1976-01-01

    Carbon contamination is removed from uranium and uranium alloys by heating in inert atmosphere to 700.degree.-1900.degree.C in effective contact with yttrium to cause carbon in the uranium to react with the yttrium. The yttrium is either in direct contact with the contaminated uranium or in indirect contact by means of an intermediate transport medium.

  17. Uranium Downblending and Disposition Project Technology Readiness

    Energy Savers [EERE]

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

  18. 2008 Annual Report

    SciTech Connect (OSTI)

    2008-01-01

    This annual report includes: a brief overview of Western; FY 2008 operational highlights; and financial data.

  19. NERSC Annual Reports

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

    Annual Reports NERSC Annual Reports Sort by: Default | Name 2014cover.jpg NERSC Annual Report 2014 Download Image: 2014cover.jpg | jpg | 202 KB Download File: 2014NERSCAnnualReport.pdf | pdf | 6.1 MB 2013-Annual-Report-cover.png NERSC Annual Report 2013 Download Image: 2013-Annual-Report-cover.png | png | 645 KB Download File: annrep2013.pdf | pdf | 6.7 MB 2012-Cover.png NERSC Annual Report 2012 Download Image: 2012-Cover.png | png | 420 KB Download File: annrep12.pdf | pdf | 38 MB

  20. ELUTION OF URANIUM FROM RESIN

    DOE Patents [OSTI]

    McLEan, D.C.

    1959-03-10

    A method is described for eluting uranium from anion exchange resins so as to decrease vanadium and iron contamination and permit recycle of the major portion of the eluats after recovery of the uranium. Diminution of vanadium and iron contamination of the major portion of the uranium is accomplished by treating the anion exchange resin, which is saturated with uranium complex by adsorption from a sulfuric acid leach liquor from an ore bearing uranium, vanadium and iron, with one column volume of eluant prepared by passing chlorine into ammonium hydroxide until the chloride content is about 1 N and the pH is about 1. The resin is then eluted with 8 to 9 column volumes of 0.9 N ammonium chloride--0.1 N hydrochloric acid solution. The eluants are collected separately and treated with ammonia to precipitate ammonium diuranate which is filtered therefrom. The uranium salt from the first eluant is contaminated with the major portion of ths vanadium and iron and is reworked, while the uranium recovered from the second eluant is relatively free of the undesirable vanadium and irons. The filtrate from the first eluant portion is discarded. The filtrate from the second eluant portion may be recycled after adding hydrochloric acid to increase the chloride ion concentration and adjust the pH to about 1.

  1. Annual energy review 1997

    SciTech Connect (OSTI)

    1998-07-01

    The Annual Energy Review (AER) is a historical data report that tells many stories. It describes, in numbers, the changes that have occurred in US energy markets since the midpoint of the 20th century. In many cases, those markets differ vastly from those of a half-century ago. By studying the graphs and data tables presented in this report, readers can learn about past energy supply and usage in the United States and gain an understanding of the issues in energy and the environment now before use. While most of this year`s report content is similar to last year`s, there are some noteworthy developments. Table 1.1 has been restructured into more summarized groupings -- fossil fuels, nuclear electric power, and renewable energy -- to aid analysts in their examination of the basic trends in those broad categories. Readers` attention is also directed to the electricity section, where considerable reformatting of the tables and graphs has been carried out to help clarify past and recent trends in the electric power industry as it enters a period of radical restructuring. Table 9.1, which summarizes US nuclear generating units, has been redeveloped to cover the entire history of the industry in this country and to provide categories relevant in assessing the future of the industry, such as the numbers of ordered generating units that have been canceled and those that were built and later shut down. In general, the AER emphasizes domestic energy statistics. Sections 1 through 10 and Section 12 are devoted mostly to US data; Section 11 reports on international statistics and world totals. 140 figs., 141 tabs.

  2. Annual energy review 2003

    SciTech Connect (OSTI)

    Seiferlein, Katherin E.

    2004-09-30

    The Annual Energy Review 2003 is a statistical history of energy activities in the United States in modern times. Data are presented for all major forms of energy by production (extraction of energy from the earth, water, and other parts of the environment), consumption by end-user sector, trade with other nations, storage changes, and pricing. Much of the data provided covers the fossil fuels—coal, petroleum, and natural gas. Fossil fuels are nature’s batteries; they have stored the sun’s energy over millennia past. It is primarily that captured energy that we are drawing on today to fuel the activities of the modern economy. Data in this report measure the extraordinary expansion of our use of fossil fuels from 29 quadrillion British thermal units (Btu) in 1949 to 84 quadrillion Btu in 2003. In recent years, fossil fuels accounted for 86 percent of all energy consumed in the United States. This report also records the development of an entirely new energy industry—the nuclear electric power industry. The industry got its start in this country in 1957 when the Shippingport, Pennsylvania, nuclear electric power plant came on line. Since that time, the industry has grown to account for 20 percent of our electrical output and 8 percent of all energy used in the country. Renewable energy is a third major category of energy reported in this volume. Unlike fossil fuels, which are finite in supply, renewable energy is essentially inexhaustible because it can be replenished. Types of energy covered in the renewable category include conventional hydroelectric power, which is power derived from falling water; wood; waste; alcohol fuels; geothermal; solar; and wind. Together, these forms of energy accounted for about 6 percent of all U.S. energy consumption in recent years.

  3. URANIUM RECOVERY FROM NUCLEAR FUEL

    DOE Patents [OSTI]

    Vogel, R.C.; Rodger, W.A.

    1962-04-24

    A process of recovering uranium from a UF/sub 4/-NaFZrF/sub 4/ mixture by spraying the molten mixture at about 200 deg C in nitrogen of super- atmospheric pressure into droplets not larger than 100 microns, and contacting the molten droplets with fluorine at about 200 deg C for 0.01 to 10 seconds in a container the walls of which have a temperature below the melting point of the mixture is described. Uranium hexafluoride is formed and volatilized and the uranium-free salt is solidified. (AEC)

  4. SEPARATION OF URANIUM FROM THORIUM

    DOE Patents [OSTI]

    Hellman, N.N.

    1959-07-01

    A process is presented for separating uranium from thorium wherein the ratio of thorium to uranium is between 100 to 10,000. According to the invention the thoriumuranium mixture is dissolved in nitric acid, and the solution is prepared so as to obtain the desired concentration within a critical range of from 4 to 8 N with regard to the total nitrate due to thorium nitrate, with or without nitric acid or any nitrate salting out agent. The solution is then contacted with an ether, such as diethyl ether, whereby uranium is extracted into ihe organic phase while thorium remains in the aqueous phase.

  5. Excess Uranium Inventory Management Plan | Department of Energy

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

    Excess Uranium Inventory Management Plan Excess Uranium Inventory Management Plan The 2013 Excess Uranium Inventory Management Plan describes a framework for the effective...

  6. Highly Enriched Uranium Materials Facility | Y-12 National Security...

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

    Highly Enriched Uranium ... Highly Enriched Uranium Materials Facility HEUMF The Highly Enriched Uranium Materials Facility is our nation's central repository for highly enriched...

  7. FLUX COMPOSITION AND METHOD FOR TREATING URANIUM-CONTAINING METAL

    DOE Patents [OSTI]

    Foote, F.

    1958-08-26

    A flux composition is preseated for use with molten uranium and uranium alloys. It consists of about 60% calcium fluoride, 30% calcium chloride and 10% uranium tetrafluoride.

  8. Uranium Processing Facility | Y-12 National Security Complex

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

    Y-12 Uranium Processing Facility Uranium Processing Facility UPF will be a state-of-the-art, consolidated facility for enriched uranium operations including assembly,...

  9. Annual Review | netl.doe.gov

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

    ON-SITE RESEARCH PUBLICATIONS Annual Reviews FY13 Annual Review FY12 Annual Review FY11 Annual Review...

