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Sample records for uranium production industry

  1. 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.

  2. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Table 9. Summary production statistics of the U.S. uranium industry, 1993-2014 Exploration and Development Surface Drilling Exploration and Development Drilling Expenditures 1 Mine Production of Uranium Uranium Concentrate Production Uranium Concentrate Shipments Employment Year (million feet) (million dollars) (million pounds U 3 O 8 ) (million pounds U 3 O 8 )

  3. 2014 Domestic Uranium Production Report

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

    9. Summary production statistics of the U.S. uranium industry, 1993-2014" ,"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)","Mine Production (million pounds U3O8)","(million pounds

  4. Domestic Uranium Production Report

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

    9. Summary production statistics of the U.S. uranium industry, 1993-2014 Year Exploration and development surface drilling (million feet) Exploration and development drilling expenditures 1 (million dollars) Mine production of uranium (million pounds U3O8) Uranium concentrate production (million pounds U3O8) Uranium concentrate shipments (million pounds U3O8) Employment (person-years) 1993 1.1 5.7 2.1 3.1 3.4 871 1994 0.7 1.1 2.5 3.4 6.3 980 1995 1.3 2.6 3.5 6.0 5.5 1,107 1996 3.0 7.2 4.7 6.3

  5. 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.

  6. Domestic Uranium Production Report

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

    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 134 139 181 195 245 301 308 348 424 512 531 416 Colorado and Texas 48 140 269 263 557 696 340 292 331 248 198 105 Nebraska and New Mexico 92 102 123 160 149 160 159 134 127 W W W Arizona, Utah, and Washington 47 40 75 120 245 360 273 281 W W W W Alaska, Michigan, Nevada, and South Dakota 0 0 0 16 25 30 W W W W W 0 California, Montana,

  7. Domestic Uranium Production Report

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

    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 18 108 W W 121 420 2005 79 149 142 154 124 648 2006 188 121 W W 155 755 2007 375 378 107 216 155 1,231 2008 457 558 W W 154 1,563 2009 175 441 W W 162 1,096 2010 211 400 W W 125 1,073 2011 208 462 W W 102 1,191 2012 161 462 W W 179 1,196 2013 149 392 W W 199 1,156 2014 86 246 W W 161

  8. 2014 Domestic Uranium Production Report

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

    Domestic Uranium Production Report April 2015 Independent ... by the U.S. Energy Information Administration (EIA), ... Team, Office of Electricity, Renewables, and Uranium ...

  9. Domestic Uranium Production Report

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

    10. Uranium reserve estimates at the end of 2013 and 2014 million pounds U3O8 End of 2013 End of 2014 Forward Cost2 Uranium Reserve Estimates1 by Mine and Property Status, Mining Method, and State(s) $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 130.7 W W 154.6 Properties Under Development for Production and Development Drilling W

  10. Domestic Uranium Production Report

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

    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 Estimated contained U3O8 (thousand pounds) Ore from Mines and Stockpiles Fed to Mills1 0 W W W 0 W W W W W W W Other Feed Materials 2 W W W W W W W W W W W W Total Mill Feed W W W W W W W W W W W W Uranium Concentrate Produced at U.S. Mills (thousand pounds U3O8) W W W W W W W W W W W W Uranium Concentrate Produced at

  11. 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.

  12. 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.

  13. 2014 Domestic Uranium Production Report

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

    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",134,139,181,195,245,301,308,348,424,512,531,416 "Colorado and Texas",48,140,269,263,557,696,340,292,331,248,198,105 "Nebraska and New Mexico",92,102,123,160,149,160,159,134,127,"W","W","W" "Arizona, Utah, and

  14. Domestic Uranium Production Report

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

    2. U.S. uranium mine production and number of mines and sources, 2003-14 Production / Mining method 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 Underground (estimated contained thousand pounds U3O8) W W W W W W W W W W W W Open Pit (estimated contained thousand pounds U3O8) 0 0 0 0 0 0 0 0 0 0 0 0 In-Situ Leaching (thousand pounds U3O8) W W 2,681 4,259 W W W W W W W W Other1 (thousand pounds U3O8) W W W W W W W W W W W W Total Mine Production (thousand pounds U3O8) E2,200 2,452

  15. Domestic Uranium Production Report

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

    Resources, Inc. dba Cameco Resources Smith Ranch-Highland Operation Converse, Wyoming ... Uranium is first processed at the Nichols Ranch plant and then transported to the Smith ...

  16. Uranium Mining, Conversion, and Enrichment Industries

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

    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 1,600

  17. 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.

  18. 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.

  19. Domestic Uranium Production Report

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

    8. U.S. uranium expenditures, 2003-14 million dollars Year Drilling1 Production2 Land and other 3 Total expenditures Total land and other Land Exploration Reclamation 2003 W W 31.3 NA NA NA W 2004 10.6 27.8 48.4 NA NA NA 86.9 2005 18.1 58.2 59.7 NA NA NA 136.0 2006 40.1 65.9 115.2 41.0 23.3 50.9 221.2 2007 67.5 90.4 178.2 77.7 50.3 50.2 336.2 2008 81.9 221.2 164.4 65.2 50.2 49.1 467.6 2009 35.4 141.0 104.0 17.3 24.2 62.4 280.5 2010 44.6 133.3 99.5 20.2 34.5 44.7 277.3 2011 53.6 168.8 96.8 19.6

  20. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 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 130.7 W W 154.6 Properties Under Development for Production and Development Drilling W 31.8 W W 38.2 W Mines in Production W 19.6 W

  1. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 State(s) 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 Wyoming 134 139 181 195 245 301 308 348 424 512 531 416 Colorado and Texas 48 140 269 263 557 696 340 292 331 248 198 105 Nebraska and New Mexico 92 102 123 160 149 160 159 134 127 W W W Arizona, Utah, and Washington 47 40 75 120 245 360 273 281 W W W W Alaska, Michigan, Nevada, and South Dakota 0

  2. Domestic Uranium Production Report

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

    4. U.S. uranium mills by owner, location, capacity, and operating status at end of the year, 2010-14 Owner Mill and Heap Leach1 Facility name County, state (existing and planned locations) Capacity (short tons of ore per day) Operating status at end of the year 2010 2011 2012 2013 2014 EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating Processing Alternate Feed Operating-Processing Alternate Feed Energy Fuels Resources Corp Pinon Ridge Mill Montrose,

  3. Domestic Uranium Production Report

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

    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 Feet (thousand) Number of holes Feet (thousand) 2003 NA NA NA NA W W 2004 W W W W 2,185 1,249 2005 W W W W 3,143 1,668 2006 1,473 821 3,430 1,892 4,903 2,713 2007 4,351 2,200 4,996 2,946 9,347 5,146 2008 5,198 2,543 4,157 2,551 9,355 5,093 2009 1,790 1,051 3,889 2,691 5,679 3,742 2010 2,439 1,460 4,770 3,444 7,209 4,904

  4. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Number of Holes Feet (thousand) Number of Holes Feet (thousand) Number of Holes Feet (thousand) 2003 NA NA NA NA W W 2004 W W W W 2,185 1,249 2005 W W W W 3,143 1,668 2006 1,473 821 3,430 1,892 4,903 2,713 2007 4,351 2,200 4,996 2,946 9,347 5,146 2008 5,198 2,543 4,157 2,551 9,355 5,093 2009 1,790 1,051 3,889 2,691 5,679 3,742 2010 2,439 1,460 4,770 3,444 7,209

  5. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Activity at U.S. Mills and In-Situ-Leach Plants 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 Ore from Underground Mines and Stockpiles Fed to Mills 1 0 W W W 0 W W W W W W W Other Feed Materials 2 W W W W W W W W W W W W Total Mill Feed W W W W W W W W W W W W (thousand pounds U 3 O 8 ) W W W W W W W W W W W W (thousand pounds U 3 O 8 ) W W W W W W W

  6. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    7 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Capacity (short tons of ore per day) 2010 2011 2012 2013 2014 EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating-Processing Alternate Feed Operating-Processing Alternate Feed Energy Fuels Resources Corp Pinon Ridge Mill Montrose, Colorado 500 Developing Permitted And Licensed Partially Permitted And Licensed Permitted And Licensed Permitted And Licensed

  7. 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...

  8. 2014 Domestic Uranium Production Report

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

    2. U.S. uranium mine production and number of mines and sources, 2003-14" "Production / Mining Method",2003,2004,2005,2006,2007,2008,2009,2010,2011,2012,2013,2014 "Underground" "(estimated contained thousand pounds U3O8)","W","W","W","W","W","W","W","W","W","W","W","W" "Open Pit" "(estimated contained thousand pounds

  9. Domestic Uranium Production Report - Energy Information Administration

    Gasoline and Diesel Fuel Update (EIA)

    Domestic Uranium Production Report - Annual With Data for 2014 | Release Date: April 30, 2015 | Next Release Date: May 2016 | full report Previous domestic uranium production reports Year: 2013 2012 2011 2010 2009 2008 2007 2006 2005 2004 Go Drilling Figure 1. U.S. Uranium drilling by number of holes, 2004-14 Total uranium drilling was 1,752 holes covering 1.3 million feet, 67% fewer holes than in 2013 and the lowest since 2004. Expenditures for uranium drilling in the United States were $28

  10. 2014 Domestic Uranium Production Report

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

    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 "Estimated contained U3O8 (thousand pounds)" "Ore from Underground Mines and Stockpiles Fed to Mills 1",0,"W","W","W",0,"W","W","W","W","W","W","W" "Other Feed Materials

  11. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    5 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Production / Mining Method 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 (estimated contained thousand pounds U 3 O 8 ) W W W W W W W W W W W W (estimated contained thousand pounds U 3 O 8 ) 0 0 0 0 0 0 0 0 0 0 0 0 (thousand pounds U 3 O 8 ) W W 2,681 4,259 W W W W W W W W (thousand pounds U 3 O 8 ) W W W W W W W W W W W W (thousand pounds U 3 O 8 ) E2,200 2,452 3,045 4,692 4,541

  12. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    9 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Year Exploration Mining Milling Processing Reclamation Total 2003 W W W W 117 321 2004 18 108 W W 121 420 2005 79 149 142 154 124 648 2006 188 121 W W 155 755 2007 375 378 107 216 155 1,231 2008 457 558 W W 154 1,563 2009 175 441 W W 162 1,096 2010 211 400 W W 125 1,073 2011 208 462 W W 102 1,191 2012 161 462 W W 179 1,196 2013 149 392 W W 199 1,156 2014 86 246 W W 161 787 Figure 3. Employment in

  13. Domestic Uranium Production Report - Quarterly

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

    1. Total production of uranium concentrate in the United States, 1996 - 4th quarter 2015 pounds U3O8 Calendar-year quarter 1st quarter 2nd quarter 3rd quarter 4th quarter Calendar-year total 1996 1,734,427 1,460,058 1,691,796 1,434,425 6,320,706 1997 1,149,050 1,321,079 1,631,384 1,541,052 5,642,565 1998 1,151,587 1,143,942 1,203,042 1,206,003 4,704,574 1999 1,196,225 1,132,566 1,204,984 1,076,897 4,610,672 2000 1,018,683 983,330 981,948 973,585 3,975,545 2001 709,177 748,298 628,720 553,060

  14. 2014 Domestic Uranium Production Report

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

    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. ...

  15. 2014 Domestic Uranium Production Report

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

    Jab and Antelope Sweetwater, Wyoming 2,000,000 Developing Developing Developing Developing Developing Uranium One Americas, Inc. Moore Ranch Campbell, Wyoming 500,000 Permitted And ...

  16. 2014 Domestic Uranium Production Report

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

    ...ing","Developing","Developing","Developing","Developing" "Uranium One Americas, Inc.","Moore Ranch","Campbell, Wyoming",500000,"Permitted And Licensed","Permitted And ...

  17. Domestic Uranium Production Report - Quarterly

    Gasoline and Diesel Fuel Update (EIA)

    Resources, Inc. dba Cameco Resources Smith Ranch-Highland Operation Converse, Wyoming ... Uranium is first processed at the Nichols Ranch plant and then transported to the Smith ...

  18. 2014 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    11 2014 Domestic Uranium Production Report Release Date: April 30, 2015 Next Release Date: May 2016 Total Land and Other 2003 W W 31.3 NA NA NA W 2004 10.6 27.8 48.4 NA NA NA 86.9 2005 18.1 58.2 59.7 NA NA NA 136.0 2006 40.1 65.9 115.2 41.0 23.3 50.9 221.2 2007 67.5 90.4 178.2 77.7 50.3 50.2 336.2 2008 81.9 221.2 164.4 65.2 50.2 49.1 467.6 2009 35.4 141.0 104.0 17.3 24.2 62.4 280.5 2010 44.6 133.3 99.5 20.2 34.5 44.7 277.3 2011 53.6 168.8 96.8 19.6 43.5 33.7 319.2 2012 66.6 186.9 99.4 16.8 33.3

  19. Decommissioning of U.S. Uranium Production Facilities

    Reports and Publications (EIA)

    1995-01-01

    This report analyzes the uranium production facility decommissioning process and its potential impact on uranium supply and prices. 1995 represents the most recent publication year.

  20. 3rd Quarter 2015 Domestic Uranium Production Report

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

    U.S. Energy Information Administration: Form EIA-851A and Form EIA-851Q, ""Domestic Uranium Production Report.""" " U.S. Energy Information Administration Domestic Uranium...

  1. Domestic Uranium Production Report 4th Quarter 2015

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

    Domestic Uranium Production Report 4th Quarter 2015 February ... DC 20585 U.S. Energy Information Administration | ... Team, Office of Electricity, Renewables, and Uranium ...

  2. 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 - other operations 2 In-situ-leach plants 3 Byproduct recovery plants 4 Total 1996 0 2 5 2 9 1997 0 3 6 2 11 1998 0 2 6 1 9 1999 1 2 4 0 7 2000 1 2 3 0 6 2001 0 1 3 0 4 2002 0 1 2 0 3 2003 0 0 2 0 2 2004 0 0 3 0 3 2005 0 1 3 0 4 2006 0 1 5 0 6 2007 0 1 5 0 6 2008 1 0 6 0 7 2009 0 1 3 0 4 2010 1 0 4 0 5 2011 1 0 5 0 6 2012 1

  3. 2014 Domestic Uranium Production Report

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

    10. Uranium reserve estimates at the end of 2013 and 2014" "million pounds U3O8" ,"End of 2013",,,"End of 2014" "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

  4. Domestic Uranium Production Report - Quarterly

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

    3. U.S. uranium mills and heap leach facilities by owner, location, capacity, and operating status Operating status at the end of Owner Mill and Heap Leach1 Facility name County, state (existing and planned locations) Capacity (short tons of ore per day) 2014 1st quarter 2015 2nd quarter 2015 3rd quarter 2015 4th Quarter 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

  5. Forest Products Industry Technology Roadmap

    SciTech Connect (OSTI)

    none,

    2010-04-01

    This document describes the forest products industry's research and development priorities. The original technology roadmap published by the industry in 1999 and was most recently updated in April 2010.

  6. 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.

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

    National Nuclear Security Administration (NNSA)

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

  8. Domestic Uranium Production Report - Quarterly - Energy Information

    Gasoline and Diesel Fuel Update (EIA)

    Administration All Nuclear Reports Domestic Uranium Production Report - Quarterly Data for 4th Quarter 2015 | Release Date: February 18, 2015 | Next Release Date: May 2016 | full report Previous Issues Year: 2015-Q3 2015-Q2 2015-Q1 2014-Q4 2014-Q3 2014-Q2 2014-Q1 2013-Q4 2013-Q3 2013-Q2 2013-Q1 2012-Q4 2012-Q3 2012-Q2 2012-Q1 2011-Q4 2011-Q3 2011-Q2 2011-Q1 2010-Q4 2010-Q3 2010-Q2 2010-Q1 2009-Q4 2009-Q3 2009-Q2 2009-Q1 2008-Q4 2008-Q3 2008-Q2 2008-Q1 Go 4th Quarter 2015 U.S. production of

  9. SEPARATION OF PLUTONIUM FROM URANIUM AND FISSION PRODUCTS

    DOE Patents [OSTI]

    Boyd, G.E.; Adamson, A.W.; Schubert, J.; Russell, E.R.

    1958-10-01

    A chromatographic adsorption process is presented for the separation of plutonium from other fission products formed by the irradiation of uranium. The plutonium and the lighter element fission products are adsorbed on a sulfonated phenol-formaldehyde resin bed from a nitric acid solution containing the dissolved uranium. Successive washes of sulfuric, phosphoric, and nitric acids remove the bulk of the fission products, then an eluate of dilute phosphoric and nitric acids removes the remaining plutonium and fission products. The plutonium is selectively removed by passing this solution through zirconium phosphate, from which the plutonium is dissolved with nitric acid. This process provides a convenient and efficient means for isolating plutonium.

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

    SciTech Connect (OSTI)

    McGinnis, Brent

    2014-04-01

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

  11. Method for the production of uranium chloride salt

    DOE Patents [OSTI]

    Westphal, Brian R.; Mariani, Robert D.

    2013-07-02

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

  12. Forest Products Industry Profile | Department of Energy

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

    Forest Products Industry Profile Forest Products Industry Profile Wood and paper products meet the everyday needs of consumers and businesses. They provide materials essential for communication, education, packaging, construction, shelter, sanitation, and protection. The U.S. forest products industry is based on a renewable and sustainable raw material: wood. It practices recovery and recycling in its operations. Its forests help the global carbon balance by taking up carbon dioxide from the

  13. President Truman Increases Production of Uranium and Plutonium | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Increases Production of Uranium and Plutonium | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases

  14. Method for making a uranium chloride salt product

    DOE Patents [OSTI]

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

    2004-10-05

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

  15. 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...

  16. Karlsruhe Institute for Industrial Production | Open Energy Informatio...

    Open Energy Info (EERE)

    Karlsruhe Institute for Industrial Production Jump to: navigation, search Name: Karlsruhe Institute for Industrial Production Place: Karlsruhe, Germany Zip: 76187 Product: String...

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

    DOE Patents [OSTI]

    Herrmann, Steven Douglas

    2014-05-27

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

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

    Open Energy Info (EERE)

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

  19. 4th Quarter 2015 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Figure 1. Uranium concentrate production in the United States, 1996 - 4th quarter 2015 pounds U 3 O 8 0 500,000 1,000,000 1,500,000 2,000,000 2,500,000 3,000,000 3,500,000 4,000,000 4,500,000 5,000,000 5,500,000 6,000,000 6,500,000 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 P2015 1st quarter 2nd quarter 3rd quarter 4th quarter P = Preliminary data. Source: U.S. Energy Information Administration: Form EIA-851A and Form EIA-851Q, "Domestic

  20. 4th Quarter 2015 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Release Date: February 18, 2016 Next Release Date: May 2016 Table 1. Total production of uranium concentrate in the United States, 1996 - 4th quarter 2015 pounds U 3 O 8 Calendar-year quarter 1st quarter 2nd quarter 3rd quarter 4th quarter Calendar-year total 1996 1,734,427 1,460,058 1,691,796 1,434,425 6,320,706 1997 1,149,050 1,321,079 1,631,384 1,541,052 5,642,565 1998 1,151,587 1,143,942 1,203,042 1,206,003 4,704,574 1999 1,196,225 1,132,566 1,204,984 1,076,897 4,610,672 2000 1,018,683

  1. 4th Quarter 2015 Domestic Uranium Production Report

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

    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. ...

  2. 4th Quarter 2015 Domestic Uranium Production Report

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

    Jab and Antelope Sweetwater, Wyoming 2,000,000 Developing Developing Developing Developing Developing Uranium One Americas, Inc. Moore Ranch Campbell, Wyoming 500,000 Permitted And ...

  3. 4th Quarter 2015 Domestic Uranium Production Report

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

    ...ing","Developing","Developing","Developing","Developing" "Uranium One Americas, Inc.","Moore Ranch","Campbell, Wyoming",500000,"Permitted And Licensed","Permitted And ...

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

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

    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

  5. EIA Energy Efficiency-Table 4f. Industrial Production Indexes...

    Gasoline and Diesel Fuel Update (EIA)

    f Page Last Modified: May 2010 Table 4f. Industrial Production Indexes by Selected Industries, 1998, 2002, and 2006 (2000 100) MECS Survey Years NAICS Subsector and Industry 1998...

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

    Gasoline and Diesel Fuel Update (EIA)

    Thank

  7. Excess Uranium Management

    Broader source: Energy.gov [DOE]

    The Department's Notice of Issues for Public Comment on the effects of DOE transfers of excess uranium on domestic uranium mining, conversion, and enrichment industries.

  8. Draft Supplement Analysis for Location(s) to Dispose of Depleted Uranium Oxide Conversion Product Generated from DOE'S Inventory of Depleted Uranium Hexafluoride

    National Nuclear Security Administration (NNSA)

    DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED URANIUM OXIDE CONVERSION PRODUCT GENERATED FROM DOE'S INVENTORY OF DEPLETED URANIUM HEXAFLUORIDE (DOE/EIS-0359-SA1 AND DOE/EIS-0360-SA1) March 2007 March 2007 i CONTENTS NOTATION........................................................................................................................... iv 1 INTRODUCTION AND BACKGROUND ................................................................. 1 1.1 Why DOE Has Prepared This

  9. 4th Quarter 2015 Domestic Uranium Production Report

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

    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 - other operations 2","In-situ-leach plants 3","Byproduct recovery plants 4","Total" 1996,0,2,5,2,9 1997,0,3,6,2,11 1998,0,2,6,1,9 1999,1,2,4,0,7 2000,1,2,3,0,6 2001,0,1,3,0,4 2002,0,1,2,0,3 2003,0,0,2,0,2 2004,0,0,3,0,3 2005,0,1,3,0,4

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

    SciTech Connect (OSTI)

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

    1981-04-01

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

  11. 4th Quarter 2015 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Table 2. Number of uranium mills and plants producing uranium concentrate in the United States End of Mills - conventional milling 1 Mills - other operations 2 In-situ-leach plants 3 Byproduct recovery plants 4 Total 1996 0 2 5 2 9 1997 0 3 6 2 11 1998 0 2 6 1 9 1999 1 2 4 0 7 2000 1 2 3 0 6 2001 0 1 3 0 4 2002 0 1 2 0 3 2003 0 0 2 0 2 2004 0 0 3 0 3 2005 0 1 3 0 4 2006 0 1 5 0 6 2007 0 1 5 0 6 2008 1 0 6 0 7 2009 0 1 3 0 4 2010 1 0 4 0 5 2011 1 0 5 0 6 2012 1 0 5 0 6 2013 0 1 6 0 7 2014 0 0 7 0

  12. 4th Quarter 2015 Domestic Uranium Production Report

    Gasoline and Diesel Fuel Update (EIA)

    Capacity (short tons of ore per day) 2014 1st quarter 2015 2nd quarter 2015 3rd quarter 2015 4th quarter 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- Processing Alternate Feed Operating Operating- Processing Alternate Feed Operating- Processing Alternate Feed Operating- Processing Alternate Feed Energy Fuels Wyoming Inc Sheep Mountain Fremont, Wyoming 725

  13. Institute for Industrial Productivity (IIP) | Open Energy Information

    Open Energy Info (EERE)

    20037-1701 Website: www.iipnetwork.org References: www.iipnetwork.org The Institute for Industrial Productivity provides companies and governments with the best energy efficiency...

  14. Covered Product Category: Industrial Luminaires (High/Low Bay) | Department

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

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

  15. 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.

  16. Natural Gas and U.S. Industrial Production: A Closer Look at Four Industries

    Gasoline and Diesel Fuel Update (EIA)

    Natural Gas and U.S. Industrial Production: A Closer Look at Four Industries Vipin Arora and Elizabeth Sendich August 30, 2014 Independent Statistics & Analysis www.eia.gov U.S. Energy Information Administration Washington, DC 20585 This paper is released to encourage discussion and critical comment. The analysis and conclusions expressed here are those of the authors and not necessarily those of the U.S. Energy Information Administration. WORKING PAPER SERIES Natural Gas and U.S. Industrial

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

    DOE Patents [OSTI]

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

    2000-02-29

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

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

    Broader source: Energy.gov [DOE]

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

  19. PROJECT RULISON A GOVERNMENT- INDUSTRY NATURAL GAS PRODUCT1 O

    Office of Legacy Management (LM)

    A GOVERNMENT- INDUSTRY NATURAL GAS PRODUCT1 O N S T I M U L A T I O N EXPERIMENT U S I N G A NUCLEAR EXPLOSIVE Issued By PROJECT RULISON JOINT OFFICE OF INFORMATION U. S. ATOMIC ENERGY COMMISSION - AUSTRAL OIL COMPANY, INCORPORATED THE DEPARTMENT OF THE INTERIOR - CER GEONUCLEAR CORPORATION May 1, 1969 OBSERVATION AREA J SURFACE GROUND ZERO AREA S C A L E - I inch e q u a l s approximatly I 2 m i l e s Project Rulison Area Map PROJECT RULISON A N INDUSTRY-GOVERNMENT NATURAL GAS PRODUCT1 ON

  20. Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity

    ScienceCinema (OSTI)

    Selldorff, John; Atwell, Monte

    2014-12-03

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

  1. Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity

    SciTech Connect (OSTI)

    Selldorff, John; Atwell, Monte

    2014-09-23

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

  2. Nanotechnology for the Forest Products Industry Vision and Technology Roadmap

    SciTech Connect (OSTI)

    Atalla, Rajai; Beecher, James; Caron, Robert; Catchmark, Jeffrey; Deng, Yulin; Glasser, Wolfgang; Gray, Derek; Haigler, Candace; Jones, Philip; Joyce, Margaret; Kohlman, Jane; Koukoulas, Alexander; Lancaster, Peter; Perine, Lori; Rodriguez, Augusto; Ragauskas, Arthur; Wegner, Theodore; Zhu, Junyong

    2005-03-01

    A roadmap for Nanotechnology in the Forest Products Industries has been developed under the umbrella of the Agenda 2020 program overseen by the CTO committee. It is expected that the use of new analytical techniques and methodologies will allow us to understand the complex nature of wood based materials and allow the dramatically enhanced use of the major strategic asset the US has in renewable, recyclable resources based on its well managed Forests.

  3. 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)

  4. Effect of Co-solutes on the Products and Solubility of Uranium(VI) Precipitated with Phosphate

    SciTech Connect (OSTI)

    Mehta, Vrajesh; Maillot, Fabien; Wang, Zheming; Catalano, Jeffrey G.; Giammar, Daniel E.

    2014-01-22

    Uranyl phosphate solids are often found with uranium ores, and their low solubility makes them promising target phases for in situ remediation of uranium-contaminated subsurface environments. The products and solubility of uranium(VI) precipitated with phosphate can be affected by the pH, dissolved inorganic carbon (DIC) concentration, and co-solute composition (e.g. Na+/Ca2+) of the groundwater. Batch experiments were performed to study the effect of these parameters on the products and extent of uranium precipitation induced by phosphate addition. In the absence of co-solute cations, chernikovite [H3O(UO2)(PO4)3H2O] precipitated despite uranyl orthophosphate [(UO2)3(PO4)24H2O] being thermodynamically more favorable under certain conditions. As determined using X-ray diffraction, electron microscopy, and laser induced fluorescence spectroscopy, the presence of Na+ or Ca2+ as a co-solute led to the precipitation of sodium autunite ([Na2(UO2)2(PO4)2] and autunite [Ca(UO2)2(PO4)2]), which are structurally similar to chernikovite. In the presence of sodium, the dissolved U(VI) concentrations were generally in agreement with equilibrium predictions of sodium autunite solubility. However, in the calcium-containing systems, the observed concentrations were below the predicted solubility of autunite, suggesting the possibility of uranium adsorption to or incorporation in a calcium phosphate precipitate in addition to the precipitation of autunite.

  5. Site evaluations for the uranium-atomic vapor laser isotope separation (U-AVLIS) production plant

    SciTech Connect (OSTI)

    Wolsko, T.; Absil, M.; Cirillo, R.; Folga, S.; Gillette, J.; Habegger, L.; Whitfield, R.

    1991-07-01

    This report describes a uranium-atomic vapor laser isotope separation (U-AVLIS) production plant siting study conducted during 1990 to identify alternative plant sites for examination in later environmental impact studies. A siting study methodology was developed in early 1990 and was implemented between June and December. This methodology had two parts. The first part -- a series of screening analyses that included exclusionary and other criteria -- was conducted to identify a reasonable number of candidates sites. This slate of candidate sites was then subjected to more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. To fully appreciate the siting study methodology, it is important to understand the U-AVLIS program and site requirements. 16 refs., 29 figs., 54 tabs.

  6. Method for converting uranium oxides to uranium metal

    DOE Patents [OSTI]

    Duerksen, Walter K. (Norris, TN)

    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.

  7. ISSUANCE 2016-02-26: Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Supplemental Proposed Determination of Miscellaneous Refrigeration Products as Covered Products

    Broader source: Energy.gov [DOE]

    Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment: Supplemental Proposed Determination of Miscellaneous Refrigeration Products as Covered Products

  8. Industrial Assessment Centers - Small Manufacturers Reduce Energy & Increase Productivity

    SciTech Connect (OSTI)

    2015-11-06

    Since 1976, the Industrial Assessment Centers (IACs), administered by the US Department of Energy, have supported small and medium-sized American manufacturers to reduce energy use and increase their productivity and competitiveness. The 24 IACs, located at premier engineering universities around the country (see below), send faculty and engineering students to local small and medium-sized manufacturers to provide no-cost assessments of energy use, process performance and waste and water flows. Under the direction of experienced professors, IAC engineering students analyze the manufacturer’s facilities, energy bills and energy, waste and water systems, including compressed air, motors/pumps, lighting, process heat and steam. The IACs then follow up with written energy-saving and productivity improvement recommendations, with estimates of related costs and payback periods.

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

    Broader source: Energy.gov [DOE]

    New report finds the production tax credit has been critical to the growth of the U.S. wind industry.

  10. 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.

  11. 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.

  12. Energy production from food industry wastewaters using bioelectrochemical cells

    SciTech Connect (OSTI)

    Hamilton, Choo Yieng

    2009-01-01

    Conversion of waste and renewable resources to energy using microbial fuel cells (MFCs) is an upcoming technology for enabling a cleaner and sustainable environment. This paper assesses the energy production potential from the US food industry wastewater resource. It also reports on an experimental study investigating conversion of wastewater from a local milk dairy plant to electricity. An MFC anode biocatalyst enriched on model sugar and organic acid substrates was used as the inoculum for the dairy wastewater MFC. The tests were conducted using a two-chamber MFC with a porous three dimensional anode and a Pt/C air-cathode. Power densities up to 690 mW/m2 (54 W/m3) were obtained. Analysis of the food industry wastewater resource indicated that MFCs can potentially recover 2 to 260 kWh/ton of food processed from wastewaters generated during food processing, depending on the biological oxygen demand and volume of water used in the process. A total of 1960 MW of power can potentially be produced from US milk industry wastewaters alone. Hydrogen is an alternate form of energy that can be produced using bioelectrochemical cells. Approximately 2 to 270 m3 of hydrogen can be generated per ton of the food processed. Application of MFCs for treatment of food processing wastewaters requires further investigations into electrode design, materials, liquid flow management, proton transfer, organic loading and scale-up to enable high power densities at the larger scale. Potential for water recycle also exists, but requires careful consideration of the microbiological safety and regulatory aspects and the economic feasibility of the process.

  13. Selling green power in California: Product, industry, and market trends

    SciTech Connect (OSTI)

    Wiser, R.H.; Pickle, S.J.

    1998-05-01

    As one of the first US stages to open its doors to retail electric competition, California offers an important opportunity to assess the effectiveness of green power marketing as a mechanism for supporting renewable energy. This report is an interim assessment of key green power product, industry, and market trends in California. The report identifies and analyzes: the potential size of the green power market in California; the companies participating in the green power market; the green power products being offered and their prices; the impact of the green market on renewable generators and the environment; and the influence of several public policies and non-governmental programs on the market for green power. Data used in this paper have been collected, in large part, from surveys and interviews with green power marketers that took place between December 1997 and April 1998. There remain legitimate concerns over the viability of green power marketing to support significant quantities of renewable energy and provide large environmental gains, and it is far too early to assess the overall strength of customer demand for renewable energy. A critical finding of this report is that, because of the high cost of acquiring and servicing residential customers and the low utility default service price, green power marketing affords new energy service providers one of the only viable entrees to California`s residential marketplace.

  14. Multidisciplinary Graduate Curriculum in Support of the Biobased Products Industry

    SciTech Connect (OSTI)

    John R. Dorgan

    2005-07-31

    The project had a dominant education component. The project involved revising curriculum to educate traditional engineering students in the emerging field of industrial biotechnology. New classes were developed and offered. As a result, the curriculum of the Colorado School of Mines was expanded to include new content. Roughly 100 undergraduates and about 10 graduate students each year benefit from this curricular expansion. The research associated with this project consisted of developing new materials and energy sources from renewable resources. Several significant advances were made, most importantly the heat distortion temperature of polylactide (PLA) was increased through the addition of cellulosic nanowhiskers. The resulting ecobionanocomposites have superior properties which enable the use of renewable resource based plastics in a variety of new applications. Significant amounts of petroleum are thereby saved and considerable environmental benefits also result. Effectiveness and economic feasibility of the project proved excellent. The educational activities are continuing in a sustainable fashion, now being supported by tuition revenues and the normal budgeting of the University. The PI will be teaching one of the newly developed classes will next Fall (Fall 2006), after the close of the DOE grant, and again repeatedly into the future. Now established, the curriculum in biobased products and energy will grow and evolve through regular teaching and revision. On the research side, the new plastic materials appear economically feasible and a new collaboration between the PIs group and Sealed Air, a major food-packaging manufacturer, has been established to bring the new green plastics to market. Public benefits of the project are noteworthy in many respects. These include the development of a better educated workforce and citizenry capable of providing technological innovation as a means of growing the economy and providing jobs. In particular, the educational components addressing the production of bioethanol, biodiesel, and bioplastics provide graduates that can assist American industries in including greater renewable content in feedstocks for materials and fuels. Finally, the collaboration fostered by this grant led to the drafting of a new book entitled, Bioengineering for Sustainability: Materials and Fuels for the 21st Century. This text will be widely available to the public interested in learning more about these important areas of technology.

  15. 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.

  16. 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.

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

    SciTech Connect (OSTI)

    Rutledge, G.P.

    1991-12-31

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

  18. 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....

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

    SciTech Connect (OSTI)

    1980-03-01

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

  20. Report A-94 T" PRODUCTION OF DgO FOR USE IN THE FISSION OP URANIUM

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

    v_^ ' / * Report A-94 T" PRODUCTION OF DgO FOR USE IN THE FISSION OP URANIUM Report by Herold G. Urey, Arlstld V. Grosse, and George Walden, June 23, 1941 LEGAL N O T I C E This report was prepared as an account of Government sponsored work. Neither the United States, nor the Commission, nor any person acting on behalf of the Commission: A . Makes any warranty or representation, express or implied, with respect to the a c - curacy, completeness, or usefulness of the information contained in

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

    SciTech Connect (OSTI)

    Collins, Robert T; Collins, Jack Lee; Hunt, Rodney Dale; Ladd-Lively, Jennifer L; Patton, Kaara K; Hickman, Robert

    2014-01-01

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

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

    DOE Patents [OSTI]

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

    1997-12-16

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

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

    DOE Patents [OSTI]

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

    1997-01-01

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

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

    Broader source: Energy.gov [DOE]

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

  5. Shenzhen Prosunpro PengSangPu Solar Industrial Products Corporation...

    Open Energy Info (EERE)

    China Zip: 518055 Sector: Solar Product: Shenzhen Prosunpro makes and installs flat panel solar passive energy collectors and engineers central solar hot water systems....

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

    DOE Patents [OSTI]

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

    2000-12-12

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

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

    DOE Patents [OSTI]

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

    1997-01-01

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

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

    DOE Patents [OSTI]

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

    1997-03-25

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

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

    SciTech Connect (OSTI)

    John R. Schlup

    2005-11-04

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

  10. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    3 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 2012 2013 2014 Advance Uranium Asset Management Ltd. 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) CNEIC (China Nuclear Energy Industry Corporation) LES, LLC (Louisiana Energy Services) LES, LLC (Louisiana Energy Services) LES, LLC (Louisiana Energy Services) NUKEM, Inc.

  11. Short-Term Energy Outlook Supplement: Energy-weighted industrial production indices

    Gasoline and Diesel Fuel Update (EIA)

    Energy-weighted industrial production indices December 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Short-Term Energy Outlook Supplement: Energy-weighted industrial production indices 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

  12. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    5. Enrichment service sellers to owners and operators of U.S. civilian nuclear power reactors, 2012-14 2012 2013 2014 Advance Uranium Asset Management Ltd. 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) CNEIC (China Nuclear Energy Industry Corporation) LES, LLC (Louisiana Energy Services) LES, LLC (Louisiana Energy Services) LES, LLC (Louisiana Energy Services)

  13. Industrial Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains

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

    Manufacturing ADVANCED MANUFACTURING OFFICE Industrial Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Development of an Open Architecture, Widely Applicable Smart Manufacturing Platform While many U.S. manufacturing operations utilize optimization for individual unit processes, smart manufacturing (SM) systems that integrate manufacturing intelligence in real time across an entire production operation are rare in large companies and virtually

  14. 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 Commissions Mid-Term Appraisal of the countrys 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 Indias 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.

  15. Hazardous waste minimization. Part 3. Waste minimization in the paint and allied products industry

    SciTech Connect (OSTI)

    Lorton, G.A.

    1988-04-01

    This paper looks at waste minimization practices available to the paint and coatings industry. The paper begins with an introduction to the industry and a description of the products. The steps involved in the manufacture of paints and coatings are then described. The paper then identifies the wastes generated. Source reduction and recycling techniques are the predominant means of minimizing waste in this industry. Equipment cleaning wastes are the largest category of wastes, and the paper concentrates on equipment and techniques available to reduce or eliminate these wastes. Techniques are described to reduce the other wastes from manufacturing operations. The paper concludes with a discussion of changing industry product trends and the effect that these trends will have on the generation of waste.

  16. 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.

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

    SciTech Connect (OSTI)

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

    1991-09-01

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

  18. 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.

  19. 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)

  20. Energy Conservation Program for Consumer Products and Commercial and Industrial Equipment

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

    Energy Conservation Program for Consumer Products and Commercial and Industrial Equipment DOE Certification, Compliance, and Enforcement Overview for Plumbing Products April 17, 2014 2 | Building Technologies Program & General Counsel's Office of Enforcement eere.energy.gov Agenda 2 Certification Requirements 3 1 Basic Models Importation Enforcement Overview 4 5 Authority, Coverage, and Definitions Pertinent Regulations & Internet Resources 6 7 Certified Ratings 3 | Building Technologies

  1. Electrolysis of uranium nitride containing fission product elements (Mo, Pd, Nd) in a molten LiCl-KCl eutectic

    SciTech Connect (OSTI)

    Satoh, Takumi; Iwai, Takashi; Arai, Yasuo

    2007-07-01

    The electrolysis of burnup-simulated uranium nitride, UN, containing representative solid fission product elements (Mo, Pd, Nd) was investigated in the molten LiCl-KCl eutectic salt with 0.54 wt% UCl{sub 3} from the view point of application of pyrochemical reprocessing to nitride fuel cycle. It was found from cyclic voltammetry and anodic polarization curve measurement that anodic dissolution of UN began at about -0.75 V vs. Ag/AgCl reference electrode in all samples. After the electrolysis at the constant anodic potential of -0.65 {approx} -0.60 V vs. Ag/AgCl, most of UN was dissolved into LiCl- KCl as UCl{sub 3} at the anode, and U was recovered in the liquid Cd cathode in all samples. Further, Nd was dissolved into LiCl-KCl as NdCl{sub 3}, while Mo and Pd were not dissolved but remained at the anode. (authors)

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

    SciTech Connect (OSTI)

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

    1987-03-01

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

  3. Report on the Effect the Low Enriched Uranium Delivered Under the Highly

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

    Enriched Uranium Agreement Between the USA and the Russian Federation has on the Domestic Uranium Mining, Conversion, and Enrichment Industries and the Ops of the Gaseous Diffusion | Department of Energy on the Effect the Low Enriched Uranium Delivered Under the Highly Enriched Uranium Agreement Between the USA and the Russian Federation has on the Domestic Uranium Mining, Conversion, and Enrichment Industries and the Ops of the Gaseous Diffusion Report on the Effect the Low Enriched Uranium

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

    SciTech Connect (OSTI)

    Not Available

    1992-05-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1992-05-01

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

  6. 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

  7. 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.