  10. URANIUM PURIFICATION PROCESS

    DOE Patents [OSTI]

    Ruhoff, J.R.; Winters, C.E.

    1957-11-12

    A process is described for the purification of uranyl nitrate by an extraction process. A solution is formed consisting of uranyl nitrate, together with the associated impurities arising from the HNO/sub 3/ leaching of the ore, in an organic solvent such as ether. If this were back extracted with water to remove the impurities, large quantities of uranyl nitrate will also be extracted and lost. To prevent this, the impure organic solution is extracted with small amounts of saturated aqueous solutions of uranyl nitrate thereby effectively accomplishing the removal of impurities while not allowing any further extraction of the uranyl nitrate from the organic solvent. After the impurities have been removed, the uranium values are extracted with large quantities of water.

  11. Annual Performance Report FY 2005 Annual Performance Plan FY 2006 |

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

    Department of Energy 5 Annual Performance Plan FY 2006 Annual Performance Report FY 2005 Annual Performance Plan FY 2006 Annual Performance Report FY 2005 Annual Performance Plan FY 2006 PDF icon Annual Performance Report FY 2005 Annual Performance Plan FY 2006 More Documents & Publications U.S. Department of Energy 2006 Annual Report FTCP Annual Plan - Fiscal Year 2005 FY 2008 E-Government Act Report

  12. DOE and MEEA Host Fourth Annual SSL Market Introduction Workshop

    Broader source: Energy.gov [DOE]

    More than 300 lighting industry leaders gathered in Chicago July 13–15, 2009, for the fourth annual Solid-State Lighting (SSL) Market Introduction Workshop, hosted by the U.S. Department of Energy (DOE) and the Midwest Energy Efficiency Alliance (MEEA). This annual workshop provides a focal point for government, industry, energy efficiency organizations, utilities, municipalities, designers, specifiers, retailers, distributors, and others to share updates and insights on the successful market introduction of high-quality, energy-efficient SSL solutions.

  13. NREL: Sustainable NREL - 2015 Energy Systems Integration Facility Annual

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

    Report Calls to Industry: Bring Us Your Challenges 2015 Energy Systems Integration Facility Annual Report Calls to Industry: Bring Us Your Challenges April 6, 2016 The 2015 Energy Systems Integration Facility Annual Report is now available for download. The Energy Systems Integration Facility (ESIF) is the nation's premier facility for research, development, and demonstration of the components and strategies needed to optimize our entire energy system. It was established in 2013 by the U.S.

  14. Y-12 and uranium history

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

    did happen six days after he was given the assignment. The history of uranium at Y-12 began with that decision, which will be commemorated on September 19, 2012, at...

  15. Domestic Uranium Production Report - Quarterly

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

    1. Total production of uranium concentrate in the United States, 1996 - 3rd quarter 2015 pounds U3O8 Calendar-year quarter 1st quarter 2nd quarter 3rd quarter 4th quarter...

  16. Laser induced phosphorescence uranium analysis

    DOE Patents [OSTI]

    Bushaw, B.A.

    1983-06-10

    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.

  17. MELTING AND PURIFICATION OF URANIUM

    DOE Patents [OSTI]

    Spedding, F.H.; Gray, C.F.

    1958-09-16

    A process is described for treating uranium ingots having inner metal portions and an outer oxide skin. The method consists in partially supporting such an ingot on the surface of a grid or pierced plate. A sufficient weight of uranium is provided so that when the mass becomes molten, the oxide skin bursts at the unsupported portions of its bottom surface, allowing molten urantum to flow through the burst skin and into a container provided below.

  18. SURFACE TREATMENT OF METALLIC URANIUM

    DOE Patents [OSTI]

    Gray, A.G.; Schweikher, E.W.

    1958-05-27

    The treatment of metallic uranium to provide a surface to which adherent electroplates can be applied is described. Metallic uranium is subjected to an etchant treatment in aqueous concentrated hydrochloric acid, and the etched metal is then treated to dissolve the resulting black oxide and/or chloride film without destroying the etched metal surface. The oxide or chloride removal is effected by means of moderately concentrated nitric acid in 3 to 20 seconds.

  19. LIQUID METAL COMPOSITIONS CONTAINING URANIUM

    DOE Patents [OSTI]

    Teitel, R.J.

    1959-04-21

    Liquid metal compositions containing a solid uranium compound dispersed therein is described. Uranium combines with tin to form the intermetallic compound USn/sub 3/. It has been found that this compound may be incorporated into a liquid bath containing bismuth and lead-bismuth components, if a relatively small percentage of tin is also included in the bath. The composition has a low thermal neutron cross section which makes it suitable for use in a liquid metal fueled nuclear reactor.

  20. Laser induced phosphorescence uranium analysis

    DOE Patents [OSTI]

    Bushaw, Bruce A.

    1986-01-01

    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.

  1. 2015 Domestic Uranium Production Report

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

    7 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 Capacity (short tons of ore per day) 2011 2012 2013 2014 2015 Anfield Resources Shootaring Canyon Uranium Mill Garfield, Utah 750 Standby Standby Standby Standby Standby EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating- Processing Alternate Feed Operating- Processing Alternate Feed Operating- Processing Alternate Feed Energy Fuels Wyoming Inc Sheep Mountain

  2. Petroleum supply annual 1993. Volume 2

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    This publication contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1993 through annual and monthly surveys. This second volume contains final statistics for each month of 1993.

  3. Petroleum supply annual 1994, Volume 2

    SciTech Connect (OSTI)

    1995-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1994 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1994, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary.

  4. The Office of Environmental Management Uranium Enrichment D&D | Department

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

    of Energy Uranium Enrichment D&D The Office of Environmental Management Uranium Enrichment D&D PDF icon Microsoft Word - B996F741.doc More Documents & Publications Microsoft Word - PSRP Updates 6-25-10_v2 Above on the left is K-25, at Oak Ridge before and after the 844,000 sq-ft demolition. In addition, on the right: K Cooling Tower at Savannah River Site demolition. Deactivation & Decommissioning (D&D) Program Map 2013 Annual Workforce Analysis and Staffing Plan Report -

  5. Beneficial Uses of Depleted Uranium

    SciTech Connect (OSTI)

    Brown, C.; Croff, A.G.; Haire, M. J.

    1997-08-01

    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.

  6. PROCESS FOR PRODUCING URANIUM HEXAFLUORIDE

    DOE Patents [OSTI]

    Fowler, R.D.

    1957-10-22

    A process for the production of uranium hexafluoride from the oxides of uranium is reported. In accordance with the method the higher oxides of uranium may be reduced to uranium dioxide (UO/sub 2/), the latter converted into uranium tetrafluoride by reaction with hydrogen fluoride, and the UF/sub 4/ convented to UF/sub 6/ by reaction with a fluorinating agent. The UO/sub 3/ or U/sub 3/O/sub 8/ is placed in a reaction chamber in a copper boat or tray enclosed in a copper oven, and heated to 500 to 650 deg C while hydrogen gas is passed through the oven. The oven is then swept clean of hydrogen and the water vapor formed by means of nitrogen and then while continuing to maintain the temperature between 400 and 600 deg C, anhydrous hydrogen fluoride is passed through. After completion of the conversion to uranium tetrafluoride, the temperature of the reaction chamber is lowered to ahout 400 deg C, and elemental fluorine is used as the fluorinating agent for the conversion of UF/sub 4/ into UF/sub 6/. The fluorine gas is passed into the chamber, and the UF/sub 6/ formed passes out and is delivered to a condenser.