  8. 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.

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

    SciTech Connect (OSTI)

    Nges, Ivo Achu; Escobar, Federico; Fu Xinmei; Bjoernsson, Lovisa

    2012-01-15

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

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

    SciTech Connect (OSTI)

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

    1991-09-01

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

  11. 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).

  12. Microsoft PowerPoint - DOE Paducah Site Tour Industry Day - 2012-07-31

    Office of Environmental Management (EM)

    Paducah Site Tour Paducah Gaseous Diffusion Plant (PGDP) Industry Workshop July 31, 2012 Site History/Key Facts In 1950, the Atomic Energy Commission selected the former Kentucky Ordnance Works site for the second of three planned uranium enrichment plants. Construction began in 1951. The first product was shipped in 1952. Placing a converter in an enrichment cell during plant construction. 1 Site History/Key Facts * Uranium was enriched for nuclear weapons until the mid-1960s when the plant

  13. Coupled Physical/Chemical and Biofiltration Technologies to Reduce Air Emissions from Forest Products Industries

    SciTech Connect (OSTI)

    Gary D. McGinnis

    2001-12-31

    The research is a laboratory and bench-scale investigation of a system to concentrate and destroy volatile organic compounds (VOCs), including hazardous air pollutants, formed from the drying of wood and the manufacture of wood board products (e.g., particle board and oriented strandboard). The approach that was investigated involved concentrating the dilute VOCs (<500 ppmv) with a physical/chemical adsorption unit, followed by the treatment of the concentrated voc stream (2,000 to 2,500 ppmv) with a biofiltration unit. The research program lasted three years, and involved three research organizations. Michigan Technological University was the primary recipient of the financial assistance, the USDA Forest Products Laboratory (FPL) and Mississippi State University (MSU) were subcontractors to MTU. The ultimate objective of this research was to develop a pilot-scale demonstration of the technology with sufficient data to provide for the design of an industrial system. No commercialization activities were included in this project.

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

    Broader source: Energy.gov [DOE]

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

  15. 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.

  16. New process modeling [sic], design, and control strategies for energy efficiency, high product quality, and improved productivity in the process industries. Final project report

    SciTech Connect (OSTI)

    Ray, W. Harmon

    2002-06-05

    This project was concerned with the development of process design and control strategies for improving energy efficiency, product quality, and productivity in the process industries. In particular, (i) the resilient design and control of chemical reactors, and (ii) the operation of complex processing systems, was investigated. Specific topics studied included new process modeling procedures, nonlinear controller designs, and control strategies for multiunit integrated processes. Both fundamental and immediately applicable results were obtained. The new design and operation results from this project were incorporated into computer-aided design software and disseminated to industry. The principles and design procedures have found their way into industrial practice.

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

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31

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

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

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31

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

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

    SciTech Connect (OSTI)

    Miller, Bruce; Shea, Winton

    2010-12-31

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

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

    SciTech Connect (OSTI)

    Miller, Bruce; Winton, Shea

    2010-12-31

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

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

    SciTech Connect (OSTI)

    Miller, Bruce; Winton, Shea

    2010-12-31

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

  2. 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.

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

    Office of Environmental Management (EM)

    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

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

    SciTech Connect (OSTI)

    Gualtieri, Alessandro F.; Giacobbe, Carlotta; Sardisco, Lorenza; Saraceno, Michele; Lassinantti Gualtieri, Magdalena; Cavenati, Cinzia; Zanatto, Ivano

    2011-01-15

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

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

    SciTech Connect (OSTI)

    Huang, Shi; Fulbright, Scott P; Zeng, Xiaowei; Yates, Tracy; Wardle, Greg; Chisholm, Stephen T; Xu, Jian; Lammers, Peter

    2011-03-16

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

  6. 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.

  7. 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.

  8. recycled_uranium.cdr

    Office of Legacy Management (LM)

    Recycled Uranium and Transuranics: Their Relationship to Weldon Spring Site Remedial Action Project Introduction Historical Perspective On August 8, 1999, Energy Secretary Bill Richardson announced a comprehensive set of actions to address issues raised at the Paducah, Kentucky, Gaseous Diffusion Plant that may have had the potential to affect the health of the workers. One of the issues addressed the need to determine the extent and significance of radioactive fission products and transuranic

  9. 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.

  10. 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.

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

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

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

  13. 2014 Uranium Marketing Annual Report

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

    5. Enrichment service sellers to owners and operators of U.S. civilian nuclear power reactors, 2012-14" 2012,2013,2014 "Advance Uranium Asset Management Ltd.","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)" "CNEIC (China Nuclear Energy Industry Corporation)","LES, LLC (Louisiana

  14. Electrochemical method of producing eutectic uranium alloy and apparatus

    DOE Patents [OSTI]

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

    1995-01-01

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

  15. Known Challenges Associated with the Production, Transportation, Storage and Usage of Pyrolysis Oil in Residential and Industrial Settings

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

    Known Challenges Associated with the Production, Transportation, Storage and Usage of Pyrolysis Oil in Residential and Industrial Settings Technical Information Exchange on Pyrolysis Oil May 9-10, 2012 Manchester, NH Dr. Jani Lehto VTT Technical Research Centre of Finland 2 07/05/2012 Outline  Introduction  Main challenges today in general  More details on challenges associated with  Feedstock processing  Pyrolysis oil production  Transportation and storage  Use of pyrolysis

  16. ITP Forest Products: Energy and Environmental Profile of the U.S. Pulp and Paper Industry

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

    ENERGY AND ENVIRONMENTAL PROFILE OF THE U.S. PULP AND PAPER INDUSTRY Industrial Technologies Program Wood chips from pulp and paper mills Willow tree research plots, Tully, New York Wood gasifier demonstration, Burlington, Vermont Paper drying steam cans, awaiting shipment December 2005 Energy and Environmental Profile of the U.S. Pulp and Paper Industry December 2005 Prepared by Energetics Incorporated Columbia, Maryland for the U.S. Department of Energy Office of Energy Efficiency and

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

    Broader source: Energy.gov [DOE]

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

  18. Uranium Processing Facility Site Readiness Subproject Completed on Time and

    National Nuclear Security Administration (NNSA)

    Under Budget | National Nuclear Security Administration Field Offices / Welcome to the NNSA Production Office / NPO News Releases / Uranium Processing Facility Site Readiness Subproject Completed ... Uranium Processing Facility Site Readiness Subproject Completed on Time and Under Budget The Uranium Processing Facility (UPF) project celebrates its first major milestone with the completion of site readiness work, delivered on time and under budget.

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

    SciTech Connect (OSTI)

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

    2011-11-01

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

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

    SciTech Connect (OSTI)

    Ferrada, J.J.

    2000-04-03

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

  1. 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.

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

    SciTech Connect (OSTI)

    Joel Morrison; Sharon Elder

    2006-01-24

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

  3. The U.S. Dry-Mill Ethanol Industry: Biobased Products and Bioenergy Initiative Success Stories

    SciTech Connect (OSTI)

    2009-10-28

    This fact sheet provides an overview of the history of ethanol production in the United States and describes innovations in dry-mill ethanol production.

  4. Microsoft Word - L15 01-22 Uranium Tranfers

    Office of Environmental Management (EM)

    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

  5. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, John P.

    1992-01-01

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

  6. Plutonium recovery from spent reactor fuel by uranium displacement

    DOE Patents [OSTI]

    Ackerman, J.P.

    1992-03-17

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

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

    SciTech Connect (OSTI)

    Li, D.; Kaplan, D.

    2012-02-29

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

  8. 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.

  9. Scrap uranium recycling via electron beam melting

    SciTech Connect (OSTI)

    McKoon, R.

    1993-11-01

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

  10. 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.

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

    SciTech Connect (OSTI)

    Joel L. Morrison

    2004-12-28

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the first quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) hosting the SWC spring proposal meeting in Golden Colorado, (2) planning of the upcoming SWC fall technology transfer meetings, and (3) recruiting the SWC base membership.

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

    SciTech Connect (OSTI)

    Joel L. Morrison

    2004-12-23

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the fifteenth quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) hosting the SWC spring proposal meeting in Golden Colorado, (2) planning of the upcoming SWC fall technology transfer meetings, and (3) recruiting the SWC base membership.

  13. 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.

  14. Uranium Marketing Annual Report -

    Annual Energy Outlook [U.S. Energy Information Administration (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...

  15. Uranium Marketing Annual Report -

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

    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...

  16. 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.

  17. 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

  18. 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

  19. Electrolytic process for preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A. (Knoxville, TN)

    1990-01-01

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

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

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

    Uranium Leasing Program Programmatic Environmental Impact Statement (PEIS) Final Uranium Leasing Program Programmatic Environmental Impact Statement (PEIS) Uranium Leasing...

  1. Waste Heat Reduction and Recovery for Improving Furnace Efficiency, Productivity and Emissions Performance: A BestPractices Process Heating Technical Brief. Industrial Technologies Program (ITP) (Brochure).

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

    Waste Heat Reduction and Recovery for Improving Furnace Efficiency, Productivity and Emissions Performance U.S. Department of Energy Energy Efficiency and Renewable Energy Bringing you a prosperous future where energy is clean, abundant, reliable, and affordable Industrial Technologies Program Boosting the productivity and competitiveness of U.S. industry through improvements in energy and environmental performance 1 BestPractices Technical Brief Waste Heat Reduction and Recovery for Improving

  2. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Lemons, T.R.

    1991-12-31

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

  3. 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.

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

    SciTech Connect (OSTI)

    1995-07-05

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

  5. Uranium Mining, Conversion, and Enrichment Industries

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

    ... Thus, increased demand in China and Russia will consume capacity with which URENCO would ... recent years has been from the Asian markets, specifically Japan, Taiwan, and South Korea. ...

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

    SciTech Connect (OSTI)

    Joel L. Morrison

    2002-09-30

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

  7. Domestic Uranium Production Report - Quarterly

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

    Thank

  8. PROCESSING OF URANIUM-METAL-CONTAINING FUEL ELEMENTS

    DOE Patents [OSTI]

    Moore, R.H.

    1962-10-01

    A process is given for recovering uranium from neutronbombarded uranium- aluminum alloys. The alloy is dissolved in an aluminum halide--alkali metal halide mixture in which the halide is a mixture of chloride and bromide, the aluminum halide is present in about stoichiometric quantity as to uranium and fission products and the alkali metal halide in a predominant quantity; the uranium- and electropositive fission-products-containing salt phase is separated from the electronegative-containing metal phase; more aluminum halide is added to the salt phase to obtain equimolarity as to the alkali metal halide; adding an excess of aluminum metal whereby uranium metal is formed and alloyed with the excess aluminum; and separating the uranium-aluminum alloy from the fission- productscontaining salt phase. (AEC)

  9. :- : DRILLING URANIUM BILLETS ON A

    Office of Legacy Management (LM)

    'Xxy";^ ...... ' '. .- -- Metals, Ceramics, and Materials. : . - ,.. ; - . _ : , , ' z . , -, .- . >. ; . .. :- : DRILLING URANIUM BILLETS ON A .-... r .. .. i ' LEBLOND-CARLSTEDT RAPID BORER 4 r . _.i'- ' ...... ' -'".. :-'' ,' :... : , '.- ' ;BY R.' J. ' ANSEN .AEC RESEARCH AND DEVELOPMENT REPORT PERSONAL PROPERTY OF J. F. Schlltz .:- DECLASSIFIED - PER AUTHORITY OF (DAlE) (NhTI L (DATE)UE) FEED MATERIALS PRODUCTION CENTER NATIONAL LFE A COMPANY OF OHIO 26 1 3967 3035406 NLCO -

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

    SciTech Connect (OSTI)

    Joseph, Brian

    2013-12-31

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

  11. About the Uranium Mine Team | Department of Energy

    Energy Savers [EERE]

    Uranium Mine Team About the Uranium Mine Team Text coming

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

    SciTech Connect (OSTI)

    Joel L. Morrison

    2004-05-17

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

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

    SciTech Connect (OSTI)

    Joel L. Morrison

    2002-08-27

    The Pennsylvania State University, under contract to the U.S. Department of Energy, National Energy Technology Laboratory will establish, promote, and manage a national industry-driven Stripper Well Consortium (SWC) that will be focused on improving the production performance of domestic petroleum and/or natural gas stripper wells. The consortium creates a partnership with the U.S. petroleum and natural gas industries and trade associations, state funding agencies, academia, and the National Energy Technology Laboratory. This report serves as the sixth quarterly technical progress report for the SWC. Key activities for this reporting period include: (1) release of 2002 SWC request-for-proposal, (2) organized and hosted the Spring SWC meeting in Columbus, Ohio for membership proposal presentations and review; (3) tentatively scheduled the 2002 fall technology transfer meeting sites, and (4) continued to recruit additional Consortium members. In addition, a literature search that focuses on the use of lasers, microwaves, and acoustics for potential stripper well applications continued.

  14. 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.

  15. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    S2. Uranium feed deliveries, enrichment services, and uranium loaded by owners and operators of U.S. civilian 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 power reactors Uranium in fuel assemblies loaded into U.S. civilian nuclear power reactors U.S.-origin enrichment services purchased Foreign-origin enrichment services purchased Total purchased enrichment services

  16. 2014 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Table S3a. Foreign purchases, foreign sales, and uranium ...

  17. 2014 Uranium Marketing Annual Report

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

    5 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Table S2. Uranium feed deliveries, enrichment services, and uranium loaded by owners ...

  18. 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.

  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. 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...

  1. Uranium Marketing Annual Report -

    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" (20...

  2. Uranium Marketing Annual Report -

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

    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" (20...

  3. Uranium Marketing Annual Report -

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

    rounding. Weighted-average prices are not adjusted for inflation. Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual Survey" (2010-14)....

  4. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    of the United States. Weighted-average prices are not adjusted for inflation. Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual Survey" (2010...

  5. Uranium Marketing Annual Report -

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

    Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual Survey" (2011...

  6. Uranium Marketing Annual Report -

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

    independent rounding. Weighted-average prices are not adjusted for inflation. Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual Survey" (2013...

  7. Uranium Marketing Annual Report -

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

    independent rounding. Weighted-average prices are not adjusted for inflation. Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual Survey" (2010-...

  8. Uranium Marketing Annual Report -

    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...

  9. Fermentation and Hydrogen Metabolism Affect Uranium Reduction by Clostridia

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

    Gao, Weimin; Francis, Arokiasamy J.

    2013-01-01

    Previously, it has been shown that not only is uranium reduction under fermentation condition common among clostridia species, but also the strains differed in the extent of their capability and the pH of the culture significantly affected uranium(VI) reduction. In this study, using HPLC and GC techniques, metabolic properties of those clostridial strains active in uranium reduction under fermentation conditions have been characterized and their effects on capability variance of uranium reduction discussed. Then, the relationship between hydrogen metabolism and uranium reduction has been further explored and the important role played by hydrogenase in uranium(VI) and iron(III) reduction bymore » clostridia demonstrated. When hydrogen was provided as the headspace gas, uranium(VI) reduction occurred in the presence of whole cells of clostridia. This is in contrast to that of nitrogen as the headspace gas. Without clostridia cells, hydrogen alone could not result in uranium(VI) reduction. In alignment with this observation, it was also found that either copper(II) addition or iron depletion in the medium could compromise uranium reduction by clostridia. In the end, a comprehensive model was proposed to explain uranium reduction by clostridia and its relationship to the overall metabolism especially hydrogen (H 2 ) production.« less

  10. Feasibility Study on the Use of On-line Multivariate Statistical Process Control for Safeguards Applications in Natural Uranium Conversion Plants

    SciTech Connect (OSTI)

    Ladd-Lively, Jennifer L

    2014-01-01

    The objective of this work was to determine the feasibility of using on-line multivariate statistical process control (MSPC) for safeguards applications in natural uranium conversion plants. Multivariate statistical process control is commonly used throughout industry for the detection of faults. For safeguards applications in uranium conversion plants, faults could include the diversion of intermediate products such as uranium dioxide, uranium tetrafluoride, and uranium hexafluoride. This study was limited to a 100 metric ton of uranium (MTU) per year natural uranium conversion plant (NUCP) using the wet solvent extraction method for the purification of uranium ore concentrate. A key component in the multivariate statistical methodology is the Principal Component Analysis (PCA) approach for the analysis of data, development of the base case model, and evaluation of future operations. The PCA approach was implemented through the use of singular value decomposition of the data matrix where the data matrix represents normal operation of the plant. Component mole balances were used to model each of the process units in the NUCP. However, this approach could be applied to any data set. The monitoring framework developed in this research could be used to determine whether or not a diversion of material has occurred at an NUCP as part of an International Atomic Energy Agency (IAEA) safeguards system. This approach can be used to identify the key monitoring locations, as well as locations where monitoring is unimportant. Detection limits at the key monitoring locations can also be established using this technique. Several faulty scenarios were developed to test the monitoring framework after the base case or normal operating conditions of the PCA model were established. In all of the scenarios, the monitoring framework was able to detect the fault. Overall this study was successful at meeting the stated objective.

  11. 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...

  12. 2014 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report May 2015 Independent ... DC 20585 U.S. Energy Information Administration | 2014 ... Team, Office of Electricity, Renewables, and Uranium ...

  13. 2014 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand ...

  14. 2014 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Minimum ...

  15. 2014 Uranium Marketing Annual Report

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

    ... Energy Information Administration, Form EIA-858 ""Uranium Marketing Annual Survey"" (2012-14)." "32 U.S. Energy Information Administration 2014 Uranium Marketing Annual Report

  16. 2014 Uranium Marketing Annual Report

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

    U.S. Energy Information Administration 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Origin of ...

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

    DOE Patents [OSTI]

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

    1982-06-29

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

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

    SciTech Connect (OSTI)

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

    2011-11-01

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

  19. URANIUM-SERIES CONSTRAINTS ON RADIONUCLIDE TRANSPORT AND GROUNDWATER FLOW AT NOPAL I URANIUM DEPOSIT, SIERRA PENA BLANCA, MEXICO

    SciTech Connect (OSTI)

    S. J. Goldstein, S. Luo, T. L. Ku, and M. T. Murrell

    2006-04-01

    Uranium-series data for groundwater samples from the vicinity of the Nopal I uranium ore deposit are used to place constraints on radionuclide transport and hydrologic processes at this site, and also, by analogy, at Yucca Mountain. Decreasing uranium concentrations for wells drilled in 2003 suggest that groundwater flow rates are low (< 10 m/yr). Field tests, well productivity, and uranium isotopic constraints also suggest that groundwater flow and mixing is limited at this site. The uranium isotopic systematics for water collected in the mine adit are consistent with longer rock-water interaction times and higher uranium dissolution rates at the front of the adit where the deposit is located. Short-lived nuclide data for groundwater wells are used to calculate retardation factors that are on the order of 1,000 for radium and 10,000 to 10,000,000 for lead and polonium. Radium has enhanced mobility in adit water and fractures near the deposit.

  20. Uranium-Loaded Water Treatment Resins: 'Equivalent Feed' at NRC and Agreement State-Licensed Uranium Recovery Facilities - 12094

    SciTech Connect (OSTI)

    Camper, Larry W.; Michalak, Paul; Cohen, Stephen; Carter, Ted

    2012-07-01

    Community Water Systems (CWSs) are required to remove uranium from drinking water to meet EPA standards. Similarly, mining operations are required to remove uranium from their dewatering discharges to meet permitted surface water discharge limits. Ion exchange (IX) is the primary treatment strategy used by these operations, which loads uranium onto resin beads. Presently, uranium-loaded resin from CWSs and mining operations can be disposed as a waste product or processed by NRC- or Agreement State-licensed uranium recovery facilities if that licensed facility has applied for and received permission to process 'alternate feed'. The disposal of uranium-loaded resin is costly and the cost to amend a uranium recovery license to accept alternate feed can be a strong disincentive to commercial uranium recovery facilities. In response to this issue, the NRC issued a Regulatory Issue Summary (RIS) to clarify the agency's policy that uranium-loaded resin from CWSs and mining operations can be processed by NRC- or Agreement State-licensed uranium recovery facilities without the need for an alternate feed license amendment when these resins are essentially the same, chemically and physically, to resins that licensed uranium recovery facilities currently use (i.e., equivalent feed). NRC staff is clarifying its current alternate feed policy to declare IX resins as equivalent feed. This clarification is necessary to alleviate a regulatory and financial burden on facilities that filter uranium using IX resin, such as CWSs and mine dewatering operations. Disposing of those resins in a licensed facility could be 40 to 50 percent of the total operations and maintenance (O and M) cost for a CWS. Allowing uranium recovery facilities to treat these resins without requiring a license amendment lowers O and M costs and captures a valuable natural resource. (authors)

  1. 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.