  7. Industrial Permit

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

    Industrial Permit Industrial Permit The Industrial Permit authorizes the Laboratory to discharge point-source effluents under the National Pollutant Discharge Elimination System. October 15, 2012 Outfall from the Laboratory's Data Communications Center cooling towers Intermittent flow of discharged water from the Laboratory's Data Communications Center eventually reaches perennial segment of Sandia Canyon during storm events (Outfall 03A199). Contact Environmental Communication & Public

  8. NERSC Annual Reports

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

    NERSC Annual Reports NERSC Annual Reports Sort by: Default | Name anrep2000.png NERSC Annual Report 2000 Download Image: anrep2000.png | png | 203 KB Download File: NERSCAnnualReport2000.pdf | pdf | 4.9 MB anrep2001.png NERSC Annual Report 2001 Download Image: anrep2001.png | png | 175 KB Download File: annrep01.pdf | pdf | 7.1 MB anrep2002.png NERSC Annual Report 2002 Download Image: anrep2002.png | png | 55 KB Download File: annrep02.pdf | pdf | 3.4 MB anrep2003.png NERSC Annual Report 2003

  9. Annual Energy Review 1999

    SciTech Connect (OSTI)

    Seiferlein, Katherine E.

    2000-07-01

    A generation ago the Ford Foundation convened a group of experts to explore and assess the Nation’s energy future, and published their conclusions in A Time To Choose: America’s Energy Future (Cambridge, MA: Ballinger, 1974). The Energy Policy Project developed scenarios of U.S. potential energy use in 1985 and 2000. Now, with 1985 well behind us and 2000 nearly on the record books, it may be of interest to take a look back to see what actually happened and consider what it means for our future. The study group sketched three primary scenarios with differing assumptions about the growth of energy use. The Historical Growth scenario assumed that U.S. energy consumption would continue to expand by 3.4 percent per year, the average rate from 1950 to 1970. This scenario assumed no intentional efforts to change the pattern of consumption, only efforts to encourage development of our energy supply. The Technical Fix scenario anticipated a “conscious national effort to use energy more efficiently through engineering know-how." The Zero Energy Growth scenario, while not clamping down on the economy or calling for austerity, incorporated the Technical Fix efficiencies plus additional efficiencies. This third path anticipated that economic growth would depend less on energy-intensive industries and more on those that require less energy, i.e., the service sector. In 2000, total energy consumption was projected to be 187 quadrillion British thermal units (Btu) in the Historical Growth case, 124 quadrillion Btu in the Technical Fix case, and 100 quadrillion Btu in the Zero Energy Growth case. The Annual Energy Review 1999 reports a preliminary total consumption for 1999 of 97 quadrillion Btu (see Table 1.1), and the Energy Information Administration’s Short-Term Energy Outlook (April 2000) forecasts total energy consumption of 98 quadrillion Btu in 2000. What energy consumption path did the United States actually travel to get from 1974, when the scenarios were drawn, to the end of the century? What happened to the relationship between growth and energy consumption? How did the fuel mix change over this period? What are the effects of energy usage on our environment? What level of consumption will the United States—and the world—record in the Annual Energy Review 2025? We present this edition of the Annual Energy Review to help investigate these important questions and to stimulate and inform our thinking about what the future holds.

  10. Industrial Users

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

    by cosmic-ray-induced neutrons upon miniature electronic devices, such as chips that help control aircraft or complex integrated circuits in automobiles. Industrial User...

  11. 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...

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

    Gasoline and Diesel Fuel Update (EIA)

    Thank

  13. Potential of Melastoma malabathricum as bio-accumulator for uranium and thorium from soil

    SciTech Connect (OSTI)

    Saat, Ahmad; Kamsani, Ain Shaqina; Kamri, Wan Nur Aina Nadzira; Talib, Nur Hasyimah Mat; Wood, Ab Khalik; Hamzah, Zaini

    2015-04-29

    Uranium and Thorium are naturally occuring radionuclides. However, due to anthropogenic activities in some locations their concentrations in the soils could be elevated. This study explores the potential of Melastoma malabathricum (locally known as ‘pokok senduduk’) as bio-accumulator of uranium and thorium from soils of three different study areas, namely former tin mining, industrial and residential/commercial areas in Peninsular Malaysia. The study found elevated concentrations of uranium and thorium in former tin mining soils as compared to natural abundance. However in industral and residential/commercial areas the concentrations are within the range of natural abundance. In terms of transfer factor (TF), in ex-mining areas TF > 1 for uranium in the leaf, stem and roots, indicating accumulation of uranium from soil. However for thorium TF < 1, indicating the occurence of transfer from soil to root, stem and leaf, but no accumulation. For other areas only transfer of uranium and thorium were observed. The results indicated the potential of Melastoma malabathricum to be used as bio-accumulatior of uranium, especially in areas of elevated concentration.

  14. METHOD OF APPLYING NICKEL COATINGS ON URANIUM

    DOE Patents [OSTI]

    Gray, A.G.

    1959-07-14

    A method is presented for protectively coating uranium which comprises etching the uranium in an aqueous etching solution containing chloride ions, electroplating a coating of nickel on the etched uranium and heating the nickel plated uranium by immersion thereof in a molten bath composed of a material selected from the group consisting of sodium chloride, potassium chloride, lithium chloride, and mixtures thereof, maintained at a temperature of between 700 and 800 deg C, for a time sufficient to alloy the nickel and uranium and form an integral protective coating of corrosion-resistant uranium-nickel alloy.

  15. SOLVENT EXTRACTION PROCESS FOR URANIUM RECOVERY

    DOE Patents [OSTI]

    Clark, H.M.; Duffey, D.

    1958-06-17

    A process is described for extracting uranium from uranium ore, wherein the uranium is substantially free from molybdenum contamination. In a solvent extraction process for recovering uranium, uranium and molybdenum ions are extracted from the ore with ether under high acidity conditions. The ether phase is then stripped with water at a lower controiled acidity, resaturated with salting materials such as sodium nitrate, and reextracted with the separation of the molybdenum from the uranium without interference from other metals that have been previously extracted.

  16. LNG Annual Report - 2006 | Department of Energy

    Energy Savers [EERE]

    6 LNG Annual Report - 2006 LNG Annual Report - 2006 PDF icon LNG Annual Report - 2006 More Documents & Publications LNG Annual Report - 2007 LNG Annual Report - 2008

  17. LNG Annual Report - 2010 | Department of Energy

    Energy Savers [EERE]

    10 LNG Annual Report - 2010 LNG Annual Report - 2010 PDF icon LNG Annual Report - 2010 More Documents & Publications LNG Annual Report - 2009 LNG Annual Report - 2008

  18. OHA 2008 ANNUAL REPORT | Department of Energy

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

    8 ANNUAL REPORT OHA 2008 ANNUAL REPORT PDF icon OHA 2008 ANNUAL REPORT FINAL More Documents & Publications OHA 2007 ANNUAL REPORT OHA 2009 ANNUAL REPORT OHA 2015

  19. Russian Experience in the Regulatory Supervision of the Uranium Legacy Sites - 12441

    SciTech Connect (OSTI)

    Kiselev, M.F.; Romanov, V.V.; Shandala, N.K.; Titov, A.V.; Kiselev, S.M.; Seregin, V.A.; Metlyaev, E.G.; Novikova, N.; Khokhlova, E.A.

    2012-07-01

    Management of the uranium legacy is accompanied with environmental impact intensity of which depends on the amount of the waste generated, the extent of that waste localization and environmental spreading. The question is: how hazardous is such impact on the environment and human health? The criterion for safety assurance is adequate regulation of the uranium legacy. Since the establishment of the uranium industry, the well done regulatory system operates in the FMBA of Russia. Such system covers inter alia, the uranium legacy. This system includes the extent laboratory network of independent control and supervision, scientific researches, regulative practices. The current Russian normative and legal basis of the regulation and its application practice has a number of problems relating to the uranium legacy, connected firstly with the environmental remediation. To improve the regulatory system, the urgent tasks are: -To introduce the existing exposure situation into the national laws and standards in compliance with the ICRP system. - To develop criteria for site remediation and return, by stages, to uncontrolled uses. The similar criteria have been developed within the Russian-Norwegian cooperation for the purpose of remediation of the sites for temporary storage of SNF and RW. - To consider possibilities and methods of optimization for the remediation strategies under development. - To separate the special category - RW resulted from uranium ore mining and dressing. The current Russian RW classification is based on the waste subdivision in terms of the specific activities. Having in mind the new RW-specific law, we receive the opportunity to separate some special category - RW originated from the uranium mining and milling. Introduction of such category can simplify significantly the situation with management of waste of uranium mining and milling processes. Such approach is implemented in many countries and approved by IAEA. The category of 'RW originated from uranium mining and milling' is to be introduced as the legal acts and regulatory documents. The recent ICRP recommendations provide the flexible approaches for solving of such tasks. The FMBA of Russia recognizes the problems of radiation safety assurance related to the legacy of the former USSR in the uranium mining industry. Some part of the regulatory problems assumes to be solved within the EurAsEC inter-state target program 'Reclamation of the territories of the EurAsEC member states affected by the uranium mining and milling facilities'. Using the example of the uranium legacy sites in Kyrgyz and Tajikistan which could result in the tran-boundary disasters and require urgent reclamation, the experience will be gained to be used in other states as well. Harmonization of the national legislations and regulative documents on radiation safety assurance is envisaged. (authors)

  20. Industrial Users

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

    Industrial Users - Media Publications and Information The Invisible Neutron Threat Neutron-Induced Failures in Semiconductor Devices Nuclear Science Research at the LANSCE-WNR Facility Links About WNR Industrial Users 4FP30L-A/ICE House 4FP30R/ICE II Media

  1. Annual Performance Report FY 2012, Annual Performance Plan FY...

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

    2, Annual Performance Plan FY 2013 & FY 2014 Annual Performance Report FY 2012, Annual Performance Plan FY 2013 & FY 2014 PDF icon Annual Performance Report and Plan FY12 FY13 FY14 ...

  2. ARM - Annual Reports

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

    MaterialsAnnual Reports Publications Journal Articles Conference Documents Program Documents Technical Reports Publications Database Public Information Materials Image Library...

  3. Annual Reports - Hanford Site

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

    Annual Reports Soil & Groundwater Home Annual Reports Environmental Data Access Administrative Record Annual Reports Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size NEW The Groundwater Remediation Project issues an annual report describing its accomplishments and plans. The projects associated with the Groundwater Remediation Project also issue periodic status reports. Those reports can be found in this section. Title Issue Date Rev. Document Information 2014

  4. NASEO 2015 Annual Meeting

    Broader source: Energy.gov [DOE]

    The National Association of State Energy Officials (NASEO) Annual Meeting will be held in San Diego, California.

  5. Annual Site Environmental Report

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

    2014 Annual Site Environmental Report Updated July 24, 2015 NETL's Annual Site Environmental Report for 2014 -ii- 2014 Annual Site Environmental Report September 9, 2015 U.S. Department of Energy National Energy Technology Laboratory Albany, Oregon Anchorage, Alaska Morgantown, West Virginia Pittsburgh, Pennsylvania Sugar Land, Texas NETL's Annual Site Environmental Report for 2014 -iii- Disclaimer This report was prepared as an account of work sponsored by an agency of the U.S. Government.

  6. 2012 Annual Plan | Department of Energy

    Energy Savers [EERE]

    Annual Plan 2012 Annual Plan Section 999: 2012 Annual Plan PDF icon Section 999 - 2012 Annual Plan More Documents & Publications 2011 Annual Plan Sec. 999 Annual Plan 2012 2013 Annual Plan

  7. Draft 2014 Annual Plan | Department of Energy

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

    Draft 2014 Annual Plan Draft 2014 Annual Plan Section 999: Draft 2014 Annual Plan PDF icon Section 999 - Draft 2014 Annual Plan More Documents & Publications 2011 Annual Plan 2013 Annual Plan Sec. 999 Annual Plan 2012

  8. Reducing emissions from uranium dissolving

    SciTech Connect (OSTI)

    Griffith, W.L.; Compere, A.L.; Huxtable, W.P.; Googin, J.M.

    1992-10-01

    This study was designed to assess the feasibility of decreasing NO[sub x] emissions from the current uranium alloy scrap tray dissolving facility. In the current process, uranium scrap is dissolved in boiling nitric acid in shallow stainless-steel trays. As scrap dissolves, more metal and more nitric acid are added to the tray by operating personnel. Safe geometry is assured by keeping liquid level at or below 5 cm, the depth of a safe infinite slab. The accountability batch control system provides additional protection against criticality. Both uranium and uranium alloys are dissolved. Nitric acid is recovered from the vapors for reuse. Metal nitrates are sent to uranium recovery. Brown NO[sub x] fumes evolved during dissolving have occasionally resulted in a visible plume from the trays. The fuming is most noticeable during startup and after addition of fresh acid to a tray. Present environmental regulations are expected to require control of brown NO[sub x] emissions. A detailed review of the literature, indicated the feasibility of slightly altering process chemistry to favor the production of NO[sub 2] which can be scrubbed and recycled as nitric acid. Methods for controlling the process to manage offgas product distribution and to minimize chemical reaction hazards were also considered.

  9. Reducing emissions from uranium dissolving

    SciTech Connect (OSTI)

    Griffith, W.L.; Compere, A.L.; Huxtable, W.P.; Googin, J.M.

    1992-10-01

    This study was designed to assess the feasibility of decreasing NO{sub x} emissions from the current uranium alloy scrap tray dissolving facility. In the current process, uranium scrap is dissolved in boiling nitric acid in shallow stainless-steel trays. As scrap dissolves, more metal and more nitric acid are added to the tray by operating personnel. Safe geometry is assured by keeping liquid level at or below 5 cm, the depth of a safe infinite slab. The accountability batch control system provides additional protection against criticality. Both uranium and uranium alloys are dissolved. Nitric acid is recovered from the vapors for reuse. Metal nitrates are sent to uranium recovery. Brown NO{sub x} fumes evolved during dissolving have occasionally resulted in a visible plume from the trays. The fuming is most noticeable during startup and after addition of fresh acid to a tray. Present environmental regulations are expected to require control of brown NO{sub x} emissions. A detailed review of the literature, indicated the feasibility of slightly altering process chemistry to favor the production of NO{sub 2} which can be scrubbed and recycled as nitric acid. Methods for controlling the process to manage offgas product distribution and to minimize chemical reaction hazards were also considered.

  10. Absorption of Thermal Neutrons in Uranium

    DOE R&D Accomplishments [OSTI]

    Creutz, E. C.; Wilson, R. R.; Wigner, E. P.

    1941-09-26

    A knowledge of the absorption processes for neutrons in uranium is important for planning a chain reaction experiment. The absorption of thermal neutrons in uranium and uranium oxide has been studied. Neutrons from the cyclotron were slowed down by passage through a graphite block. A uranium or uranium oxide sphere was placed at various positions in the block. The neutron intensity at different points in the sphere and in the graphite was measured by observing the activity induced in detectors or uranium oxide or manganese. It was found that both the fission activity in the uranium oxide and the activity induced in manganese was affected by non-thermal neutrons. An experimental correction for such effects was made by making measurements with the detectors surrounded by cadmium. After such corrections the results from three methods of procedure with the uranium oxide detectors and from the manganese detectors were consistent to within a few per cent.

  11. Inherently safe in situ uranium recovery

    DOE Patents [OSTI]

    Krumhansl, James L; Brady, Patrick V

    2014-04-29

    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.