  2. Safeguards on uranium ore concentrate? the impact of modern mining and milling process

    SciTech Connect (OSTI)

    Francis, Stephen

    2013-07-01

    Increased purity in uranium ore concentrate not only raises the question as to whether Safeguards should be applied to the entirety of uranium conversion facilities, but also as to whether some degree of coverage should be moved back to uranium ore concentrate production at uranium mining and milling facilities. This paper looks at uranium ore concentrate production across the globe and explores the extent to which increased purity is evident and the underlying reasons. Potential issues this increase in purity raises for IAEA's strategy on the Starting Point of Safeguards are also discussed.

  3. Electrochemical method of producing eutectic uranium alloy and apparatus

    DOE Patents [OSTI]

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

    1995-01-10

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

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

    SciTech Connect (OSTI)

    Olsen, D.K.; Ramzel, E.B.; Strycker, A.R.; Guariguata, G.; Salmen, F.G.

    1994-12-01

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

  5. Advanced uranium enrichment technologies. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Sixth Congress, first session, September 22, 1979

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    This hearing was to learn about projected requirements for enriched uranium. The gas centrifuge work at Oak Ridge, Tennessee, and Portsmouth, Ohio, needed assessing. Laser isotope separation technique needed to be reviewed. Three technologies currently being emphasized in the Department of Energy's Advanced Isotope Separation (AIS) program were discussed; these included the Molecular Laser Isotope Separation (MLIS), Livermore's process called Atomic Vapor Laser Isotope Separation (AVLIS), and Plasma Separation Process (PSP). The status of each process was given. The present DOE AIS program calls for a process selection at the end of FY 1981, development module operation starting in the mid-1980's, pilot plant operations through the late 1980's and early 1990's, and a first production plant in the mid-1990's. (DP)

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

    SciTech Connect (OSTI)

    Joseph Rabovitser

    2009-06-30

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

  7. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    2 U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 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

  8. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    a. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors, 1994-2014 million pounds U3O8 equivalent Delivery year Total purchased Purchased from U.S. producers Purchased from U.S. brokers and traders Purchased from other owners and operators of U.S. civilian nuclear power reactors, other U.S. suppliers, (and U.S. government for 2007)1 Purchased from foreign suppliers U.S.-origin uranium Foreign-origin uranium Spot contracts2 Short, medium, and long-term contracts3 1994

  9. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    . Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by supplier and delivery year, 2010-14 thousand pounds U3O8 equivalent, dollars per pound U3O8 equivalent Deliveries 2010 2011 2012 2013 2014 Purchased from U.S. producers Purchases of U.S.-origin and foreign-origin uranium 350 550 W W W Weighted-average price 47.13 58.12 W W W Purchased from U.S. brokers and traders Purchases of U.S.-origin and foreign-origin uranium 11,745 14,778 11,545 12,835 17,111

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

    SciTech Connect (OSTI)

    McKimpson, Marvin G.

    2006-04-06

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

  11. Uranium Marketing Annual Report -

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

    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...

  12. Uranium Marketing Annual Report -

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

    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...

  13. Uranium Marketing Annual Report -

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

    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...

  14. Uranium Marketing Annual Report -

    Annual Energy Outlook [U.S. Energy Information Administration (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...

  15. Uranium Marketing Annual Report

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

    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...

  16. Uranium Marketing Annual Report -

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

    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...

  17. Uranium Marketing Annual Report -

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

    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...

  18. Uranium Marketing Annual Report -

    Annual Energy Outlook [U.S. Energy Information Administration (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...

  19. Eolica Industrial | Open Energy Information

    Open Energy Info (EERE)

    Industrial Jump to: navigation, search Name: Eolica Industrial Place: Sao Paulo, Sao Paulo, Brazil Zip: 01020-901 Sector: Wind energy Product: Brazil based wind turbine steel...

  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. Meehan s Industrial | Open Energy Information

    Open Energy Info (EERE)

    Meehan s Industrial Jump to: navigation, search Name: Meehan's Industrial Place: Milton, Ontario, Canada Zip: L9T 5C1 Product: Meehan's Industrial is a manufacturer, project...

  2. Lien Hwa Industrial Corporation | Open Energy Information

    Open Energy Info (EERE)

    Lien Hwa Industrial Corporation Jump to: navigation, search Name: Lien Hwa Industrial Corporation Place: Taipei, Taiwan Product: Lien Hwa Industrial Corporation is an agricultural,...

  3. TG Agro Industrial | Open Energy Information

    Open Energy Info (EERE)

    TG Agro Industrial Jump to: navigation, search Name: TG Agro Industrial Place: Brazil Product: Maranhao-based ethanol producer. References: TG Agro Industrial1 This article is a...

  4. Biofuel Industries Group LLC | Open Energy Information

    Open Energy Info (EERE)

    Industries Group LLC Jump to: navigation, search Name: Biofuel Industries Group LLC Place: Adrian, Michigan Zip: 49221 Product: Biofuel Industries Group, LLC owns and operates the...

  5. MRL Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    MRL Industries Inc Jump to: navigation, search Name: MRL Industries Inc Place: Sonora, California Zip: 95370 Sector: Solar Product: MRL Industries is a US company committed to...

  6. Users from Industry

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

    Users from Industry Users from Industry Print The Advanced Light Source (ALS) welcomes industrial users from large and small companies whose projects advance scientific knowledge, investigate the development of new products and manufacturing methods, and/or provide economic benefits and jobs to the economy. The nature of industrial research can be different from traditional university and government sponsored projects, so the ALS has created unique opportunities for new and existing industrial

  7. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

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

    2000-06-01

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

  8. 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

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

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

    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...

  10. 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.

  11. 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)

  12. Process for electrolytically preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A. (Knoxville, TN)

    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.

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

    DOE Patents [OSTI]

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

    1983-08-31

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

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

    DOE Patents [OSTI]

    Pruett, David J. (Knoxville, TN); McTaggart, Donald R. (Knoxville, TN)

    1984-01-01

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

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

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

    Industrial Efficiency and Energy Productivity Video Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video Addthis An error occurred. Try...

  16. Users from Industry

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

    industrial users from large and small companies whose projects advance scientific knowledge, investigate the development of new products and manufacturing methods, andor...

  17. Uranium-titanium-niobium alloy

    DOE Patents [OSTI]

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

    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.

  18. 2014 Uranium Marketing Annual Report

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

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 2013 2014 2013 2014 2013 2014 Weighted-average price ...

  19. 2014 Uranium Marketing Annual Report

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

    2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand pounds U 3 O 8 equivalent Year Maximum ...

  20. 2014 Uranium Marketing Annual Report

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

    1 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Deliveries Uranium concentrate Natural UF 6 Enriched UF 6 Total Purchases 2,004 1,312 ...

  1. 2014 Uranium Marketing Annual Report

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

    2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Table S1a. Uranium purchased by owners and operators of U.S. civilian nuclear power ...

  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. Largest Producer of Steel Products in the United States Achieves Significant Energy Savings at its Minntac Plant; Industrial Technologies Program (ITP) Save Energy Now (SEN) Case Study (Brochure)

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

    Located at Mt. Iron on the Mesabi Iron Range in northern Minnesota, the U. S. Steel Minntac plant produces approxi- mately 14.5 million tons of taconite pellets annually. Largest Producer of Steel Products in the United States Achieves Significant Energy Savings at its Minntac Plant U. S. Steel's Taconite Pellet Manufacturing Facility Improves Process Heating Efficiency and Rejuvenates Energy Savings Strategy Following Save Energy Now Assessment Industrial Technologies Program Case Study

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

    SciTech Connect (OSTI)

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

    2012-07-31

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

  5. 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)

  6. Table 9.3 Uranium Overview, 1949-2011

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

    3 Uranium Overview, 1949-2011 Year Domestic Concentrate Production 1 Purchased Imports 2 Export 2 Sales Electric Plant Purchases From Domestic Suppliers Loaded Into U.S. Nuclear Reactors 3 Inventories Average Price Domestic Suppliers Electric Plants Total Purchased Imports Domestic Purchases Million Pounds Uranium Oxide Dollars 4 per Pound Uranium Oxide 1949 0.36 4.3 0.0 NA NA NA NA NA NA NA 1950 .92 5.5 .0 NA NA NA NA NA NA NA 1951 1.54 6.1 .0 NA NA NA NA NA NA NA 1952 1.74 5.7 .0 NA NA NA NA

  7. Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    b. Weighted-average price of uranium purchased by owners and operators of U.S. civilian nuclear power reactors, 1994-2014 dollars per pound U3O8 equivalent Delivery year Total purchased (weighted-average price) Purchased from U.S. producers Purchased from U.S. brokers and traders Purchased from other owners and operators of U.S. civilian nuclear power reactors, other U.S. suppliers, (and U.S. government for 2007)1 Purchased from foreign suppliers U.S.-origin uranium (weighted-average price)

  8. 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.

  9. 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.

  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. Photovoltaics industry profile

    SciTech Connect (OSTI)

    1980-10-01

    A description of the status of the US photovoltaics industry is given. Principal end-user industries are identified, domestic and foreign market trends are discussed, and industry-organized and US government-organized trade promotion events are listed. Trade associations and trade journals are listed, and a photovoltaic product manufacturers list is included. (WHK)

  12. Science, technology, and the industrialization of laser-driven processes

    SciTech Connect (OSTI)

    Davis, J.I.; Paisner, J.A.

    1985-05-01

    Members of the laser program at Lawrence Livermore National Laboratory (LLNL) reviewed potential applications of lasers in industry, some of which are: isotope separation; cleanup of radioactive waste; trace impurity removal; selective chemical reactions; photochemical activation or dissociation of gases; control of combustion particulates; crystal and powder chemistry; and laser induced biochemistry. Many of these areas are currently under active study in the community. The investigation at LLNL focused on laser isotope separation of atomic uranium because of the large demand (> 1000 tonnes/year) and high product enrichment price (> $600/kg of product) for material used as fuel in commercial light-water nuclear power reactors. They also believed that once the technology was fully developed and deployed, it could be applied directly to separating many elements economically on an industrial scale. The Atomic Vapor Laser Isotope Separation (AVLIS) program at LLNL has an extensive uranium and plutonium program of >$100 M in FY85 and a minor research program for other elements. This report describes the AVLIS program conducted covering the following topics; candidate elements; separative work units; spectroscopic selectivety; major systems; facilities; integrated process model;multivariable sensitivety studies; world market; and US enrichment enterprise. 23 figs. (AT)

  13. Literature review: Phytoaccumulation of chromium, uranium, and plutonium in

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

    plant systems (Technical Report) | SciTech Connect Literature review: Phytoaccumulation of chromium, uranium, and plutonium in plant systems Citation Details In-Document Search Title: Literature review: Phytoaccumulation of chromium, uranium, and plutonium in plant systems × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI

  14. 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.

  15. Enviromech Industries | Open Energy Information

    Open Energy Info (EERE)

    search Name: Enviromech Industries Place: Thousands Palms, California Zip: 92276 Product: Alternative fuel system design and integration company. References: Enviromech...

  16. CEMI Industrial Efficiency (text version)

    Broader source: Energy.gov [DOE]

    Below is the text version for the Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video.

  17. 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.

  18. 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

  19. Development of value-added products from alumina industry mineral wastes using low-temperature-setting phosphate ceramics

    SciTech Connect (OSTI)

    Wagh, A.S.; Jeong, Seung-Young; Singh, D.

    1996-01-01

    A room-temperature process for stabilizing mineral waste streams has been developed, based on acid-base reaction between MgO and H3PO4 or acid phosphate solution. The resulting waste form sets into a hard ceramic in a few hours. In this way, various alumina industry wastes, such as red mud and treated potliner waste, can be solidified into ceramics which can be used as structural materials in waste management and construction industry. Red mud ceramics made by this process were low-porosity materials ({approx}2 vol%) with a compression strength equal to portland cement concrete (4944 psi). Bonding mechanism appears to be result of reactions of boehmite, goethite, and bayerite with the acid solution, and also encapsulation of red mud particles in Mg phosphate matrix. Possible applications include liners for ponds and thickned tailings disposal, dikes for waste ponds, and grouts. Compatability problems arising at the interface of the liner and the waste are avoided.

  20. Sustainable Nanomaterials Industry Perspective

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

    Industry Perspective U.S. Department of Energy Advanced Manufacturing Office Sustainable Nanomaterials Workshop Washington, DC Mark Watkins Senior Vice President MeadWestvaco Corporation July 26, 2012 Transforming the forest products industry through innovation 2 The U.S. Forest Products Industry's Economic Impact  5% of U.S. manufacturing GDP  Ninth largest manufacturing sector in U.S.  On par with plastics and automotive  Top 10 manufacturing employer in 48 states  418 pulp and

  1. Reaction of uranium oxides with chlorine and carbon or carbon monoxide to prepare uranium chlorides

    SciTech Connect (OSTI)

    Haas, P.A.; Lee, D.D.; Mailen, J.C.

    1991-11-01

    The preferred preparation concept of uranium metal for feed to an AVLIS uranium enrichment process requires preparation of uranium tetrachloride (UCI{sub 4}) by reacting uranium oxides (UO{sub 2}/UO{sub 3}) and chlorine (Cl{sub 2}) in a molten chloride salt medium. UO{sub 2} is a very stable metal oxide; thus, the chemical conversion requires both a chlorinating agent and a reducing agent that gives an oxide product which is much more stable than the corresponding chloride. Experimental studies in a quartz reactor of 4-cm ID have demonstrated the practically of some chemical flow sheets. Experimentation has illustrated a sequence of results concerning the chemical flow sheets. Tests with a graphite block at 850{degrees}C demonstrated rapid reactions of Cl{sub 2} and evolution of carbon dioxide (CO{sub 2}) as a product. Use of carbon monoxide (CO) as the reducing agent also gave rapid reactions of Cl{sub 2} and formation of CO{sub 2} at lower temperatures, but the reduction reactions were slower than the chlorinations. Carbon powder in the molten salt melt gave higher rates of reduction and better steady state utilization of Cl{sub 2}. Addition of UO{sub 2} feed while chlorination was in progress greatly improved the operation by avoiding the plugging effects from high UO{sub 2} concentrations and the poor Cl{sub 2} utilizations from low UO{sub 2} concentrations. An UO{sub 3} feed gave undesirable effects while a feed of UO{sub 2}-C spheres was excellent. The UO{sub 2}-C spheres also gave good rates of reaction as a fixed bed without any molten chloride salt. Results with a larger reactor and a bottom condenser for volatilized uranium show collection of condensed uranium chlorides as a loose powder and chlorine utilizations of 95--98% at high feed rates. 14 refs., 7 figs., 14 tabs.

  2. DOE - Office of Legacy Management -- Canonsburg Industrial Park - PA 05

    Office of Legacy Management (LM)

    Canonsburg Industrial Park - PA 05 FUSRAP Considered Sites Site: Canonsburg Industrial Park (PA.05 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Canonsburg, Pennsylvania, Disposal Site Documents Related to Canonsburg Industrial Park 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act

  3. 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...

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

    DOE Patents [OSTI]

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

    1995-05-30

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

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

    DOE Patents [OSTI]

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

    1995-01-01

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

  6. 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.

  7. 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.

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

    SciTech Connect (OSTI)

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

    2009-10-01

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

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

    SciTech Connect (OSTI)

    Rogers, Robin

    2013-12-21

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

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

    SciTech Connect (OSTI)

    Andrews, Lester

    2014-10-17

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

  12. 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.

  13. Aluminum and polymeric coatings for protection of uranium

    SciTech Connect (OSTI)

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

    1983-12-21

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

  14. Method 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.

  15. State-of-the-art adsorption and membrane separation processes for carbon dioxide production from carbon dioxide emitting industries

    SciTech Connect (OSTI)

    Ebner, A.D.; Ritter, J.A.

    2009-07-01

    With the growing concern about global warming placing greater demands on improving energy efficiency and reducing CO{sub 2} emissions, the need for improving the energy intensive, separation processes involving CO{sub 2} is well recognized. The US Department of Energy estimates that the separation of CO{sub 2} represents 75% of the cost associated with its separation, storage, transport, and sequestration operations. Hence, energy efficient, CO{sub 2} separation technologies with improved economics are needed for industrial processing and for future options to capture and concentrate CO{sub 2} for reuse or sequestration. The overall goal of this review is to foster the development of new adsorption and membrane technologies to improve manufacturing efficiency and reduce CO{sub 2} emissions. This study focuses on the power, petrochemical, and other CO{sub 2} emitting industries, and provides a detailed review of the current commercial CO{sub 2} separation technologies, i.e., absorption, adsorption, membrane, and cryogenic, an overview of the emerging adsorption and membrane technologies for CO{sub 2} separation, and both near and long term recommendations for future research on adsorption and membrane technologies. Flow sheets of the principal CO{sub 2} producing processes are provided for guidance and new conceptual flow sheets with ideas on the placement of CO{sub 2} separations technologies have also been devised.

  16. Selective leaching of uranium from uranium-contaminated soils: Progress report 1

    SciTech Connect (OSTI)

    Francis, C.W.; Mattus, A.J.; Farr, L.L.; Elless, M.P.; Lee, S.Y.

    1993-02-01

    Three soils and a sediment contaminated with uranium were used to determine the effectiveness of sodium carbonate and citric acid leaching to decontaminated or remove uranium to acceptable regulatory levels. Two of the soils were surface soils from the DOE facility formerly called the Feed Materials Production Center (FMPC) at Fernald, Ohio. This facility is presently called the Femald Environmental Management Project (FEMP). Carbonate extractions generally removed from 70 to 90% of the uranium from the Fernald storage pad soil. Uranium was slightly more difficult to extract from the Fernald incinerator and the Y-12 landfarm soils. Very small amounts of uranium could be extracted from the storm sewer sediment. Extraction with carbonate at high solution-to-soil ratios were as effective as extractions at low solution-to-soil ratios, indicating attrition by the paddle mixer was not significantly different than that provided in a rotary extractor. Also, pretreatments such as milling or pulverizing the soil sample did not appear to increase extraction efficiency when carbonate extractions were carried out at elevated temperatures (60{degree}C) or long extraction times (23 h). Adding KMnO{sub 4} in the carbonate extraction appeared to increase extraction efficiency from the Fernald incinerator soil but not the Fernald storage pad soil. The most effective leaching rates (> 90 % from both Fernald soils) were obtained using a citrate/dithionite extraction procedure designed to remove amorphous (noncrystalline) iron/aluminum sesquioxides from surfaces of clay minerals. Citric acid also proved to be a very good extractant for uranium.

  17. Selective leaching of uranium from uranium-contaminated soils: Progress report 1

    SciTech Connect (OSTI)

    Francis, C.W.; Mattus, A.J.; Farr, L.L.; Elless, M.P.; Lee, S.Y.