  12. The Electrolytic Production of Metallic Uranium

    DOE Patents [OSTI]

    Rosen, R.

    1950-08-22

    This patent covers a process for producing metallic uranium by electrolyzing uranium tetrafluoride at an elevated temperature in a fused bath consisting essentially of mixed alkali and alkaline earth halides.

  13. Uranium Mining and Milling near Rifle, Colorado

    Broader source: Energy.gov [DOE]

    The small town of Rifle, Colorado, has an interesting history related to uranium and vanadium production. A mineral found near Rifle, called roscolite, contains both vanadium and uranium but was...

  14. RECOVERY OF URANIUM VALUES FROM URANIUM BEARING RAW MATERIALS

    DOE Patents [OSTI]

    Michal, E.J.; Porter, R.R.

    1959-06-16

    Uranium leaching from ground uranium-bearing raw materials using MnO/sub 2/ in H/sub 2/SO/sub 4/ is described. The MnO/sub 2/ oxidizes U to the leachable hexavalent state. The MnO/sub 2/ does not replace Fe normally added, because the Fe complexes P and catalyzes the MnO/sub 2/ reaction. Three examples of continuous processes are given, but batch operation is also possible. The use of MnO/sub 2/ makes possible recovery of very low U values. (T.R.H.)

  15. U.S. Billion-Ton Update: Biomass Supply for a Bioenergy and Bioproducts Industry

    Broader source: Energy.gov [DOE]

    An update to the 2005 report, "Biomass as a Feedstock for a Bioenergy and Bioproducts Industry: The Technical Feasibility of a Billion-Ton Annual Supply"

  16. METHOD OF APPLYING COPPER COATINGS TO URANIUM

    DOE Patents [OSTI]

    Gray, A.G.

    1959-07-14

    A method is presented for protecting metallic uranium, which comprises anodic etching of the uranium in an aqueous phosphoric acid solution containing chloride ions, cleaning the etched uranium in aqueous nitric acid solution, promptly electro-plating the cleaned uranium in a copper electro-plating bath, and then electro-plating thereupon lead, tin, zinc, cadmium, chromium or nickel from an aqueous electro-plating bath.

  17. Uranium Management and Policy | Department of Energy

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

    Uranium Management and Policy Uranium Management and Policy The Paducah Gaseous Diffusion Plant is located 3 miles south of the Ohio River and is 12 miles west of Paducah, Kentucky. Paducah remains the only operating gaseous diffusion uranium enrichment plant in the United States. The Paducah Gaseous Diffusion Plant is located 3 miles south of the Ohio River and is 12 miles west of Paducah, Kentucky. Paducah remains the only operating gaseous diffusion uranium enrichment plant in the United

  18. URANIUM BISMUTHIDE DISPERSION IN MOLTEN METAL

    DOE Patents [OSTI]

    Teitel, R.J.

    1959-10-27

    The formation of intermetallic bismuth compounds of thorium or uranium dispersed in a liquid media containing bismuth and lead is described. A bismuthide of uranium dispersed in a liquid metal medium is formed by dissolving uranium in composition of lead and bismuth containing less than 80% lead and lowering the temperature of the composition to a temperature below the point at which the solubility of uranium is exceeded and above the melting point of the composition.

  19. PROCESS FOR THE RECOVERY OF URANIUM

    DOE Patents [OSTI]

    Morris, G.O.

    1955-06-21

    This patent relates to a process for the recovery of uranium from impure uranium tetrafluoride. The process consists essentially of the steps of dissolving the impure uranium tetrafluoride in excess dilute sulfuric acid in the presence of excess hydrogen peroxide, precipitating ammonium uranate from the solution so formed by adding an excess of aqueous ammonia, dissolving the precipitate in sulfuric acid and adding hydrogen peroxide to precipitate uranium peroxdde.

  20. Industry Economist

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will report to the Manager of Load Forecasting and Analysis of the Customer Services Organization. He/she serves as an industry economist engaged in load...

  1. Industry Perspective

    Broader source: Energy.gov [DOE]

    Fuel cell and biogas industries perspectives. Presented by Mike Hicks, Fuel Cell and Hydrogen Energy Association, at the NREL/DOE Biogas and Fuel Cells Workshop held June 11-13, 2012, in Golden, Colorado.

  2. Continuous reduction of uranium tetrafluoride

    SciTech Connect (OSTI)

    DeMint, A.L.; Maxey, A.W.

    1993-10-21

    Operation of a pilot-scale system for continuous metallothermic reduction of uranium tetrafluoride (UF{sub 4} or green salt) has been initiated. This activity is in support of the development of a cost- effective process to produce uranium-iron (U-Fe) alloy feed for the Uranium-Atomic Vapor Laser Isotope Separation (U-AVLIS) program. To date, five runs have been made to reduce green salt (UF{sub 4}) with magnesium. During this quarter, three runs were made to perfect the feeding system, examine feed rates, and determine the need for a crust breaker/stirrer. No material was drawn off in any of the runs; both product metal and by-product salt were allowed to accumulate in the reactor.

  3. Industry @ ALS

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

    Industry @ ALS Industry @ ALS Hewlett Packard Labs Gains Insights with Innovative ALS Research Tools Print Thursday, 05 May 2016 11:21 For the past eight years, Hewlett Packard Labs, the central research organization of Hewlett Packard Enterprise, has been using cutting-edge ALS techniques to advance some of their most promising technological research, including vanadium dioxide phase transitions and atomic movement during memristor operation. Read more... ALS, Molecular Foundry, and aBeam

  4. CATALYZED OXIDATION OF URANIUM IN CARBONATE SOLUTIONS

    DOE Patents [OSTI]

    Clifford, W.E.

    1962-05-29

    A process is given wherein carbonate solutions are employed to leach uranium from ores and the like containing lower valent uranium species by utilizing catalytic amounts of copper in the presence of ammonia therein and simultaneously supplying an oxidizing agent thereto. The catalysis accelerates rate of dissolution and increases recovery of uranium from the ore. (AEC)

  5. PROCESS FOR SEPARATING URANIUM FISSION PRODUCTS

    DOE Patents [OSTI]

    Spedding, F.H.; Butler, T.A.; Johns, I.B.

    1959-03-10

    The removal of fission products such as strontium, barium, cesium, rubidium, or iodine from neutronirradiated uranium is described. Uranium halide or elemental halogen is added to melted irradiated uranium to convert the fission products to either more volatile compositions which vaporize from the melt or to higher melting point compositions which separate as solids.

  6. High strength uranium-tungsten alloy process

    DOE Patents [OSTI]

    Dunn, Paul S.; Sheinberg, Haskell; Hogan, Billy M.; Lewis, Homer D.; Dickinson, James M.

    1990-01-01

    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.

  7. High strength uranium-tungsten alloys

    DOE Patents [OSTI]

    Dunn, Paul S.; Sheinberg, Haskell; Hogan, Billy M.; Lewis, Homer D.; Dickinson, James M.

    1991-01-01

    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.

  8. Annual outlook for US electric power, 1986

    SciTech Connect (OSTI)

    Not Available

    1986-04-24

    This document includes summary information on the ownership structure of the US electric utility industry, a description of electric utility regulation, and identification of selected factors likely to affect US electricity markets from 1985 through 1995. This Outlook expands upon projections first presented in the Annual Energy Outlook 1985, offering additional discussion of projected US electricity markets and regional detail. It should be recognized that work on the Annual Energy Outlook 1985 had been completed prior to the sharp reductions in world oil prices experienced early in 1986.

  9. METHOD OF PROTECTIVELY COATING URANIUM

    DOE Patents [OSTI]

    Eubank, L.D.; Boller, E.R.

    1959-02-01

    A method is described for protectively coating uranium with zine comprising cleaning the U for coating by pickling in concentrated HNO/sub 3/, dipping the cleaned U into a bath of molten zinc between 430 to 600 C and containing less than 0 01% each of Fe and Pb, and withdrawing and cooling to solidify the coating. The zinccoated uranium may be given a; econd coating with another metal niore resistant to the corrosive influences particularly concerned. A coating of Pb containing small proportions of Ag or Sn, or Al containing small proportions of Si may be applied over the zinc coatings by dipping in molten baths of these metals.

  10. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    4. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status Operating status at the end of In-situ-leach plant owner In-situ-leach plant name County, state (existing and planned locations) Production capacity (pounds U3O8 per year) 2015 1st quarter 2016 AUC LLC Reno Creek Campbell, Wyoming 2,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Azarga Uranium Corp. Dewey Burdock Project Fall River and Custer, South Dakota 1,000,000 Partially

  11. 2015 Domestic Uranium Production Report

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

    Domestic Uranium Production Report 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 State(s) 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 Wyoming 134 139 181 195 245 301 308 348 424 512 531 416 343 Colorado and Texas 48 140 269 263 557 696 340 292 331 248 198 105 79 Nebraska and New Mexico 92 102 123 160 149 160 159 134 127 W W W W Arizona, Utah, and Washington 47 40 75 120 245 360 273 281 W W W W W Alaska, Michigan, Nevada, and

  12. 2015 Domestic Uranium Production Report

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

    Domestic Uranium Production Report 2015 Domestic Uranium Production Report Release Date: May 5, 2016 Next Release Date: May 2017 million pounds U 3 O 8 $0 to $30 per pound $0 to $50 per pound $0 to $100 per pound $0 to $30 per pound $0 to $50 per pound $0 to $100 per pound Properties with Exploration Completed, Exploration Continuing, and Only Assessment Work W W 154.6 24.3 W 151.6 Properties Under Development for Production and Development Drilling W 38.2 W W 38.2 W Mines in Production W 19.2 W

  13. 2015 Domestic Uranium Production Report

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

    10. Uranium reserve estimates at the end of 2014 and 2015" "million pounds U3O8" ,"End of 2014",,,"End of 2015" "Uranium Reserve Estimates1 by Mine and Property Status, Mining Method, and State(s)","Forward Cost 2" ,"$0 to $30 per pound","$0 to $50 per pound","$0 to $100 per pound","$0 to $30 per pound","$0 to $50 per pound","$0 to $100 per pound" "Properties with Exploration

  14. Electron Backscatter Diffraction (EBSD) Characterization of Uranium and Uranium Alloys

    SciTech Connect (OSTI)

    McCabe, Rodney J.; Kelly, Ann Marie; Clarke, Amy J.; Field, Robert D.; Wenk, H. R.

    2012-07-25

    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.

  15. Removal of uranium from aqueous HF solutions

    DOE Patents [OSTI]

    Pulley, Howard; Seltzer, Steven F.

    1980-01-01

    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.

  16. Development of pulsed neutron uranium logging instrument

    SciTech Connect (OSTI)

    Wang, Xin-guang; Liu, Dan; Zhang, Feng

    2015-03-15

    This article introduces a development of pulsed neutron uranium logging instrument. By analyzing the temporal distribution of epithermal neutrons generated from the thermal fission of {sup 235}U, we propose a new method with a uranium-bearing index to calculate the uranium content in the formation. An instrument employing a D-T neutron generator and two epithermal neutron detectors has been developed. The logging response is studied using Monte Carlo simulation and experiments in calibration wells. The simulation and experimental results show that the uranium-bearing index is linearly correlated with the uranium content, and the porosity and thermal neutron lifetime of the formation can be acquired simultaneously.

  17. 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)

    1991-01-01

    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.

  18. SEPARATION OF PLUTONIUM FROM URANIUM

    DOE Patents [OSTI]

    Feder, H.M.; Nuttall, R.L.

    1959-12-15

    A process is described for extracting plutonium from powdered neutron- irradiated urarium metal by contacting the latter, while maintaining it in the solid form, with molten magnesium which takes up the plutonium and separating the molten magnesium from the solid uranium.

  19. GRAIN REFINEMENT OF URANIUM BILLETS

    DOE Patents [OSTI]

    Lewis, L.

    1964-02-25

    A method of refining the grain structure of massive uranium billets without resort to forging is described. The method consists in the steps of beta- quenching the billets, annealing the quenched billets in the upper alpha temperature range, and extrusion upset of the billets to an extent sufficient to increase the cross sectional area by at least 5 per cent. (AEC)

  20. Commercial / Industrial Lighting

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

    New Commercial Program Development Commercial Current Promotions Industrial Federal Agriculture Commercial & Industrial Lighting Efficiency Program The Commercial & Industrial...

  1. Annual Site Environmental Report

    Energy Savers [EERE]

    Department of Energy Annual Reports to Congress on Federal Government Energy Management Annual Reports to Congress on Federal Government Energy Management Annual reports on federal energy management respond to section 548 of the National Energy Conservation Policy Act (NECPA, Pub. L. No. 95-619), as amended, and provide information on energy consumption in federal buildings, operations, and vehicles. Compiled by the Federal Energy Management Program, these reports document activities

  2. Uranium Enrichment Standards of the Y-12 Nuclear Detection and Sensor Testing Center

    SciTech Connect (OSTI)

    Cantrell, J.

    2012-05-23

    The Y-12 National Security Complex has recently fabricated and characterized a new series of metallic uranium standards for use in the Nuclear Detection and Sensor Testing Center (NDSTC). Ten uranium metal disks with enrichments varying from 0.2 to 93.2% {sup 235}U were designed to provide researchers access to a wide variety of measurement scenarios in a single testing venue. Special care was taken in the selection of the enrichments in order to closely bracket the definitions of reactor fuel at 4% {sup 235}U and that of highly enriched uranium (HEU) at 20% {sup 235}U. Each standard is well characterized using analytical chemistry as well as a series of gamma-ray spectrometry measurements. Gamma-ray spectra of these standards are being archived in a reference library for use by customers of the NDSTC. A software database tool has been created that allows for easier access and comparison of various spectra. Information provided through the database includes: raw count data (including background spectra), regions of interest (ROIs), and full width half maximum calculations. Input is being sought from the user community on future needs including enhancements to the spectral database and additional Uranium standards, shielding configurations and detector types. A related presentation are planned for the INMM 53rd Annual Meeting (Hull, et al.), which describe new uranium chemical compound standards and testing opportunities at Y-12 Nuclear Detection and Sensor Testing Center (NDSTC).

  3. NUG Annual Meetings

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

    NUGEX Elections Charter User Announcements Help Staff Blogs Request Repository Mailing List Operations for: Passwords & Off-Hours Status 1-800-66-NERSC, option 1 or 510-486-6821 Account Support https://nim.nersc.gov accounts@nersc.gov 1-800-66-NERSC, option 2 or 510-486-8612 Consulting http://help.nersc.gov consult@nersc.gov 1-800-66-NERSC, option 3 or 510-486-8611 Home » For Users » NERSC Users Group » Annual Meetings NUG Annual Meetings NUG holds annual face-to-face meetings. The annual

  4. 2007 Annual Report

    SciTech Connect (OSTI)

    2007-01-01

    This annual report includes: a brief overview of Western; FY 2007 highlights; FY 2007 Integrated Resource Planning, or IRP, survey; and financial data.

  5. EMSL 2009 Annual Report

    SciTech Connect (OSTI)

    Showalter, Mary Ann; Kathmann, Loel E.; Manke, Kristin L.; Wiley, Julie G.; Reed, Jennifer R.

    2010-02-26

    The EMSL 2009 Annual Report describes the science conducted at EMSL during 2009 as well as outreach activities and awards and honors received by users and staff.