    1993-02-01

    Three soils and a sediment contaminated with uranium were used to determine the effectiveness of sodium carbonate and citric acid leaching to decontaminated or remove uranium to acceptable regulatory levels. Two of the soils were surface soils from the DOE facility formerly called the Feed Materials Production Center (FMPC) at Fernald, Ohio. This facility is presently called the Femald Environmental Management Project (FEMP). Carbonate extractions generally removed from 70 to 90% of the uranium from the Fernald storage pad soil. Uranium was slightly more difficult to extract from the Fernald incinerator and the Y-12 landfarm soils. Very small amounts of uranium could be extracted from the storm sewer sediment. Extraction with carbonate at high solution-to-soil ratios were as effective as extractions at low solution-to-soil ratios, indicating attrition by the paddle mixer was not significantly different than that provided in a rotary extractor. Also, pretreatments such as milling or pulverizing the soil sample did not appear to increase extraction efficiency when carbonate extractions were carried out at elevated temperatures (60[degree]C) or long extraction times (23 h). Adding KMnO[sub 4] in the carbonate extraction appeared to increase extraction efficiency from the Fernald incinerator soil but not the Fernald storage pad soil. The most effective leaching rates (> 90 % from both Fernald soils) were obtained using a citrate/dithionite extraction procedure designed to remove amorphous (noncrystalline) iron/aluminum sesquioxides from surfaces of clay minerals. Citric acid also proved to be a very good extractant for uranium.

  18. 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.

  19. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Delivery year Total purchased (weighted- average price) Purchased from U.S. producers Purchased from U.S. brokers and traders Purchased from other owners and operators of U.S. civilian nuclear power reactors, other U.S. suppliers, (and U.S. government for 2007) 1 Purchased from foreign suppliers U.S.-origin uranium (weighted- average price) Foreign-origin uranium (weighted-

  20. 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...

  1. 2014 Uranium Marketing Annual Survey

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

    5 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Quantity with reported price Weighted-average price Quantity with reported price ...

  2. Uranium Oxide Aerosol Transport in Porous Graphite

    SciTech Connect (OSTI)

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

    2012-01-23

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

  3. 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.

  4. Depleted and Recyclable Uranium in the United States: Inventories and Options

    SciTech Connect (OSTI)

    Schneider, Erich; Scopatza, Anthony; Deinert, Mark

    2007-07-01

    International consumption of uranium currently outpaces production by nearly a factor of two. Secondary supplies from dismantled nuclear weapons, along with civilian and governmental stockpiles, are being used to make up the difference but supplies are limited. Large amounts of {sup 235}U are contained in spent nuclear fuel as well as in the tails left over from past uranium enrichment. The usability of these inhomogeneous uranium supplies depends on their isotopics. We present data on the {sup 235}U content of spent nuclear fuel and depleted uranium tails in the US and discuss the factors that affect its marketability and alternative uses. (authors)

  5. 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.

  6. 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...

  7. 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...

  8. Multiple Mechanisms of Uranium Immobilization by Cellulomonas...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Multiple Mechanisms of Uranium Immobilization by Cellulomonas sp. Strain ES6 Citation Details In-Document Search Title: Multiple Mechanisms of Uranium ...

  9. 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...

  10. 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...

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

    DOE Patents [OSTI]

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

    2001-01-01

    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.

  12. 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.

  13. Feasibility study of wood-fired cogeneration at a Wood Products Industrial Park, Belington, WV. Phase II

    SciTech Connect (OSTI)

    Vasenda, S.K.; Hassler, C.C.

    1992-06-01

    Customarily, electricity is generated in a utility power plant while thermal energy is generated in a heating/cooling plant; the electricity produced at the power plant is transmitted to the heating/cooling plant to power equipments. These two separate systems waste vast amounts of heat and result in individual efficiencies of about 35%. Cogeneration is the sequential production of power (electrical or mechanical) and thermal energy (process steam, hot/chilled water) from a single power source; the reject heat of one process issued as input into the subsequent process. Cogeneration increases the efficiency of these stand-alone systems by producing these two products sequentially at one location using a small additional amount of fuel, rendering the system efficiency greater than 70%. This report discusses cogeneration technologies as applied to wood fuel fired system.

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

    SciTech Connect (OSTI)

    Visser, Ann E; Bridges, Nicholas J

    2014-06-10

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

  15. Novel Sensor for the In Situ Measurement of Uranium Fluxes

    SciTech Connect (OSTI)

    Hatfield, Kirk

    2015-02-10

    The goal of this project was to develop a sensor that incorporates the field-tested concepts of the passive flux meter to provide direct in situ measures of flux for uranium and groundwater in porous media. Measurable contaminant fluxes [J] are essentially the product of concentration [C] and groundwater flux or specific discharge [q ]. The sensor measures [J] and [q] by changes in contaminant and tracer amounts respectively on a sorbent. By using measurement rather than inference from static parameters, the sensor can directly advance conceptual and computational models for field scale simulations. The sensor was deployed in conjunction with DOE in obtaining field-scale quantification of subsurface processes affecting uranium transport (e.g., advection) and transformation (e.g., uranium attenuation) at the Rifle IFRC Site in Rifle, Colorado. Project results have expanded our current understanding of how field-scale spatial variations in fluxes of uranium, groundwater and salient electron donor/acceptors are coupled to spatial variations in measured microbial biomass/community composition, effective field-scale uranium mass balances, attenuation, and stability. The coupling between uranium, various nutrients and micro flora can be used to estimate field-scale rates of uranium attenuation and field-scale transitions in microbial communities. This research focuses on uranium (VI), but the sensor principles and design are applicable to field-scale fate and transport of other radionuclides. Laboratory studies focused on sorbent selection and calibration, along with sensor development and validation under controlled conditions. Field studies were conducted at the Rifle IFRC Site in Rifle, Colorado. These studies were closely coordinated with existing SBR (formerly ERSP) projects to complement data collection. Small field tests were conducted during the first two years that focused on evaluating field-scale deployment procedures and validating sensor performance under controlled field conditions. In the third and fourth year a suite of larger field studies were conducted. For these studies, the uranium flux sensor was used with uranium speciation measurements and molecular-biological tools to characterize microbial community and active biomass at synonymous wells distributed in a large grid. These field efforts quantified spatial changes in uranium flux and field-scale rates of uranium attenuation (ambient and stimulated), uranium stability, and quantitatively assessed how fluxes and effective reaction rates were coupled to spatial variations in microbial community and active biomass. Analyses of data from these field experiments were used to generate estimates of Monod kinetic parameters that are effective in nature and optimal for modeling uranium fate and transport at the field-scale. This project provided the opportunity to develop the first sensor that provides direct measures of both uranium (VI) and groundwater flux. A multidisciplinary team was assembled to include two geochemists, a microbiologist, and two quantitative contaminant hydrologists. Now that the project is complete, the sensor can be deployed at DOE sites to evaluate field-scale uranium attenuation, source behavior, the efficacy of remediation, and off-site risk. Because the sensor requires no power, it can be deployed at remote sites for periods of days to months. The fundamental science derived from this project can be used to advance the development of predictive models for various transport and attenuation processes in aquifers. Proper development of these models is critical for long-term stewardship of contaminated sites in the context of predicting uranium source behavior, remediation performance, and off-site risk.

  16. Industries & Technologies | Department of Energy

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

    Information Resources » Industries & Technologies Industries & Technologies The Advanced Manufacturing Office (AMO) emphasizes innovative technologies to increase manufacturing agility and open new markets. AMO also maintains a range of projects, analyses, protocols, and strategies to reduce industrial energy intensity and carbon emissions in specific industries and technology areas: Industries Aluminum Chemicals Forest Products Glass Metal Casting Mining Other Industries Petroleum

  17. Uranium Biomineralization by Natural Microbial Phosphatase Activities in the Subsurface

    SciTech Connect (OSTI)

    Sobecky, Patricia A.

    2015-04-06

    In this project, inter-disciplinary research activities were conducted in collaboration among investigators at The University of Alabama (UA), Georgia Institute of Technology (GT), Lawrence Berkeley National Laboratory (LBNL), Brookhaven National Laboratory (BNL), the DOE Joint Genome Institute (JGI), and the Stanford Synchrotron Radiation Light source (SSRL) to: (i) confirm that phosphatase activities of subsurface bacteria in Area 2 and 3 from the Oak Ridge Field Research Center result in solid U-phosphate precipitation in aerobic and anaerobic conditions; (ii) investigate the eventual competition between uranium biomineralization via U-phosphate precipitation and uranium bioreduction; (iii) determine subsurface microbial community structure changes of Area 2 soils following organophosphate amendments; (iv) obtain the complete genome sequences of the Rahnella sp. Y9-602 and the type-strain Rahnella aquatilis ATCC 33071 isolated from these soils; (v) determine if polyphosphate accumulation and phytate hydrolysis can be used to promote U(VI) biomineralization in subsurface sediments; (vi) characterize the effect of uranium on phytate hydrolysis by a new microorganism isolated from uranium-contaminated sediments; (vii) utilize positron-emission tomography to label and track metabolically-active bacteria in soil columns, and (viii) study the stability of the uranium phosphate mineral product. Microarray analyses and mineral precipitation characterizations were conducted in collaboration with DOE SBR-funded investigators at LBNL. Thus, microbial phosphorus metabolism has been shown to have a contributing role to uranium immobilization in the subsurface.

  18. 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

  19. Everbrite Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Everbrite Industries Inc. Place: Toronto, Ontario, Canada Zip: M1R 2T6 Sector: Solar Product: Everbrite Industries is an electrical contractor...

  20. Angelantoni Industrie Spa | Open Energy Information

    Open Energy Info (EERE)

    Angelantoni Industrie Spa Jump to: navigation, search Name: Angelantoni Industrie Spa Place: Massa Martana, Italy Zip: 6056 Sector: Renewable Energy Product: String representation...

  1. Goat Industries Fuels | Open Energy Information

    Open Energy Info (EERE)

    Industries Fuels Jump to: navigation, search Name: Goat Industries Fuels Place: Gwynedd, Wales, United Kingdom Zip: LL56 4PZ Product: Welsh manufacturer of biodiesel equipment that...

  2. Integrated Biodiesel Industries Ltd | Open Energy Information

    Open Energy Info (EERE)

    Industries Ltd Jump to: navigation, search Name: Integrated Biodiesel Industries Ltd Place: Sao Paulo, Sao Paulo, Brazil Zip: 01418-200 Product: Sao Paulo-based biodiesel producer....

  3. Guardian Industries Corp | Open Energy Information

    Open Energy Info (EERE)

    Industries Corp Jump to: navigation, search Name: Guardian Industries Corp Place: Auburn Hills, Michigan Zip: 48326-1714 Sector: Solar Product: Michigan-based firm that...

  4. Solventus Industrial SL | Open Energy Information

    Open Energy Info (EERE)

    Name: Solventus Industrial SL Place: Alczar de San Juan, Spain Zip: 13600 Product: Spanish project developer and engineering. References: Solventus Industrial SL1 This...

  5. Hebei Huazheng Industry | Open Energy Information

    Open Energy Info (EERE)

    Hebei Province, China Zip: 53500 Product: Hebei Huazheng Industry manufactures electrical semiconductor devices. References: Hebei Huazheng Industry1 This article is a stub. You...

  6. CRV industrial Ltda | Open Energy Information

    Open Energy Info (EERE)

    CRV industrial Ltda Jump to: navigation, search Name: CRV industrial Ltda Place: Carmo do Rio Verde, Goias, Brazil Sector: Biomass Product: Ethanol and biomass energy producer...

  7. Yusheng Industrial Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Yusheng Industrial Co Ltd Jump to: navigation, search Name: Yusheng Industrial Co., Ltd Place: Hunan Province, China Zip: 415000 Sector: Hydro Product: Hunan-based small hydro...

  8. Aditya Solar Power Industries | Open Energy Information

    Open Energy Info (EERE)

    Aditya Solar Power Industries Jump to: navigation, search Name: Aditya Solar Power Industries Place: India Sector: Solar Product: Bangalore-based solar project developer....

  9. Clean Technology Sustainable Industries Organization | Open Energy...

    Open Energy Info (EERE)

    Sustainable Industries Organization Jump to: navigation, search Name: Clean Technology & Sustainable Industries Organization Place: Royal Oak, Michigan Zip: 48073 Product: A...

  10. Phoenix Bio Industries LLC | Open Energy Information

    Open Energy Info (EERE)

    Bio Industries LLC Jump to: navigation, search Name: Phoenix Bio-Industries LLC Place: Goshen, California Zip: 93227 Product: Ethanol producer. Coordinates: 37.988525,...

  11. AgroIndustrial Capela | Open Energy Information

    Open Energy Info (EERE)

    AgroIndustrial Capela Jump to: navigation, search Name: AgroIndustrial Capela Place: Capela, Sergipe, Brazil Product: Brazil based ethanol producer located in Sergipe, part of...

  12. PAIS Industries Group | Open Energy Information

    Open Energy Info (EERE)

    PAIS Industries Group Jump to: navigation, search Name: PAIS Industries Group Sector: Solar Product: Plans to supply solar-grade silicon, conditional on an agreement with the Inner...

  13. Vikram Group of Industries | Open Energy Information

    Open Energy Info (EERE)

    Vikram Group of Industries Jump to: navigation, search Name: Vikram Group of Industries Place: Kolkatta, West Bengal, India Zip: 700001 Product: Kolkata-based tea processing...

  14. Danish Wind Industry Association | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Danish Wind Industry Association Place: Copenhagen V, Denmark Zip: DK-1552 Sector: Wind energy Product: The Danish Wind Industry Association...

  15. California Solar Energy Industries Association | Open Energy...

    Open Energy Info (EERE)

    Solar Energy Industries Association Jump to: navigation, search Name: California Solar Energy Industries Association Place: Rio Vista, California Zip: 94571 Sector: Solar Product:...

  16. Triangle biofuels Industries | Open Energy Information

    Open Energy Info (EERE)

    Triangle biofuels Industries Jump to: navigation, search Name: Triangle biofuels Industries Place: Iowa Product: Biodiesel producer developing a 19mlpa plant in Johnston, IA....

  17. Agro Industrial Taruma | Open Energy Information

    Open Energy Info (EERE)

    Industrial Taruma Jump to: navigation, search Name: Agro Industrial Taruma Place: Sao Pedro do Turvo, Sao Paulo, Brazil Zip: 18940-000 Product: Brazil based ethanol producer...

  18. South Jersey Industries | Open Energy Information

    Open Energy Info (EERE)

    Jersey Industries Jump to: navigation, search Name: South Jersey Industries Place: Folsom, New Jersey Zip: 8037 Sector: Services Product: An energy services holding company....

  19. Canyon Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    Industries Inc Jump to: navigation, search Name: Canyon Industries Inc Place: Deming, Washington State Zip: 98244 Sector: Hydro Product: Canyon Hydro produces a range of small...

  20. Industrial Assessment Centers Small Manufacturers Reduce Energy...

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

    DOEEE-1278 Industrial Assessment Centers Small Manufacturers Reduce Energy & Increase Productivity Since 1976, the Industrial Assessment Centers (IACs), administered by the US...

  1. Sanyo Chemical Industries | Open Energy Information

    Open Energy Info (EERE)

    Industries Jump to: navigation, search Name: Sanyo Chemical Industries Place: Tokyo, Japan Zip: 103-0023 Product: String representation "Sanyo is a petr ... uction process." is...

  2. Toray Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    Industries Inc Jump to: navigation, search Name: Toray Industries Inc Place: Tokyo, Japan Zip: 103 8666 Sector: Carbon, Vehicles, Wind energy Product: String representation "A...

  3. Millennium Energy Industries | Open Energy Information

    Open Energy Info (EERE)

    Industries Place: Jordan Zip: 1182 Sector: Solar Product: Jordan-based solar energy firm focused in MENA region. References: Millennium Energy Industries1 This article is a...

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

    Broader source: Energy.gov [DOE]

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

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

    DOE Patents [OSTI]

    Friedman, Horace A. (Oak Ridge, TN)

    1985-01-01

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

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

    DOE Patents [OSTI]

    Friedman, H.A.

    1984-06-13

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

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  8. Industrial Users

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

    Industrial Users The facility has been used for more than a decade by a virtual Who's Who of the semiconductor industry to simulate the potential failures posed by cosmic-ray-induced neutrons upon miniature electronic devices, such as chips that help control aircraft or complex integrated circuits in automobiles. Industrial User Information The Neutron and Nuclear Science (WNR) Facility welcomes proposals for beam time experiments from industry users. Proprietary and non-proprietary industrial

  9. Uranium Downblending and Disposition Project Technology Readiness

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

    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

  10. 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)

  11. Domestic Uranium Production Report 2004-13

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

    Thank

  12. 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,...

  13. Uranium Marketing Annual Report -

    Gasoline and Diesel Fuel Update (EIA)

    3. Deliveries of uranium feed by owners and operators of U.S. civilian nuclear power reactors by enrichment country and delivery year, 2012-14 thousand pounds U3O8 equivalent Feed deliveries in 2012 Feed deliveries in 2013 Feed deliveries in 2014 Enrichment country U.S.-origin 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 W W W W 2,140 Netherlands W W 2,674 1,058

  14. PROCESS FOR THE CONCENTRATION OF ORES CONTAINING GOLD AND URANIUM

    DOE Patents [OSTI]

    Gaudin, A.M.; Dasher, J.

    1958-06-10

    ABS>A process is described for concentrating certain low grade uranium and gold bearing ores, in which the gangue is mainly quartz. The production of the concentrate is accomplished by subjecting the crushed ore to a froth floatation process using a fatty acid as a collector in conjunction with a potassium amyl xanthate collector. Pine oil is used as the frothing agent.

  15. Greenline Industries | Open Energy Information

    Open Energy Info (EERE)

    Industries Place: San Rafael, California Zip: 94901 Product: Small to medium scale biodiesel plants designer and producer. They also run a biodiesel plant in Vallejo,...

  16. Jax Industries | Open Energy Information

    Open Energy Info (EERE)

    Jax Industries Place: Hillsboro, Oregon Product: Developer of recharge systems for CZ process silicon ingot growers, some of which produce PV silicon feedstock. Coordinates:...

  17. DOE Announces Transfer of Depleted Uranium to Advance the U.S...

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

    A more detailed description of the project is available HERE. The project will ensure a supply of U.S.-origin unobligated uranium to support the NNSA tritium production for up to ...

  18. Critical experiments with mixed plutonium-uranium nitrate solutions having

    Office of Scientific and Technical Information (OSTI)

    Pu:(Pu + U) ratios greater than 0.5 (Technical Report) | SciTech Connect Critical experiments with mixed plutonium-uranium nitrate solutions having Pu:(Pu + U) ratios greater than 0.5 Citation Details In-Document Search Title: Critical experiments with mixed plutonium-uranium nitrate solutions having Pu:(Pu + U) ratios greater than 0.5 × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical

  19. Method for cleaning bomb-reduced uranium derbies

    DOE Patents [OSTI]

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

    1981-01-01

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

  20. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Deliveries 2010 2011 2012 2013 2014 Purchases of U.S.-origin and foreign-origin uranium 350 550 W W W Weighted-average price 47.13 58.12 W W W Purchases of U.S.-origin and foreign-origin uranium 11,745 14,778 11,545 12,835 17,111 Weighted-average price 44.98 53.29 54.44 50.44 42.90 Purchases 0 0 0 0 0 Weighted-average price -- -- -- -- -- Purchases of U.S.-origin and

  1. 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...

  2. 2014 Uranium Marketing Annual Report

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

    9 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Annual Cumulative Annual Cumulative 2014 2,494 2,494 - -- 2015 6,014 8,507 3,496 3,496 ...

  3. 2014 Uranium Marketing Annual Report

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

    1 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand pounds U 3 O 8 equivalent U.S.-origin Foreign- origin Total U.S.-origin ...

  4. 2014 Uranium Marketing Annual Report

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

    9 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Deliveries to foreign suppliers and utilities 2010 2011 2012 2013 2014 Foreign sales ...

  5. 2014 Uranium Marketing Annual Report

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

    9 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand pounds U 3 O 8 equivalent; dollars per pound U 3 O 8 equivalent Deliveries ...

  6. 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.

  7. Laser induced phosphorescence uranium analysis

    DOE Patents [OSTI]

    Bushaw, Bruce A. (Kennewick, WA)

    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.