  6. OPSI Annual Meeting

    Broader source: Energy.gov [DOE]

    The Organization of PJM States, Inc. (OPSI) is hosting its annual meeting in Chicago, IL, on October 13-14, 2014.

  7. Current Annualized Request

    Office of Environmental Management (EM)

    Appropriation FY 2012 FY 2013 FY 2014 Current Annualized Request CR % Energy And Water Development, And Related Agencies Energy Programs Energy Efficiency and Renewable Energy...

  8. FEOSH Annual Safety Training

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) has developed an annual safety training course that is mandatory for all current DOE Federal employees and for each new hire.

  9. Historical Natural Gas Annual

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

    6 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

  10. Historical Natural Gas Annual

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

    7 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

  11. Historical Natural Gas Annual

    Gasoline and Diesel Fuel Update (EIA)

    8 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

  12. SPEER Third Annual Summit

    Broader source: Energy.gov [DOE]

    The South-Central Partnership for Energy Efficiency as a Resource (SPEER) is hosting their 3rd Annual Summit in Dallas, Texas.

  13. Required Annual Notices

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

    Annual Notices The Women's Health and Cancer Rights Act of 1998 (WHCRA) The medical programs sponsored by LANS will not restrict benefits if you or your dependent receives...

  14. Required Annual Notices

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

    Required Annual Notices The Women's Health and Cancer Rights Act of 1998 (WHCRA) The medical programs sponsored by LANS will not restrict benefits if you or your dependent...

  15. BPA 2002 Annual Report

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

    STATEMENTS 2002 Annual Report of the Bonneville Power Administration Cover photo BPA fish biologist Andy Thoms (upper right) works with students from H.B. Lee Middle School...

  16. Historical Natural Gas Annual

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

    Historical Natural Gas Annual . 1996 Published October 1997 1997 Published October 1998 1998 Published October 1999 1999 Published October 2000 2000 Published December 2001

  17. Annual Energy Outlook2014

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

    For further information . . . The Annual Energy Outlook 2014 (AEO2014) was prepared by the U.S. Energy Information Administration (EIA), under the direction of John J. Conti...

  18. NRECA Annual Meeting

    Broader source: Energy.gov [DOE]

    The National Rural Electric Cooperative Association (NRECA) is hosting its annual conference in Orlando, FL, on Feb. 19-27, 2015.

  19. OPSI Annual Meeting

    Broader source: Energy.gov [DOE]

    The Organization of PJM States, Inc. (OPSI) is hosting its annual meeting with sessions covering clean power, gas and electric coordination, and more.

  20. Uranium isotopes fingerprint biotic reduction

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

    Stylo, Malgorzata; Neubert, Nadja; Wang, Yuheng; Monga, Nikhil; Romaniello, Stephen J.; Weyer, Stefan; Bernier-Latmani, Rizlan

    2015-04-20

    Knowledge of paleo-redox conditions in the Earth’s history provides a window into events that shaped the evolution of life on our planet. The role of microbial activity in paleo-redox processes remains unexplored due to the inability to discriminate biotic from abiotic redox transformations in the rock record. The ability to deconvolute these two processes would provide a means to identify environmental niches in which microbial activity was prevalent at a specific time in paleo-history and to correlate specific biogeochemical events with the corresponding microbial metabolism. Here, we demonstrate that the isotopic signature associated with microbial reduction of hexavalent uranium (U),more » i.e., the accumulation of the heavy isotope in the U(IV) phase, is readily distinguishable from that generated by abiotic uranium reduction in laboratory experiments. Thus, isotope signatures preserved in the geologic record through the reductive precipitation of uranium may provide the sought-after tool to probe for biotic processes. Because uranium is a common element in the Earth’s crust and a wide variety of metabolic groups of microorganisms catalyze the biological reduction of U(VI), this tool is applicable to a multiplicity of geological epochs and terrestrial environments. The findings of this study indicate that biological activity contributed to the formation of many authigenic U deposits, including sandstone U deposits of various ages, as well as modern, Cretaceous, and Archean black shales. In addition, engineered bioremediation activities also exhibit a biotic signature, suggesting that, although multiple pathways may be involved in the reduction, direct enzymatic reduction contributes substantially to the immobilization of uranium.« less

  1. Uranium isotopes fingerprint biotic reduction

    SciTech Connect (OSTI)

    Stylo, Malgorzata; Neubert, Nadja; Wang, Yuheng; Monga, Nikhil; Romaniello, Stephen J.; Weyer, Stefan; Bernier-Latmani, Rizlan

    2015-04-20

    Knowledge of paleo-redox conditions in the Earth’s history provides a window into events that shaped the evolution of life on our planet. The role of microbial activity in paleo-redox processes remains unexplored due to the inability to discriminate biotic from abiotic redox transformations in the rock record. The ability to deconvolute these two processes would provide a means to identify environmental niches in which microbial activity was prevalent at a specific time in paleo-history and to correlate specific biogeochemical events with the corresponding microbial metabolism. Here, we demonstrate that the isotopic signature associated with microbial reduction of hexavalent uranium (U), i.e., the accumulation of the heavy isotope in the U(IV) phase, is readily distinguishable from that generated by abiotic uranium reduction in laboratory experiments. Thus, isotope signatures preserved in the geologic record through the reductive precipitation of uranium may provide the sought-after tool to probe for biotic processes. Because uranium is a common element in the Earth’s crust and a wide variety of metabolic groups of microorganisms catalyze the biological reduction of U(VI), this tool is applicable to a multiplicity of geological epochs and terrestrial environments. The findings of this study indicate that biological activity contributed to the formation of many authigenic U deposits, including sandstone U deposits of various ages, as well as modern, Cretaceous, and Archean black shales. In addition, engineered bioremediation activities also exhibit a biotic signature, suggesting that, although multiple pathways may be involved in the reduction, direct enzymatic reduction contributes substantially to the immobilization of uranium.

  2. Reducing Emissions from Uranium Dissolving

    SciTech Connect (OSTI)

    Griffith, W.L.

    1992-01-01

    This study was designed to assess the feasibility of decreasing NO{sub x} emissions from the current uranium alloy scrap tray dissolving facility. In the current process, uranium scrap is dissolved in boiling nitric acid in shallow stainless-steel trays. As scrap dissolves, more metal and more nitric acid are added to the tray by operating personnel. Safe geometry is assured by keeping liquid level at or below 5 cm, the depth of a safe infinite slab. The accountability batch control system provides additional protection against criticality. The trays are steam coil heated. The process has operated satisfactorily, with few difficulties, for decades. Both uranium and uranium alloys are dissolved. Nitric acid is recovered from the vapors for reuse. Metal nitrates are sent to uranium recovery. Brown NO{sub x} fumes evolved during dissolving have occasionally resulted in a visible plume from the trays. The fuming is most noticeable during startup and after addition of fresh acid to a tray. Present environmental regulations are expected to require control of brown NO{sub x} emissions. Because NO{sub x} is hazardous, fumes should be suppressed whenever the electric blower system is inoperable. Because the tray dissolving process has worked well for decades, as much of the current capital equipment and operating procedures as possible were preserved. A detailed review of the literature, indicated the feasibility of slightly altering process chemistry to favor the production of NO{sub 2}, which can be scrubbed and recycled as nitric acid. Methods for controlling the process to manage offgas product distribution and to minimize chemical reaction hazards were also considered.