  8. Uranium Elemental and Isotopic Constraints on Groundwater Flow Beneath the Nopal I Uranium Deposit, Pena Blanca, Mexico

    SciTech Connect (OSTI)

    S.J. Goldstein; M.T. Murrell; A.M. Simmons

    2005-07-11

    The Nopal I uranium deposit in Chihuahua, Mexico, is an excellent analogue for evaluating the fate of spent fuel, associated actinides, and fission products over long time scales for the proposed Yucca Mountain high-level nuclear waste repository. In 2003, three groundwater wells were drilled directly adjacent to (PB-1) and 50 m on either side of the uranium deposit (PB-2 and PB-3) in order to evaluate uranium-series transport in three dimensions. After drilling, uranium concentrations were elevated in all of the three wells (0.1-18 ppm) due to drilling activities and subsequently decreased to {approx}5-20% of initial values over the next several months. The {sup 234}U/{sup 238}U activity ratios were similar for PB-1 and PB-2 (1.005 to 1.079) but distinct for PB-3 (1.36 to 1.83) over this time period, suggesting limited mixing between groundwater from these wells over these short time and length scales. Regional groundwater wells located up to several km from the deposit also have distinct uranium isotopic characteristics and constrain mixing over larger length and time scales. We model the decreasing uranium concentrations in the newly drilled wells with a simple one-dimensional advection-dispersion model, assuming uranium is introduced as a slug to each of the wells and transported as a conservative tracer. Using this model for our data, the relative uranium concentrations are dependent on both the longitudinal dispersion as well as the mean groundwater flow velocity. These parameters have been found to be correlated in both laboratory and field studies of groundwater velocity and dispersion (Klotz et al., 1980). Using typical relationships between velocity and dispersion for field and laboratory studies along with the relationship observed from our uranium data, both velocity (1-10 n/yr) and dispersion coefficient (1E-5 to 1E-2 cm{sup 2}/s) can be derived from the modeling. As discussed above, these relatively small flow velocities and dispersivities agree with mixing considerations derived from the {sup 234}U/{sup 238}U data. While these results and the limited productivity of these wells consistently suggest limited groundwater flow and mixing, we anticipate additional work with artificial tracers to better establish groundwater flow velocities and gradient at this site.

  9. Uranium chloride extraction of transuranium elements from LWR fuel

    DOE Patents [OSTI]

    Miller, William E.; Ackerman, John P.; Battles, James E.; Johnson, Terry R.; Pierce, R. Dean

    1992-01-01

    A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.

  10. Uranium chloride extraction of transuranium elements from LWR fuel

    DOE Patents [OSTI]

    Miller, W.E.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Pierce, R.D.

    1992-08-25

    A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800 C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein. 1 figure.

  11. 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.

  12. Industrial Scale Demonstration of Smart Manufacturing Achieving...

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

    Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Industrial Scale Demonstration of Smart Manufacturing Achieving Transformational...

  13. Ashkelon Technological Industries ATI | Open Energy Information

    Open Energy Info (EERE)

    Ashkelon Technological Industries (ATI) Place: Israel Sector: Services Product: General Financial & Legal Services ( Government Public sector ) References: Ashkelon...

  14. RESULTS OF THE TECHNICAL AND ECONOMIC FEASIBILITY ANALYSIS FOR A NOVEL BIOMASS GASIFICATION-BASED POWER GENERATION SYSTEM FOR THE FOREST PRODUCTS INDUSTRY

    SciTech Connect (OSTI)

    Bruce Bryan; Joseph Rabovitser; Sunil Ghose; Jim Patel

    2003-11-01

    In 2001, the Gas Technology Institute (GTI) entered into Cooperative Agreement DE-FC26-01NT41108 with the U.S. Department of Energy (DOE) for an Agenda 2020 project to develop an advanced biomass gasification-based power generation system for near-term deployment in the Forest Products Industry (FPI). The advanced power system combines three advanced components, including biomass gasification, 3-stage stoker-fired combustion for biomass conversion, and externally recuperated gas turbines (ERGTs) for power generation. The primary performance goals for the advanced power system are to provide increased self-generated power production for the mill and to increase wastewood utilization while decreasing fossil fuel use. Additional goals are to reduce boiler NOx and CO{sub 2} emissions. The current study was conducted to determine the technical and economic feasibility of an Advanced Power Generation System capable of meeting these goals so that a capital investment decision can be made regarding its implementation at a paper mill demonstration site in DeRidder, LA. Preliminary designs and cost estimates were developed for all major equipment, boiler modifications and balance of plant requirements including all utilities required for the project. A three-step implementation plan was developed to reduce technology risk. The plant design was found to meet the primary objectives of the project for increased bark utilization, decreased fossil fuel use, and increased self-generated power in the mill. Bark utilization for the modified plant is significantly higher (90-130%) than current operation compared to the 50% design goal. For equivalent steam production, the total gas usage for the fully implemented plant is 29% lower than current operation. While the current average steam production from No.2 Boiler is about 213,000 lb/h, the total steam production from the modified plant is 379,000 lb/h. This steam production increase will be accomplished at a grate heat release rate (GHRR) equal to the original boiler design. Boiler efficiencies (cogeneration-steam plus air) is increased from the original design value of 70% to 78.9% due to a combination of improved burnout, operation with lower excess air, and drier fuel. For the fully implemented plant, the thermal efficiency of fuel to electricity conversion is 79.8% in the cogeneration mode, 5% above the design goal. Finally, self-generated electricity will be increased from the 10.8 MW currently attributable to No.2 Boiler to 46.7MW, an increase of 332%. Environmental benefits derived from the system include a reduction in NOx emissions from the boiler of about 30-50% (90-130 tons/year) through syngas reburning, improved carbon burnout and lower excess air. This does not count NOx reduction that may be associated with replacement of purchased electricity. The project would reduce CO{sub 2} emissions from the generation of electricity to meet the mill's power requirements, including 50,000 tons/yr from a net reduction in gas usage in the mill and an additional 410,000 tons/yr reduction in CO{sub 2} emissions due to a 34 MW reduction of purchased electricity. The total CO{sub 2} reduction amounts to about 33% of the CO{sub 2} currently generated to meet the mills electricity requirement. The overall conclusion of the study is that while significant engineering challenges are presented by the proposed system, they can be met with operationally acceptable and cost effective solutions. The benefits of the system can be realized in an economic manner, with a simple payback period on the order of 6 years. The results of the study are applicable to many paper mills in the U.S. firing woodwastes and other solid fuels for steam and power production.

  15. An Industry/DOE Program to Develop and Benchmark Advanced Diamond Product Drill Bits and HP/HT Drilling Fluids to Significantly Improve Rates of Penetration

    SciTech Connect (OSTI)

    TerraTek

    2007-06-30

    A deep drilling research program titled 'An Industry/DOE Program to Develop and Benchmark Advanced Diamond Product Drill Bits and HP/HT Drilling Fluids to Significantly Improve Rates of Penetration' was conducted at TerraTek's Drilling and Completions Laboratory. Drilling tests were run to simulate deep drilling by using high bore pressures and high confining and overburden stresses. The purpose of this testing was to gain insight into practices that would improve rates of penetration and mechanical specific energy while drilling under high pressure conditions. Thirty-seven test series were run utilizing a variety of drilling parameters which allowed analysis of the performance of drill bits and drilling fluids. Five different drill bit types or styles were tested: four-bladed polycrystalline diamond compact (PDC), 7-bladed PDC in regular and long profile, roller-cone, and impregnated. There were three different rock types used to simulate deep formations: Mancos shale, Carthage marble, and Crab Orchard sandstone. The testing also analyzed various drilling fluids and the extent to which they improved drilling. The PDC drill bits provided the best performance overall. The impregnated and tungsten carbide insert roller-cone drill bits performed poorly under the conditions chosen. The cesium formate drilling fluid outperformed all other drilling muds when drilling in the Carthage marble and Mancos shale with PDC drill bits. The oil base drilling fluid with manganese tetroxide weighting material provided the best performance when drilling the Crab Orchard sandstone.

  16. 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)

  17. Nuclear forensic analysis of uranium oxide powders interdicted in Victoria, Australia

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

    Kristo, Michael Joseph; Keegan, Elizabeth; Colella, Michael; Williams, Ross; Lindvall, Rachel; Eppich, Gary; Roberts, Sarah; Borg, Lars; Gaffney, Amy; Plaue, Jonathan; et al

    2015-04-13

    Nuclear forensic analysis was conducted on two uranium samples confiscated during a police investigation in Victoria, Australia. The first sample, designated NSR-F-270409-1, was a depleted uranium powder of moderate purity (~1000 μg/g total elemental impurities). The chemical form of the uranium was a compound similar to K2(UO2)3O4·4H2O. While aliquoting NSR-F-270409-1 for analysis, the body and head of a Tineid moth was discovered in the sample. The second sample, designated NSR-F-270409-2, was also a depleted uranium powder. It was of reasonably high purity (~380 μg/g total elemental impurities). The chemical form of the uranium was primarily UO3·2H2O, with minor phases ofmore » U3O8 and UO2. While aliquoting NSR-F-270409-2 for analysis, a metal staple of unknown origin was discovered in the sample. The presence of 236U and 232U in both samples indicates that the uranium feed stocks for these samples experienced a neutron flux at some point in their history. The reactor burn-up calculated from the isotopic composition of the uranium is consistent with that of spent fuel from natural uranium (NU) fueled Pu production. These nuclear forensic conclusions allow us to categorically exclude Australia as the origin of the material and greatly reduce the number of candidate sources.« less

  18. Nuclear reactor fuel structure containing uranium alloy wires embedded in a metallic matrix plate

    DOE Patents [OSTI]

    Travelli, A.

    1985-10-25

    A flat or curved plate structure, to be used as fuel in a nuclear reactor, comprises elongated fissionable wires or strips embedded in a metallic continuous non-fissionable matrix plate. The wires or strips are made predominantly of a malleable uranium alloy, such as uranium silicide, uranium gallide or uranium germanide. The matrix plate is made predominantly of aluminum or an aluminum alloy. The wires or strips are located in a single row at the midsurface of the plate, parallel with one another and with the length dimension of the plate. The wires or strips are separated from each other, and from the surface of the plate, by sufficient thicknesses of matrix material, to provide structural integrity and effective fission product retention, under neutron irradiation. This construction makes it safely feasible to provide a high uranium density, so that the uranium enrichment with uranium 235 may be reduced below about 20%, to deter the reprocessing of the uranium for use in nuclear weapons.

  19. Nuclear reactor fuel structure containing uranium alloy wires embedded in a metallic matrix plate

    DOE Patents [OSTI]

    Travelli, Armando

    1988-01-01

    A flat or curved plate structure, to be used as fuel in a nuclear reactor, comprises elongated fissionable wires or strips embedded in a metallic continuous non-fissionable matrix plate. The wires or strips are made predominantly of a malleable uranium alloy, such as uranium silicide, uranium gallide or uranium germanide. The matrix plate is made predominantly of aluminum or an aluminum alloy. The wires or strips are located in a single row at the midsurface of the plate, parallel with one another and with the length dimension of the plate. The wires or strips are separated from each other, and from the surface of the plate, by sufficient thicknesses of matrix material, to provide structural integrity and effective fission product retention, under neutron irradiation. This construction makes it safely feasible to provide a high uranium density, so that the uranium enrichment with uranium 235 may be reduced below about 20%, to deter the reprocessing of the uranium for use in nuclear weapons.

  20. Compact reaction cell for homogenizing and down-blending highly enriched uranium metal

    DOE Patents [OSTI]

    McLean, W. II; Miller, P.E.; Horton, J.A.

    1995-05-02

    The invention is a specialized reaction cell for converting uranium metal to uranium oxide. In a preferred form, the reaction cell comprises a reaction chamber with increasing diameter along its length (e.g. a cylindrical chamber having a diameter of about 2 inches in a lower portion and having a diameter of from about 4 to about 12 inches in an upper portion). Such dimensions are important to achieve the necessary conversion while at the same time affording criticality control and transportability of the cell and product. The reaction chamber further comprises an upper port and a lower port, the lower port allowing for the entry of reactant gases into the reaction chamber, the upper port allowing for the exit of gases from the reaction chamber. A diffuser plate is attached to the lower port of the reaction chamber and serves to shape the flow of gas into the reaction chamber. The reaction cell further comprises means for introducing gases into the reaction chamber and a heating means capable of heating the contents of the reaction chamber. The present invention also relates to a method for converting uranium metal to uranium oxide in the reaction cell of the present invention. The invention is useful for down-blending highly enriched uranium metal by the simultaneous conversion of highly enriched uranium metal and natural or depleted uranium metal to uranium oxide within the reaction cell. 4 figs.

  1. Compact reaction cell for homogenizing and down-blanding highly enriched uranium metal

    DOE Patents [OSTI]

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

    1995-01-01

    The invention is a specialized reaction cell for converting uranium metal to uranium oxide. In a preferred form, the reaction cell comprises a reaction chamber with increasing diameter along its length (e.g. a cylindrical chamber having a diameter of about 2 inches in a lower portion and having a diameter of from about 4 to about 12 inches in an upper portion). Such dimensions are important to achieve the necessary conversion while at the same time affording criticality control and transportability of the cell and product. The reaction chamber further comprises an upper port and a lower port, the lower port allowing for the entry of reactant gasses into the reaction chamber, the upper port allowing for the exit of gasses from the reaction chamber. A diffuser plate is attached to the lower port of the reaction chamber and serves to shape the flow of gas into the reaction chamber. The reaction cell further comprises means for introducing gasses into the reaction chamber and a heating means capable of heating the contents of the reaction chamber. The present invention also relates to a method for converting uranium metal to uranium oxide in the reaction cell of the present invention. The invention is useful for down-blending highly enriched uranium metal by the simultaneous conversion of highly enriched uranium metal and natural or depleted uranium metal to uranium oxide within the reaction cell.

  2. Natural Gas Industrial Price

    Gasoline and Diesel Fuel Update (EIA)

    Citygate Price Residential Price Commercial Price Industrial Price Electric Power Price Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Gas in Underground

  3. Small cell experiments for electrolytic reduction of uranium oxides to uranium metal using fluoride salts

    SciTech Connect (OSTI)

    Haas, P.A.; Adcock, P.W.; Coroneos, A.C.; Hendrix, D.E. )

    1994-08-01

    Electrolytic reduction of uranium oxide was proposed for the preparation of uranium metal feed for the atomic vapor laser isotope separation (AVLIS) process. A laboratory cell of 25-cm ID was operated to obtain additional information in areas important to design and operation of a pilot plant cell. Reproducible test results and useful operating and control procedures were demonstrated. About 20 kg of uranium metal of acceptable purity were prepared. A good supply of dissolved UO[sub 2] feed at the anode is the most important controlling requirement for efficient cell operation. A large fraction of the cell current is nonproductive in that it does not produce a metal product nor consume carbon anodes. All useful test conditions gave some reduction of UF[sub 4] to produce CF[sub 4] in addition to the reduction of UO[sub 2], but the fraction of metal from the reduction of UF[sub 4] can be decreased by increasing the concentration of dissolved UO[sub 2]. Operation of large continuous cells would probably be limited to current efficiencies of less than 60 pct, and more than 20 pct of the metal would result from the reduction of UF[sub 4].

  4. Solar Night Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    St Louis, Missouri Zip: 63147 Product: Manufacturer and distributor of products which store energy by day and release it by night. References: Solar Night Industries Inc1 This...

  5. 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

  6. Industry Economists

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

    Industry Economists The U.S. Energy Information Administration (EIA) within the Department of Energy has forged a world-class information program that stresses quality, teamwork, and employee growth. In support of our program, we offer a variety of profes- sional positions, including the Industry Economist, whose work is associated with the performance of economic analyses using economic techniques. Responsibilities: Industry Economists perform or participate in one or more of the following

  7. Performance Assessment Transport Modeling of Uranium at the Area 5 Radioactive Waste Management Site at the Nevada National Security Site

    SciTech Connect (OSTI)

    NSTec Radioactive Waste

    2010-10-12

    Following is a brief summary of the assumptions that are pertinent to the radioactive isotope transport in the GoldSim Performance Assessment model of the Area 5 Radioactive Waste Management Site, with special emphasis on the water-phase reactive transport of uranium, which includes depleted uranium products.

  8. 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...

  9. 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.

  10. Monthly Biodiesel Production Report

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

    U.S. Biodiesel production capacity and production million gallons Period Annual Production ... B100 is the industry designation for pure biodiesel; a biodiesel blend contains both pure ...

  11. Uranium Biomineralization By Natural Microbial Phosphatase Activities...

    Office of Scientific and Technical Information (OSTI)

    Uranium Biomineralization By Natural Microbial Phosphatase Activities in the Subsurface ... Country of Publication: United States Language: English Subject: 54 ENVIRONMENTAL ...

  12. 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

  13. 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.

  14. 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.

  15. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand pounds U 3 O 8 equivalent 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 (U 3 O 8 ) 13,076 14,718 15,963 18,131 20,501 Natural UF 6 35,767 35,883 29,084 38,332 40,972 Enriched UF 6 25,392 19,596 38,428 40,841

  16. High strength uranium-tungsten alloys

    DOE Patents [OSTI]

    Dunn, Paul S. (Santa Fe, NM); Sheinberg, Haskell (Los Alamos, NM); Hogan, Billy M. (Los Alamos, NM); Lewis, Homer D. (Bayfield, CO); Dickinson, James M. (Los Alamos, NM)

    1991-01-01

    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.

  17. High strength uranium-tungsten alloy process

    DOE Patents [OSTI]

    Dunn, Paul S. (Santa Fe, NM); Sheinberg, Haskell (Los Alamos, NM); Hogan, Billy M. (Los Alamos, NM); Lewis, Homer D. (Bayfield, CO); Dickinson, James M. (Los Alamos, NM)

    1990-01-01

    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.

  18. 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

  19. 2014 Uranium Market Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 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 Table 8. Contracts signed in 2014 by owners and operators of U.S. civilian nuclear power reactors by contract type thousand

  20. 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.

  1. The methanol industry`s missed opportunities

    SciTech Connect (OSTI)

    Stokes, C.A.

    1995-12-31

    Throughout its history the methanol industry has been backward in research and development and in industry cooperation on public image and regulatory matters. It has been extremely reticent as to the virtue of its product for new uses, especially for motor fuel. While this is perhaps understandable looking back, it is inexcusable looking forward. The industry needs to cooperate on a worldwide basis in research and market development, on the one hand, and in image-building and political influence, on the other, staying, of course, within the US and European and other regional antitrust regulations. Unless the industry develops the motor fuel market, and especially the exciting new approach through fuel cell operated EVs, to siphon off incremental capacity and keep plants running at 90% or more of capacity, it will continue to live in a price roller-coaster climate. A few low-cost producers will do reasonably well and the rest will just get along or drop out here and there along the way, as in the past. Having come so far from such a humble beginning, it is a shame not to realize the full potential that is clearly there: a potential to nearly double sales dollars without new plants and to produce from a plentiful resource, at least for the next half-century, all the methanol that can be imagined to be needed. Beyond that the industry can turn to renewable energy--the sun--via biomass growth, to make their product. In so doing, it can perhaps apply methanol as a plant growth stimulant, in effect making the product fully self-sustainable. The world needs to know what methanol can do to provide--economically and reliably--the things upon which a better life rests.

  2. Uranium-233 purification and conversion to stabilized ceramic grade urania for LWBR fuel fabrication (LWBR Development Program)

    SciTech Connect (OSTI)

    Lloyd, R.

    1980-10-01

    High purity ceramic grade urania (/sup 233/UO/sub 2/) used in manufacturing the fuel for the Light Water Breeder Reactor (LWBR) core was made from uranium-233 that was obtained by irradiating thoria under special conditions to result in not more than 10 ppM of uranium-232 in the recovered uranium-233 product. A developmental study established the operating parameters of the conversion process for transforming the uranium-233 into urania powder with the appropriate chemical and physical attributes for use in fabricating the LWBR core fuel. This developmental study included the following: (a) design of an ion exchange purification process for removing the gamma-emitting alpha-decay daughters of uranium-232, to reduce the gamma-radiation field of the uranium-233 during LWBR fuel manufacture; (b) definition of the parameters for precipitating the uranium-233 as ammonium uranate (ADU) and for reducing the ADU with hydrogen to yield a urania conversion product of the proper particle size, surface area and sinterability for use in manufacturing the LWBR fuel; (c) establishment of parameters and design of equipment for stabilizing the urania conversion product to prevent it from undergoing excessive oxidation on exposure to the air during LWBR fuel manufacturing operations; and (d) development of a procedure and a facility to reprocess the unirradiated thoria-urania fuel scrap from the LWBR core manufacturing operations to recover the uranium-233 and convert it into high purity ceramic grade urania for LWBR core fabrication.

  3. 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.

  4. Chemicals Industry Profile | Department of Energy

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

    Chemicals Industry Profile Chemicals Industry Profile Chemical products are essential to the production of a myriad of manufactured products. More than 96% of all manufactured goods are directly touched by the chemicals industry.1 The industry greatly influences our safe water supply, food, shelter, clothing, health care, computer technology, transportation, and almost every other facet of modern life. Economic The United States is the top chemical producer in the world, accounting for nearly

  5. 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 × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product

  6. 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.

  7. Kr Ion Irradiation Study of the Depleted-Uranium Alloys

    SciTech Connect (OSTI)

    J. Gan; D. Keiser; B. Miller; M. Kirk; J. Rest; T. Allen; D. Wachs

    2010-12-01

    Fuel development for the Reduced Enrichment Research and Test Reactor program is tasked with the development of new low-enriched uranium nuclear fuels that can be employed to replace existing highly enriched uranium fuels currently used in some research reactors throughout the world. For dispersion-type fuels, radiation stability of the fuel/cladding interaction product has a strong impact on fuel performance. Three depleted uranium alloys are cast for the radiation stability studies of the fuel/cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Si, Al)3, (U, Mo)(Si, Al)3, UMo2Al20, U6Mo4Al43, and UAl4. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200C to ion doses up to 2.5 1015 ions/cm2 (~ 10 dpa) with an Kr ion flux of 1012 ions/cm2-sec (~ 4.0 10-3 dpa/sec). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

  8. 2014 Uranium Marketing Annual Report

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

    7 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Year of delivery Minimum Maximum 2015 2,838 2,838 2016 3,573 3,573 2017 2,718 2,818 ...

  9. Supporting industries energy and environmental profile

    SciTech Connect (OSTI)

    None, None

    2005-09-21

    As part of its Industries of the Future strategy, the Industrial Technologies Program within the U.S. Department of Energys (DOE) Office of Energy Efficiency and Renewable Energy works with energy-intensive industries to improve efficiency, reduce waste, and increase productivity. These seven Industries of the Future (IOFs) aluminum, chemicals, forest products, glass, metal casting, mining, and steel rely on several other so-called supporting industries to supply materials and processes necessary to the products that the IOFs create. The supporting industries, in many cases, also provide great opportunities for realizing energy efficiency gains in IOF processes.

  10. Process for producing an aggregate suitable for inclusion into a radiation shielding product

    DOE Patents [OSTI]

    Lessing, Paul A. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID)

    2000-01-01

    The present invention is directed to methods for converting depleted uranium hexafluoride to a stable depleted uranium silicide in a one-step reaction. Uranium silicide provides a stable aggregate material that can be added to concrete to increase the density of the concrete and, consequently, shield gamma radiation. As used herein, the term "uranium silicide" is defined as a compound generically having the formula U.sub.x Si.sub.y, wherein the x represents the molecules of uranium and the y represent the molecules of silicon. In accordance with the present invention, uranium hexafluoride is converted to a uranium silicide by contacting the uranium hexafluoride with a silicon-containing material at a temperature in a range between about 1450.degree. C. and about 1750.degree. C. The stable depleted uranium silicide is included as an aggregate in a radiation shielding product, such as a concrete product.

  11. Production plant separator system conceptual design

    SciTech Connect (OSTI)

    Ng, E.; Kan, T.

    1994-12-31

    A full conceptual design has been completed for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant capable of producing {approximately}1700 metric tons of enriched uranium per year (MTU/y). This plant is the first step in the deployment of AVLIS enrichment technology, which will provide inexpensive, dependable, and environmentally safe uranium enrichment services to utility customers. Previous issues of the ISAM Semiannual Report describe other major systems in the plant, namely the laser, feed and product systems. This article describes the design of the separator system. The separator system is a a key component in the plant. After the feed conversion system converts uranium trioxide (UO{sub 3}) to a uranium-iron alloy, the alloy enters the separator system. In the separator, and intense electron beam vaporizes uranium metal in a vacuum chamber. In the laser system, fixed-frequency copper-vapor lasers pump tunable dye lasers. These precisely tuned dye lasers then selectively excite and ionize uranium-235 atoms in the vapor stream, leaving the uranium-238 atoms untouched. The photo-ions of uranium-235 are then drawn to an electrically biased collector, producing the enriched product stream. The remaining vapor flows through, producing the depleted tails stream. Both product and tails streams are continuously removed from the separator pod as flowing liquid uranium metal. Withdrawal containers are used to collect separately the enriched and depleted uranium. The enriched product will be converted by fuel fabricators to uranium dioxide (UO{sub 2}) and used to fabricate reactor fuel assemblies for utility customers.

  12. 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...

  13. Industry @ ALS

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

    Industry @ ALS Industry @ ALS ALS, Molecular Foundry, and aBeam Technologies Collaborate to Make Metrology History Print Thursday, 21 January 2016 12:47 A collaboration between Bay Area company aBeam Technologies, the ALS, and the Molecular Foundry is bringing cutting-edge metrology instrumentation to the semiconductor market, which will enable a new level of quality control. Summary Slide Read more... Takeda Advances Diabetes Drug Development at the ALS Print Tuesday, 19 May 2015 12:25 Type 2

  14. 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 Earths 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 Earths 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.

  15. 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

  16. Industry Partners Panel

    Broader source: Energy.gov [DOE]

    Industry Panel presenters include: Michael G. Andrew, Director - Academic and Technical Programs, Advanced Products and Materials, Johnson Controls Power Solutions Michael A. Fetcenko, Vice President and Managing Director, BASF Battery Materials – Ovonic, BASF Corporation Adam Kahn, Founder and CEO, AKHAN Technologies, Inc. Stephen E. Zimmer, Executive Director, United States Council for Automotive Research (USCAR)

  17. US developments in technology for uranium enrichment

    SciTech Connect (OSTI)

    Wilcox, W.J. Jr.; McGill, R.M.

    1982-01-01

    The purpose of this paper is to review recent progress and the status of the work in the United States on that part of the fuel cycle concerned with uranium enrichment. The United States has one enrichment process, gaseous diffusion, which has been continuously operated in large-scale production for the past 37 years; another process, gas centrifugation, which is now in the construction phase; and three new processes, molecular laser isotope separation, atomic vapor laser isotope separation, plasma separation process, in which the US has also invested sizable research and development efforts over the last few years. The emphasis in this paper is on the technical aspects of the various processes, but the important economic factors which will define the technological mix which may be applied in the next two decades are also discussed.

  18. Directory of Tennessee's forest industries 1980

    SciTech Connect (OSTI)

    Not Available

    1980-09-01

    A directory of primary and secondary forest industries is presented. Firm names and addresses are listed by county in alphabetical order. The following information is listed for each industry: type of plant, production and employee size class, products manufactured, and equipment. For the primary industries, the major species of trees used are listed. (MHR)

  19. NNSA Production Office more than doubles Feds Feed Families campaign...

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

    fund CNS supports Tenn. Science Bowl CNS helps provide housing to homeless veterans Robbins named NNSA Production Office Deputy Manager Uranium project achieves safety milestone...

  20. Niowave Develops Production Route for Medical Radioisotopes with...

    Office of Science (SC) Website

    ... In addition to creating high-tech domestic jobs, this new production technique reduces nuclear proliferation concerns by eliminating the use of weapons grade uranium for producing ...

  1. Laser Isotope Enrichment for Medical and Industrial Applications

    SciTech Connect (OSTI)

    Leonard Bond

    2006-07-01

    Laser Isotope Enrichment for Medical and Industrial Applications by Jeff Eerkens (University of Missouri), Jay Kunze (Idaho State University), and Leonard Bond (Idaho National Laboratory) The principal isotope enrichment business in the world is the enrichment of uranium for commercial power reactor fuels. However, there are a number of other needs for separated isotopes. Some examples are: 1) Pure isotopic targets for irradiation to produce medical radioisotopes. 2) Pure isotopes for semiconductors. 3) Low neutron capture isotopes for various uses in nuclear reactors. 4) Isotopes for industrial tracer/identification applications. Examples of interest to medicine are targets to produce radio-isotopes such as S-33, Mo-98, Mo-100, W-186, Sn-112; while for MRI diagnostics, the non-radioactive Xe-129 isotope is wanted. For super-semiconductor applications some desired industrial isotopes are Si-28, Ga-69, Ge-74, Se-80, Te-128, etc. An example of a low cross section isotope for use in reactors is Zn-68 as a corrosion inhibitor material in nuclear reactor primary systems. Neutron activation of Ar isotopes is of interest in industrial tracer and diagnostic applications (e.g. oil-logging). . In the past few years there has been a sufficient supply of isotopes in common demand, because of huge Russian stockpiles produced with old electromagnetic and centrifuge separators previously used for uranium enrichment. Production of specialized isotopes in the USA has been largely accomplished using old calutrons (electromagnetic separators) at Oak Ridge National Laboratory. These methods of separating isotopes are rather energy inefficient. Use of lasers for isotope separation has been considered for many decades. None of the proposed methods have attained sufficient proof of principal status to be economically attractive to pursue commercially. Some of the authors have succeeded in separating sulfur isotopes using a rather new and different method, known as condensation repression. In this scheme a gas, of the selected isotopes for enrichment, is irradiated with a laser at a particular wavelength that would excite only one of the isotopes. The entire gas is subject to low temperatures sufficient to cause condensation on a cold surface. Those molecules in the gas that the laser excited are not as likely to condense as are the unexcited molecules. Hence the gas drawn out of the system will be enriched in the isotope that was excited by the laser. We have evaluated the relative energy required in this process if applied on a commercial scale. We estimate the energy required for laser isotope enrichment is about 20% of that required in centrifuge separations, and 2% of that required by use of "calutrons".

  2. Energy Assessment Helps Kaiser Aluminum Save Energy and Improve Productivity; DOE Software Adopted as Standard for Analyzing Plant Process Heating Systems Company-Wide; Industrial Technologies Program (ITP) Save Energy Now (SEN) Case Study

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

    Kaiser Aluminum plant in Sherman, Texas, improved its annual furnace energy intensity by 11.1% after imple- menting recommendations from the Save Energy Now assessment. Energy Assessment Helps Kaiser Aluminum Save Energy and Improve Productivity DOE Software Adopted as Standard for Analyzing Plant Process Heating Systems Company-Wide Industrial Technologies Program Case Study Key Findings * Opportunities for energy efficiency do not require large capital expenditures to achieve significant

  3. Toxic Substances Control Act Uranium Enrichment Federal Facility Compliance

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

    Agreement | Department of Energy Toxic Substances Control Act Uranium Enrichment Federal Facility Compliance Agreement Toxic Substances Control Act Uranium Enrichment Federal Facility Compliance Agreement Toxic Substances Control Act (TSCA) Uranium Enrichment Federal Facility Compliance Agreement establishes a plan to bring DOE's Uranium Enrichment Plants (and support facilities) located in Portsmouth, Ohio and Paducah, Kentucky and DOE's former Uranium Enrichment Plant (and support

  4. March market review. [Spot market prices for uranium (1993)

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The spot market price for uranium in unrestricted markets weakened further during March, and at month end, the NUEXCO Exchange Value had fallen $0.15, to $7.45 per pound U3O8. The Restricted American Market Penalty (RAMP) for concentrates increased $0.15, to $2.55 per pound U3O8. Ample UF6 supplies and limited demand led to a $0.50 decrease in the UF6 Value, to $25.00 per kgU as UF6, while the RAMP for UF6 increased $0.75, to $5.25 per kgU. Nine near-term uranium transactions were reported, totalling almost 3.3 million pounds equivalent U3O8. This is the largest monthly spot market volume since October 1992, and is double the volume reported in January and February. The March 31 Conversion Value was $4.25 per kgU as UF6. Beginning with the March 31 Value, NUEXCO now reports its Conversion Value in US dollars per kilogram of uranium (US$/kgU), reflecting current industry practice. The March loan market was inactive with no transactions reported. The Loan Rate remained unchanged at 3.0 percent per annum. Low demand and increased competition among sellers led to a one-dollar decrease in the SWU Value, to $65 per SWU, and the RAMP for SWU declined one dollar, to $9 per SWU.

  5. Shenzhen Coolead Industry Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    navigation, search Name: Shenzhen Coolead Industry Co. Ltd. Place: China Product: Air conditioning R&D, equipment manufacture and sales. References: Shenzhen Coolead Industry Co....

  6. Kung Long Batteries Industrial Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Kung Long Batteries Industrial Co Ltd Jump to: navigation, search Name: Kung Long Batteries Industrial Co Ltd Place: Nantou, Taiwan Product: Manufacturer of more than 200 types of...

  7. Solar Energy LLC Industrial Investors Group | Open Energy Information

    Open Energy Info (EERE)

    LLC Industrial Investors Group Jump to: navigation, search Name: Solar Energy LLC - Industrial Investors Group Place: Moscow, Russian Federation Zip: 119017 Sector: Solar Product:...

  8. Companhia Industrial do Nordeste Brasileiro | Open Energy Information

    Open Energy Info (EERE)

    Industrial do Nordeste Brasileiro Jump to: navigation, search Name: Companhia Industrial do Nordeste Brasileiro Place: Pernambuco, Brazil Sector: Biomass Product: Brazil based...

  9. Dapu Huatai Industrial Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Dapu Huatai Industrial Co Ltd Jump to: navigation, search Name: Dapu Huatai Industrial Co., Ltd. Place: Meizhou, Guangdong Province, China Zip: 715403 Sector: Hydro Product:...

  10. Jiangxi Huahui Industrial Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Huahui Industrial Co Ltd Jump to: navigation, search Name: Jiangxi Huahui Industrial Co., Ltd. Place: Fuzhou, Jiangxi Province, China Zip: 335300 Sector: Hydro Product: China-based...

  11. Triunfo Agro Industrial S A | Open Energy Information

    Open Energy Info (EERE)

    Triunfo Agro Industrial S A Jump to: navigation, search Name: Triunfo Agro Industrial SA Place: Maceio, Alagoas, Brazil Product: Brazilian ethanol producer References: Triunfo...

  12. Companhia Agro Industrial de Goiana | Open Energy Information

    Open Energy Info (EERE)

    Companhia Agro Industrial de Goiana Jump to: navigation, search Name: Companhia Agro Industrial de Goiana Place: Recife, Pernambuco, Brazil Sector: Biomass Product: Ethanol and...

  13. ShaanXi Tianhong Silicon Industrial | Open Energy Information

    Open Energy Info (EERE)

    ShaanXi Tianhong Silicon Industrial Jump to: navigation, search Name: ShaanXi Tianhong Silicon Industrial Place: Shaanxi Province, China Product: Shaaxi-based polysilicon maker...

  14. Xi an Kaixin Industrial Development | Open Energy Information

    Open Energy Info (EERE)

    Kaixin Industrial Development Jump to: navigation, search Name: Xi(tm)an Kaixin Industrial Development Place: Xian, Shaanxi Province, China Sector: Hydro Product: China-based...

  15. Agropecuaria e Industrial Serra Grande | Open Energy Information

    Open Energy Info (EERE)

    e Industrial Serra Grande Jump to: navigation, search Name: Agropecuaria e Industrial Serra Grande Place: So Raimundo das Mangabeiras, Maranhao, Brazil Product: Privately owned...

  16. Amrit Bio Energy Industries Ltd | Open Energy Information

    Open Energy Info (EERE)

    Amrit Bio Energy Industries Ltd Jump to: navigation, search Name: Amrit Bio Energy & Industries Ltd. Place: Kolkata, West Bengal, India Zip: 700017 Sector: Biomass Product:...

  17. Nanjing Dalu Industry Investment Group | Open Energy Information

    Open Energy Info (EERE)

    Dalu Industry Investment Group Jump to: navigation, search Name: Nanjing Dalu Industry Investment Group Place: Beijing Municipality, China Zip: 100055 Sector: Solar Product:...

  18. Henan Yinge Industrial Investment Corporation | Open Energy Informatio...

    Open Energy Info (EERE)

    Yinge Industrial Investment Corporation Jump to: navigation, search Name: Henan Yinge Industrial Investment Corporation Place: Henan Province, China Sector: Biomass Product:...

  19. Shenzhen Heng Yang Solar Industrial Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Solar Industrial Co Ltd Jump to: navigation, search Name: Shenzhen Heng Yang Solar Industrial Co Ltd Place: Shenzhen, Guangdong Province, China Zip: 518081 Product: Imported...

  20. Lee Chung Yung Chemical Industry Corporation | Open Energy Information

    Open Energy Info (EERE)

    Chung Yung Chemical Industry Corporation Jump to: navigation, search Name: Lee Chung Yung Chemical Industry Corporation Place: Taipei, Taiwan Product: Chemical manufacturer...

  1. Jay Mahesh Sugar Industries Ltd | Open Energy Information

    Open Energy Info (EERE)

    Sugar Industries Ltd. Place: Maharashtra, India Zip: 431131 Product: Beed-based sugar mill with cogeneration project. References: Jay Mahesh Sugar Industries Ltd.1 This article...

  2. BOC Lienhwa Industrial Gases BOCLH | Open Energy Information

    Open Energy Info (EERE)

    Lienhwa Industrial Gases (BOCLH) Place: Taipei, Taiwan Sector: Solar Product: BOCLH is a joint venture between the Lien Hwa Industrial Corporation and the BOC Group in the United...

  3. Vietnam National Coal Mineral Industries Group Vinacomin | Open...

    Open Energy Info (EERE)

    National Coal Mineral Industries Group Vinacomin Jump to: navigation, search Name: Vietnam National Coal-Mineral Industries Group (Vinacomin) Place: Vietnam Product: Vietnam-based...

  4. Nova Chemicals Reliance Industries JV | Open Energy Information

    Open Energy Info (EERE)

    Product: Nova Chemicals has signed an agreement with Reliance Industries to construct energy efficient buildings in India. References: Nova Chemicals & Reliance Industries...

  5. Shanghai New Energy industry Association SNEIA | Open Energy...

    Open Energy Info (EERE)

    (SNEIA) Place: Shanghai Municipality, China Zip: 200235 Product: Shanghai-based industrial association for new energy sector References: Shanghai New Energy industry...

  6. Vision Industries dba Vision Motor Corp | Open Energy Information

    Open Energy Info (EERE)

    Industries dba Vision Motor Corp Jump to: navigation, search Name: Vision Industries (dba Vision Motor Corp) Place: Santa Monica, California Zip: 90405 Product: Santa Monica-based...

  7. China South Industries Group Corp CSG | Open Energy Information

    Open Energy Info (EERE)

    Industries Group Corp CSG Jump to: navigation, search Name: China South Industries Group Corp (CSG) Place: Beijing, Beijing Municipality, China Zip: 100821 Product: Beijing-based...

  8. Nahar Industrial Enterprises Limited NIEL | Open Energy Information

    Open Energy Info (EERE)

    Industrial Enterprises Limited NIEL Jump to: navigation, search Name: Nahar Industrial Enterprises Limited (NIEL) Place: Punjab, India Zip: 140506 Sector: Biomass Product:...

  9. Allsoft Engenharia e Informatica Industrial | Open Energy Information

    Open Energy Info (EERE)

    Allsoft Engenharia e Informatica Industrial Jump to: navigation, search Name: Allsoft Engenharia e Informatica Industrial Place: Brazil Product: A Brazilian engineering and...

  10. Baoding High Tech Industry Development Zone | Open Energy Information

    Open Energy Info (EERE)

    Name: Baoding High-Tech Industry Development Zone Place: China Product: Government & NGO ( State-owned commercial entity ) References: Baoding High-Tech Industry Development...

  11. Target and method for the production of fission product molybdenum-99

    DOE Patents [OSTI]

    Vandegrift, G.F.; Vissers, D.R.; Marshall, S.L.; Varma, R.

    1987-10-26

    A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm/sup 2/ of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99. 2 figs.