  3. LNG Annual Report - 2004 | Department of Energy

    Energy Savers [EERE]

    4 LNG Annual Report - 2004 LNG Annual Report - 2004 PDF icon LNG Annual Report - 2004 More Documents & Publications LNG Annual Report - 2005 LNG Annual Report - 2007 LNG Annual Report - 2006

  4. LNG Annual Report - 2005 | Department of Energy

    Energy Savers [EERE]

    5 LNG Annual Report - 2005 LNG Annual Report - 2005 PDF icon LNG Annual Report - 2005 More Documents & Publications LNG Annual Report - 2004 LNG Annual Report - 2006 LNG Annual Report - 2007

  5. LNG Annual Report - 2011 | Department of Energy

    Energy Savers [EERE]

    1 LNG Annual Report - 2011 LNG Annual Report - 2011 (Revised 3/15/2012) PDF icon LNG Annual Report 2011 More Documents & Publications LNG Annual Report - 2012 LNG Annual Report - 2013 LNG Annual Report - 2010

  6. LNG Annual Report - 2012 | Department of Energy

    Energy Savers [EERE]

    2 LNG Annual Report - 2012 LNG Annual Report - 2012 (Revised 3/21/2013) PDF icon LNG Annual Report - 2012 More Documents & Publications LNG Annual Report - 2013 LNG Annual Report - 2014 LNG Annual Report - 2011

  7. LNG Annual Report - 2014 | Department of Energy

    Energy Savers [EERE]

    Annual Report - 2014 LNG Annual Report - 2014 LNG Annual Report - 2014 rev PDF icon LNG 2014 rev2.pdf More Documents & Publications LNG Annual Report - 2013 LNG Annual Report - 2012 LNG Annual Report - 2015

  8. Recommendations: 2009 Annual Plan | Department of Energy

    Energy Savers [EERE]

    9 Annual Plan Recommendations: 2009 Annual Plan PDF icon URTAC - Recommendations on 2009 Section 999 Annual Plan More Documents & Publications Recommendations: Draft 2009 Section 999 Annual Plan Recommendations: 2010 Annual Plan Recommendations: Draft 2010 Section 999 Annual Plan

  9. Industry Information Practices and the Failure to Remember | Department of

    Office of Environmental Management (EM)

    Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Industrial Assessment Centers (IACs) Small- and medium-sized manufacturers may be eligible to receive a no-cost assessment provided by DOE Industrial Assessment Centers (IACs). Teams located at 24 universities around the country conduct the energy audits to identify opportunities to improve productivity, reduce waste, and save energy. IACs typically identify more than $130,000 in potential annual savings opportunities for

  10. Eck Industries, Inc. Realizes Savings Through Smarter Lighting Solutions |

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

    Department of Energy Eck Industries, Inc. Realizes Savings Through Smarter Lighting Solutions Eck Industries, Inc. Realizes Savings Through Smarter Lighting Solutions This case study discusses how Eck Industries pursued a lighting retrofit project that reduced its Manitowoc, Wisconsin, facility's plant-wide electricity use, achieved annual operating savings, and provided higher quality lighting. PDF icon Eck Industries, Inc. Realizes Savings Through Smarter Lighting Solutions (January 2011)

  11. Natural gas annual 1992: Supplement: Company profiles

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    The data for the Natural Gas Annual 1991 Supplement : Company Profiles are taken from Form EIA-176, (open quotes) Annual Report of Natural and Supplemental Gas Supply and Disposition (close quotes). Other sources include industry literature and corporate annual reports to shareholders. The companies appearing in this report are major interstate natural gas pipeline companies, large distribution companies, or combination companies with both pipeline and distribution operations. The report contains profiles of 45 corporate families. The profiles describe briefly each company, where it operates, and any important issues that the company faces. The purpose of this report is to show the movement of natural gas through the various States served by the 45 large companies profiled.

  12. Petroleum supply annual 1998: Volume 2

    SciTech Connect (OSTI)

    1999-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. This second volume contains final statistics for each month of 1998, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  13. Petroleum supply annual, 1997. Volume 2

    SciTech Connect (OSTI)

    1998-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  14. Petroleum supply annual 1995: Volume 2

    SciTech Connect (OSTI)

    1996-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1995 through monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and selected Refinery Statistics each with final annual data. The second volume contains final statistics for each month of 1995, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary.

  15. Natural gas annual 1993 supplement: Company profiles

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. This report, the Natural Gas Annual 1993 Supplement: Company Profiles, presents a detailed profile of 45 selected companies in the natural gas industry. The purpose of this report is to show the movement of natural gas through the various States served by the companies profiled. The companies in this report are interstate pipeline companies or local distribution companies (LDC`s). Interstate pipeline companies acquire gas supplies from company owned production, purchases from producers, and receipts for transportation for account of others. Pipeline systems, service area maps, company supply and disposition data are presented.

  16. Electric power annual 1997. Volume 1

    SciTech Connect (OSTI)

    1998-07-01

    The Electric Power Annual presents a summary of electric power industry statistics at national, regional, and State levels. The objective of the publication is to provide industry decisionmakers, government policy-makers, analysts, and the general public with data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Electric Power Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. Volume 1 -- with a focus on US electric utilities -- contains final 1997 data on net generation and fossil fuel consumption, stocks, receipts, and cost; preliminary 1997 data on generating unit capability, and retail sales of electricity, associated revenue, and the average revenue per kilowatthour of electricity sold (based on a monthly sample: Form EIA-826, ``Monthly Electric Utility Sales and Revenue Report with State Distributions``). Additionally, information on net generation from renewable energy sources and on the associated generating capability is included in Volume 1 of the EPA.

  17. Electric power annual 1997. Volume 2

    SciTech Connect (OSTI)

    1998-10-01

    The Electric Power Annual 1997, Volume 2 contains annual summary statistics at national, regional, and state levels for the electric power industry, including information on both electric utilities and nonutility power producers. Included are data for electric utility retail sales of electricity, associated revenue, and average revenue per kilowatthour of electricity sold; financial statistics; environmental statistics; power transactions; and demand-side management. Also included are data for US nonutility power producers on installed capacity; gross generation; emissions; and supply and disposition of energy. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts, and the general public with historical data that may be used in understanding US electricity markets. 15 figs., 62 tabs.

  18. Petroleum supply annual 1996: Volume 2

    SciTech Connect (OSTI)

    1997-06-01

    The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1996 through monthly surveys. The PSA is divided into two volumes. The first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Capacity; each with final annual data. The second volume contains final statistics for each month of 1996, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Explanatory Notes, located at the end of this publication, present information describing data collection, sources, estimation methodology, data quality control procedures, modifications to reporting requirements and interpretation of tables. Industry terminology and product definitions are listed alphabetically in the Glossary. 35 tabs.

  19. Macro-Industrial Working Group: meeting 1

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

    July 24, 2012 Macroeconomic team: Kay Smith, Russ Tarver, Elizabeth Sendich and Vipin Arora WORKING GROUP PRESENTATION FOR DISCUSSION PURPOSES DO NOT QUOTE OR CITE AS RESULTS ARE SUBJECT TO CHANGE Joint Macro-Industrial Working Group: Annual Energy Outlook 2013 Macroeconomic Modeling Plans Presentation Goals 2 July 24 2012 Joint Macroeconomics and Industrial Working Group * Highlight proposed macroeconomic AEO2013 modeling changes * Description of Proposed Reference Case - Highlight short-term

  20. Macro-Industrial Working Group: meeting 1

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

    4 Macro/Industrial Working Group Macroeconomic team: Kay Smith, Russ Tarver, Elizabeth Sendich and Vipin Arora Briefing on Macroeconomic Reference Case for the Annual Energy Outlook 2015 Macro's FY2015 AEO initiatives met 2 Kay Smith, AEO2015 Macroeconomic/Industrial Working Group July 24, 2014 PLEASE DO NOT CITE OR DISTRIBUTE * Review incorporation of completed AEO macroeconomic initiatives. - Incorporation of 2009 based GDP - Use of 2007 supply matrix and its extension to 2012 - The extension