  12. Target and method for the production of fission product molybdenum-99

    DOE Patents [OSTI]

    Vandegrift, George F. (Bolingbrook, IL); Vissers, Donald R. (Naperville, IL); Marshall, Simon L. (Woodridge, IL); Varma, Ravi (Hinsdale, IL)

    1989-01-01

    A target for the reduction of fission product Mo-99 is prepared from uranium of low U-235 enrichment by coating a structural support member with a preparatory coating of a substantially oxide-free substrate metal. Uranium metal is electrodeposited from a molten halide electrolytic bath onto a substrate metal. The electrodeposition is performed at a predetermined direct current rate or by using pulsed plating techniques which permit relaxation of accumulated uranium ion concentrations within the melt. Layers of as much as to 600 mg/cm.sup.2 of uranium can be prepared to provide a sufficient density to produce acceptable concentrations of fission product Mo-99.

  13. Fabrication of Cerium Oxide and Uranium Oxide Microspheres for Space Nuclear Power Applications

    SciTech Connect (OSTI)

    Jeffrey A. Katalenich; Michael R. Hartman; Robert C. O'Brien

    2013-02-01

    Cerium oxide and uranium oxide microspheres are being produced via an internal gelation sol-gel method to investigate alternative fabrication routes for space nuclear fuels. Depleted uranium and non-radioactive cerium are being utilized as surrogates for plutonium-238 (Pu-238) used in radioisotope thermoelectric generators and for enriched uranium required by nuclear thermal rockets. While current methods used to produce Pu-238 fuels at Los Alamos National Laboratory (LANL) involve the generation of fine powders that pose a respiratory hazard and have a propensity to contaminate glove boxes, the sol-gel route allows for the generation of oxide microsphere fuels through an aqueous route. The sol-gel method does not generate fine powders and may require fewer processing steps than the LANL method with less operator handling. High-quality cerium dioxide microspheres have been fabricated in the desired size range and equipment is being prepared to establish a uranium dioxide microsphere production capability.

  14. 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...

  15. Uranium Pyrophoricity Phenomena and Prediction (FAI/00-39)

    SciTech Connect (OSTI)

    PLYS, M.G.

    2000-10-10

    The purpose of this report is to provide a topical reference on the phenomena and prediction of uranium pyrophoricity for the Hanford Spent Nuclear Fuel (SNF) Project with specific applications to SNF Project processes and situations. Spent metallic uranium nuclear fuel is currently stored underwater at the K basins in the Hanford 100 area, and planned processing steps include: (1) At the basins, cleaning and placing fuel elements and scrap into stainless steel multi-canister overpacks (MCOs) holding about 6 MT of fuel apiece; (2) At nearby cold vacuum drying (CVD) stations, draining, vacuum drying, and mechanically sealing the MCOs; (3) Shipping the MCOs to the Canister Storage Building (CSB) on the 200 Area plateau; and (4) Welding shut and placing the MCOs for interim (40 year) dry storage in closed CSB storage tubes cooled by natural air circulation through the surrounding vault. Damaged fuel elements have exposed and corroded fuel surfaces, which can exothermically react with water vapor and oxygen during normal process steps and in off-normal situations, A key process safety concern is the rate of reaction of damaged fuel and the potential for self-sustaining or runaway reactions, also known as uranium fires or fuel ignition. Uranium metal and one of its corrosion products, uranium hydride, are potentially pyrophoric materials. Dangers of pyrophoricity of uranium and its hydride have long been known in the U.S. Department of Energy (Atomic Energy Commission/DOE) complex and will be discussed more below; it is sufficient here to note that there are numerous documented instances of uranium fires during normal operations. The motivation for this work is to place the safety of the present process in proper perspective given past operational experience. Steps in development of such a perspective are: (1) Description of underlying physical causes for runaway reactions, (2) Modeling physical processes to explain runaway reactions, (3) Validation of the method against experimental data, (4) Application of the method to plausibly explain operational experience, and (5) Application of the method to present process steps to demonstrate process safety and margin. Essentially, the logic above is used to demonstrate that runaway reactions cannot occur during normal SNF Project process steps, and to illustrate the depth of the technical basis for such a conclusion. Some off-normal conditions are identified here that could potentially lead to runaway reactions. However, this document is not intended to provide an exhaustive analysis of such cases. In summary, this report provides a ''toolkit'' of models and approaches for analysis of pyrophoricity safety issues at Hanford, and the technical basis for the recommended approaches. A summary of recommended methods appears in Section 9.0.

  16. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand separative 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 1,496 2,112 1,801 Russia 5,055 5,308 6,560 2,491 3,083 United Kingdom 2,119 2,813 2,648 2,674 2,435 Europe 1 W 670 W 0 W Other 2 W

  17. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    8 U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Deliveries 2010 2011 2012 2013 2014 Purchases 2,226 1,668 1,194 W 410 Weighted-average price 43.36 54.85 51.78 W 33.55 Purchases 27,186 24,695 24,606 W 28,743 Weighted-average price 41.42 49.69 47.75 W 38.42 Purchases 29,412 26,363 25,800 30,191 29,153 Weighted-average price 41.57 50.02 47.94 42.95 38.35 Purchases 24,693

  18. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 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 57.47 6,724 51.17 10,741 49.92 10,511 48.03 Brazil W W W W W W W W W W Canada 10,238 50.35 10,832 56.08 13,584 56.75 7,808 52.61 9,789 45.87 China 0 -- W W W W W W W W Czech

  19. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 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 Weighted- average price First 8 10,981 45.58 8 12,328 42.01 8 11,681 37.64 Second 7 11,659 53.03 8 13,143 49.94 7 8,493 42.68 Third 7 21,146 57.22 7 18,057 53.43 7 21,805 48.04

  20. Depleted uranium disposal options evaluation

    SciTech Connect (OSTI)

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

    1994-05-01

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

  1. Industrial-Strength UPF | Y-12 National Security Complex

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

    Industrial-Strength UPF Industrial-Strength UPF Posted: July 22, 2013 - 3:17pm | Y-12 Report | Volume 10, Issue 1 | 2013 UPF is an excellent opportunity to rebuild the supply chain for new nuclear facility construction in the Tennessee Valley Corridor and beyond. The Uranium Processing Facility is the Department of Energy's single largest capital investment in Tennessee since World War II and the National Nuclear Security Administration's largest-ever construction project. UPF will consolidate

  2. uranium | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    uranium | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home

  3. Uranium Metal Analysis via Selective Dissolution

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Chenault, Jeffrey W.

    2008-09-10

    Uranium metal, which is present in sludge held in the Hanford Site K West Basin, can create hazardous hydrogen atmospheres during sludge handling, immobilization, or subsequent transport and storage operations by its oxidation/corrosion in water. A thorough knowledge of the uranium metal concentration in sludge therefore is essential to successful sludge management and waste process design. The goal of this work was to establish a rapid routine analytical method to determine uranium metal concentrations as low as 0.03 wt% in sludge even in the presence of up to 1000-fold higher total uranium concentrations (i.e., up to 30 wt% and more uranium) for samples to be taken during the upcoming sludge characterization campaign and in future analyses for sludge handling and processing. This report describes the experiments and results obtained in developing the selective dissolution technique to determine uranium metal concentration in K Basin sludge.

  4. Industrial Energy Efficiency Basics | Department of Energy

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

    Industrial Energy Efficiency Basics Industrial Energy Efficiency Basics The industrial sector is vital to the U.S. economy, but at the same time consumes the most energy in the country to manufacture products we use every day. Among the most energy-intensive industries are aluminum, chemicals, forest product, glass, metal casting, mining, petroleum refining, and steel. The energy supply chain begins with electricity, steam, natural gas, coal, and other fuels supplied to a manufacturing plant

  5. DOE/NNSA Successfully Establishes Uranium Lease and Takeback Program to

    National Nuclear Security Administration (NNSA)

    Support Critical Medical Isotope Production | National Nuclear Security Administration Successfully Establishes Uranium Lease and Takeback Program to Support Critical Medical Isotope Production | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our

  6. TRIMOLECULAR REACTIONS OF URANIUM HEXAFLUORIDE WITH WATER

    SciTech Connect (OSTI)

    Westbrook, M.; Becnel, J.; Garrison, S.

    2010-02-25

    The hydrolysis reaction of uranium hexafluoride (UF{sub 6}) is a key step in the synthesis of uranium dioxide (UO{sub 2}) powder for nuclear fuels. Mechanisms for the hydrolysis reactions are studied here with density functional theory and the Stuttgart small-core scalar relativistic pseudopotential and associated basis set for uranium. The reaction of a single UF{sub 6} molecule with a water molecule in the gas phase has been previously predicted to proceed over a relatively sizeable barrier of 78.2 kJ {center_dot} mol{sup -1}, indicating this reaction is only feasible at elevated temperatures. Given the observed formation of a second morphology for the UO{sub 2} product coupled with the observations of rapid, spontaneous hydrolysis at ambient conditions, an alternate reaction pathway must exist. In the present work, two trimolecular hydrolysis mechanisms are studied with density functional theory: (1) the reaction between two UF{sub 6} molecules and one water molecule, and (2) the reaction of two water molecules with a single UF{sub 6} molecule. The predicted reaction of two UF{sub 6} molecules with one water molecule displays an interesting 'fluorine-shuttle' mechanism, a significant energy barrier of 69.0 kJ {center_dot} mol{sup -1} to the formation of UF{sub 5}OH, and an enthalpy of reaction ({Delta}H{sub 298}) of +17.9 kJ {center_dot} mol{sup -1}. The reaction of a single UF{sub 6} molecule with two water molecules displays a 'proton-shuttle' mechanism, and is more favorable, having a slightly lower computed energy barrier of 58.9 kJ {center_dot} mol{sup -1} and an exothermic enthalpy of reaction ({Delta}H{sub 298}) of -13.9 kJ {center_dot} mol{sup -1}. The exothermic nature of the overall UF{sub 6} + 2 {center_dot} H{sub 2}O trimolecular reaction and the lowering of the barrier height with respect to the bimolecular reaction are encouraging; however, the sizable energy barrier indicates further study of the UF{sub 6} hydrolysis reaction mechanism is warranted to resolve the remaining discrepancies between the predicted mechanisms and experimental observations.

  7. Uranium Leasing Program | Department of Energy

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

    » Uranium Leasing Program Uranium Leasing Program Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado LM currently manages the Uranium Leasing Program and continues to administer 31 lease tracts, all located within the Uravan Mineral Belt in southwestern Colorado. Twenty-nine of these lease tracts are actively held under lease and two tracts have been placed in inactive status indefinitely. Administrative duties include ongoing

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

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

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

  9. Uranium Processing Facility Team Signs Partnering Agreement ...

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

    Processing Facility ... Uranium Processing Facility Team Signs Partnering Agreement Posted: July 18, 2014 - 4:39pm Front row, left to right: Bill Priest, Consolidated Nuclear...

  10. Oxidation and crystal field effects in uranium

    SciTech Connect (OSTI)

    Tobin, J. G.; Booth, C. H.; Shuh, D. K.; van der Laan, G.; Sokaras, D.; Weng, T. -C.; Yu, S. W.; Bagus, P. S.; Tyliszczak, T.; Nordlund, D.

    2015-07-06

    An extensive investigation of oxidation in uranium has been pursued. This includes the utilization of soft x-ray absorption spectroscopy, hard x-ray absorption near-edge structure, resonant (hard) x-ray emission spectroscopy, cluster calculations, and a branching ratio analysis founded on atomic theory. The samples utilized were uranium dioxide (UO2), uranium trioxide (UO3), and uranium tetrafluoride (UF4). As a result, a discussion of the role of non-spherical perturbations, i.e., crystal or ligand field effects, will be presented.

  11. Colorimetric detection of uranium in water

    DOE Patents [OSTI]

    DeVol, Timothy A.; Hixon, Amy E.; DiPrete, David P.

    2012-03-13

    Disclosed are methods, materials and systems that can be used to determine qualitatively or quantitatively the level of uranium contamination in water samples. Beneficially, disclosed systems are relatively simple and cost-effective. For example, disclosed systems can be utilized by consumers having little or no training in chemical analysis techniques. Methods generally include a concentration step and a complexation step. Uranium concentration can be carried out according to an extraction chromatographic process and complexation can chemically bind uranium with a detectable substance such that the formed substance is visually detectable. Methods can detect uranium contamination down to levels even below the MCL as established by the EPA.

  12. Radiological Safety Training for Uranium Facilities

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

    ... Continued on Next Page * Stein, F., Instructor Competencies: the Standards. International ... and acute exposures to significant amounts of uranium may result in kidney damage. ...

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

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

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial ... Dear Mr. Friedman: We have audited the financial statements of the Department of Energy's ...

  14. Plutonium Uranium Extraction Plant (PUREX) - Hanford Site

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

    Site. The Plutonium Uranium Extraction Plant is massive. It is longer than three football fields, stands 64 feet above the ground, and extends another 40 feet below ground....

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

    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 uranium, a vital national security asset. HEUMF is a massive concrete and steel structure that provides maximum security for the highly enriched uranium material that it protects. Approximately 300 feet by 475 feet, HEUMF has areas for receiving, shipping and providing long-term storage of the enriched uranium, as well

  16. High strength and density tungsten-uranium alloys

    DOE Patents [OSTI]

    Sheinberg, Haskell (Los Alamos, NM)

    1993-01-01

    Alloys of tungsten and uranium and a method for making the alloys. The amount of tungsten present in the alloys is from about 55 vol % to about 85 vol %. A porous preform is made by sintering consolidated tungsten powder. The preform is impregnated with molten uranium such that (1) uranium fills the pores of the preform to form uranium in a tungsten matrix or (2) uranium dissolves portions of the preform to form a continuous uranium phase containing tungsten particles.

  17. DOE Evaluates Environmental Impacts of Uranium Mining on Government...

    Energy Savers [EERE]

    Evaluates Environmental Impacts of Uranium Mining on Government Land in Western Colorado DOE Evaluates Environmental Impacts of Uranium Mining on Government Land in Western...

  18. Record of Decision for the Uranium Leasing Program Programmatic...

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

    Record of Decision for the Uranium Leasing Program Programmatic Environmental Impact Statement Record of Decision for the Uranium Leasing Program Programmatic Environmental Impact...

  19. Toxic Substances Control Act Uranium Enrichment Federal Facility...

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

    Toxic Substances Control Act Uranium Enrichment Federal Facility Compliance Agreement Toxic Substances Control Act Uranium Enrichment Federal Facility Compliance Agreement Toxic...

  20. DOE/NNSA Successfully Establishes Uranium Lease and Takeback...

    National Nuclear Security Administration (NNSA)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home NNSA Blog DOENNSA Successfully Establishes Uranium Lease and Takeback ... DOENNSA Successfully Establishes Uranium Lease ...

  1. DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6...

    Office of Environmental Management (EM)

    Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at Ohio and Kentucky Facilities DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at...

  2. Legacy Management Work Progresses on Defense-Related Uranium...

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

    defense-related legacy uranium mine sites located within 11 uranium mining districts in 6 western states. At these sites, photographs and global positioning location data were...

  3. Highly Enriched Uranium Materials Facility, Major Design Changes...

    Energy Savers [EERE]

    Highly Enriched Uranium Materials Facility, Major Design Changes Late...Lessons Learned Report, NNSA, Dec 2010 Highly Enriched Uranium Materials Facility, Major Design Changes...

  4. DOE Extends Contract to Operate Depleted Uranium Hexafluoride...

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

    Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants December 24, 2015 -...

  5. Sequestering Uranium from Seawater: Binding Strength and Modes...

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

    Sequestering Uranium from Seawater: Binding Strength and Modes of Uranyl Complexes with Glutarimidedioxime Sequestering Uranium from Seawater: Binding Strength and Modes of Uranyl...

  6. The Impact of Ethanol Production on U.S. and Regional Gasoline Prices and on the Profitability of the U.S. Oil Refinery Industry

    SciTech Connect (OSTI)

    Du, Xiaodong; Hayes, Dermot J.

    2008-04-01

    This report details pooled regional time-series data and panel data estimation used to quantify the impact of monthly ethanol production on monthly retail regular gasoline prices.

  7. FutureGen Industrial Alliance Inc | Open Energy Information

    Open Energy Info (EERE)

    FutureGen Industrial Alliance Inc Jump to: navigation, search Name: FutureGen Industrial Alliance Inc Place: Washington, Washington, DC Zip: 20006 Product: The FutureGen Industrial...

  8. S. 210: This Act may be referred to as the Comprehensive Uranium Act of 1991, introduced in the Senate of the United States, One Hundred Second Congress, First Session, January 15, 1991

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This bill would establish the United States Enrichment Corporation to operate the Federal uranium enrichment program on a profitable and efficient basis in order to maximize the long term economic value to the US, provide assistance to the domestic uranium industry, and provide a Federal contribution for the reclamation of mill tailings generated pursuant to Federal defense contracts at active uranium and thorium processing sites. The bill describes congressional findings; definitions, establishment of corporation, and purposes; corporate offices; powers and duties of the corporation; organization, finance, and management; licensing, taxation, and miscellaneous provisions; decontamination and decommissioning; and uranium security and tailing reclamation.

  9. Conceptual design of a high throughput electrorefining of a uranium by using graphite cathode

    SciTech Connect (OSTI)

    Lee, J.H.; Kang, Y.H.; Hwang, S.C.; Park, S.B.; Shim, J.B.; Lee, H.S.; Kim, E.H.; Park, S.W.

    2007-07-01

    Conceptual designing of a high throughput electro-refiner was performed by using basic experimental data and a commercial computational fluid dynamic code, CFX. An electro-refiner concept equipped with a graphite cathode bundle was designed to recover a high purity uranium product continuously without a noble metal contamination. The performance of the process for a decontamination of a noble metal in a uranium product was evaluated as a function of the process parameters such as the rotation speeds of the stirrer and the anode basket. (authors)

  10. Industrial Solar Technology Corp | Open Energy Information

    Open Energy Info (EERE)

    Solar Technology Corp Jump to: navigation, search Name: Industrial Solar Technology Corp Place: Golden, Colorado Zip: CO 80403-1 Product: IST designs, manufactures, installs and...

  11. Taiwan Glass Industry Corp | Open Energy Information

    Open Energy Info (EERE)

    Taiwan Glass Industry Corp Place: Taipei, Taiwan Zip: 10566 Product: Engaged in the manufacturing, processing and selling of various types of glass. References: Taiwan Glass...

  12. Biodiesel Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    Barbara, California Zip: 93110 Product: Biodiesel producer and facility developer. References: Biodiesel Industries Inc1 This article is a stub. You can help OpenEI by expanding...

  13. Industrial Research Ltd IRL | Open Energy Information

    Open Energy Info (EERE)

    Research Ltd IRL Jump to: navigation, search Name: Industrial Research Ltd (IRL) Place: New Zealand Sector: Services Product: General Financial & Legal Services ( State-owned...

  14. Thompson Technology Industries TTI | Open Energy Information

    Open Energy Info (EERE)

    TTI Jump to: navigation, search Name: Thompson Technology Industries (TTI) Place: Novato, California Zip: 94949 Sector: Solar Product: Designer and manufacturer of solar tracking...

  15. SLS Power Industries Ltd | Open Energy Information

    Open Energy Info (EERE)

    Ltd. Place: Bangalore, Karnataka, India Sector: Hydro Product: Bangalore-based small hydro project developer. References: SLS Power Industries Ltd.1 This article is a stub....

  16. Cathay Industrial Biotech Ltd | Open Energy Information

    Open Energy Info (EERE)

    and supplier of chemicals, fuels and polymers that is exploring biobutanol research and production. References: Cathay Industrial Biotech Ltd1 This article is a stub. You can...

  17. Minxing Industry Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Co. Ltd. Place: Sichuan Province, China Zip: 625700 Sector: Hydro Product: Sichuan-based small hydro project developer. References: Minxing Industry Co. Ltd.1 This article is a...

  18. Unichem Industries Inc | Open Energy Information

    Open Energy Info (EERE)

    Unichem produces high resolution screen printing equipment for crystalline silicon solar cell production. References: Unichem Industries Inc1 This article is a stub. You...

  19. United Nations Industrial Development Organization (UNIDO) |...

    Open Energy Info (EERE)

    development of industry in developing nations. UNIDO focuses on three key areas: Poverty reduction through productive activities Trade capacity-building Energy and...

  20. Siddeshwari Industries Pvt Ltd | Open Energy Information

    Open Energy Info (EERE)

    Muzaffarnagar, Uttar Pradesh, India Zip: 251001 Product: Muzaffarnagar based paper mill with cogeneration activities References: Siddeshwari Industries Pvt Ltd.1 This...