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1

Total production of uranium concentrate in the United States  

Gasoline and Diesel Fuel Update (EIA)

2. Number of uranium mills and plants producing uranium concentrate in the United States 2. Number of uranium mills and plants producing uranium concentrate in the United States Uranium Concentrate Processing Facilities End of 1996 End of 1997 End of 1998 End of 1999 End of 2000 End of 2001 End of 2002 End of 2003 End of 2004 End of 2005 End of 2006 End of 2007 End of 2008 End of 2009 End of 2010 End of 2011 End of 2012 End of 3rd Quarter 2013 Mills - conventional milling1 0 0 0 1 1 0 0 0 0 0 0 0 1 0 1 1 1 0 Mills - other operators2 2 3 2 2 2 1 1 0 0 1 1 1 0 1 0 0 0 1 In-Situ-Leach Plants3 5 6 6 4 3 3 2 2 3 3 5 5 6 3 4 5 5 5 Byproduct Recovery Plants4 2 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 9 11 9 7 6 4 3 2 3 4 6 6 7 4 5 6 6 6

2

Total production of uranium concentrate in the United States  

Gasoline and Diesel Fuel Update (EIA)

4. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status 4. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status Operating Status at the End of In-Situ-Leach Plant Owner In-Situ-Leach Plant Name County, State (existing and planned locations) Production Capacity (pounds U3O8 per year) 2012 1st Quarter 2013 2nd Quarter 2013 3rd Quarter 2013 Cameco Crow Butte Operation Dawes, Nebraska 1,000,000 Operating Operating Operating Operating Hydro Resources, Inc. Church Rock McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Hydro Resources, Inc. Crownpoint McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed

3

Total production of uranium concentrate in the United States  

Gasoline and Diesel Fuel Update (EIA)

3. U.S. uranium mills and heap leach facilities by owner, location, capacity, and operating status 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) 2012 1st Quarter 2013 2nd Quarter 2013 3rd Quarter 2013 EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating-Processing Alternate Feed Energy Fuels Resources Corporation Piñon Ridge Mill Montrose, Colorado 500 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Permitted and Licensed Energy Fuels Wyoming Inc Sheep Mountain Fremont, Wyoming 725 - Undeveloped Undeveloped Undeveloped

4

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

SciTech Connect

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.

McGinnis, Brent [Innovative Solutions Unlimited, LLC] [Innovative Solutions Unlimited, LLC

2014-04-01T23:59:59.000Z

5

2013 Domestic Uranium Production Report  

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

3. U.S. uranium concentrate production, shipments, and sales, 2003-13" "Activity at U.S. Mills and In-Situ-Leach Plants",2003,2004,2005,2006,2007,2008,2009,2010,2011,2012,2013...

6

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

9. Summary production statistics of the U.S. uranium industry, 1993-2012 9. Summary production statistics of the U.S. uranium industry, 1993-2012 Item 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 E2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Exploration and Development Surface Drilling (million feet) 1.1 0.7 1.3 3.0 4.9 4.6 2.5 1.0 0.7 W W 1.2 1.7 2.7 5.1 5.1 3.7 4.9 6.3 7.2 Drilling Expenditures (million dollars)1 5.7 1.1 2.6 7.2 20.0 18.1 7.9 5.6 2.7 W W 10.6 18.1 40.1 67.5 81.9 35.4 44.6 53.6 66.6 Mine Production of Uranium (million pounds U3O8) 2.1 2.5 3.5 4.7 4.7 4.8 4.5 3.1 2.6 2.4 2.2 2.5 3.0 4.7 4.5 3.9 4.1 4.2 4.1 4.3 Uranium Concentrate Production (million pounds U3O8) 3.1 3.4 6.0 6.3 5.6 4.7 4.6 4.0 2.6 2.3 2.0 2.3 2.7 4.1 4.5 3.9 3.7 4.2 4.0 4.1

7

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

2 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 Uranium Concentrate Produced at U.S. Mills (thousand pounds U3O8) W W W W W W W W W W W Uranium Concentrate...

8

Domestic Uranium Production Report  

Annual Energy Outlook 2012 (EIA)

6. Employment in the U.S. uranium production industry by category, 2003-13 person-years Year Exploration Mining Milling Processing Reclamation Total 2003 W W W W 117 321 2004 18...

9

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

10. Uranium reserve estimates at the end of 2012 10. Uranium reserve estimates at the end of 2012 million pounds U3O8 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 Properties with Exploration Completed, Exploration Continuing, and Only Assessment Work W W 102.0 Properties Under Development for Production W W W Mines in Production W 21.4 W Mines Closed Temporarily and Closed Permanently W W 133.1 In-Situ Leach Mining W W 128.6 Underground and Open Pit Mining W W 175.4 Arizona, New Mexico and Utah 0 W 164.7 Colorado, Nebraska and Texas W W 40.8 Wyoming W W 98.5 Total 51.8 W 304.0 1 Sixteen respondents reported reserve estimates on 71 mines and properties. These uranium reserve estimates cannot be compared with the much larger historical data set of uranium reserves that were published in the July 2010 report U.S. Uranium Reserves Estimates at http://www.eia.gov/cneaf/nuclear/page/reserves/ures.html. Reserves, as reported here, do not necessarily imply compliance with U.S. or Canadian government definitions for purposes of investment disclosure.

10

2012 Domestic Uranium Production Report  

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

9. Summary production statistics of the U.S. uranium industry, 1993-2012" 9. Summary production statistics of the U.S. uranium industry, 1993-2012" "Item",1993,1994,1995,1996,1997,1998,1999,2000,2001,2002,"E2003",2004,2005,2006,2007,2008,2009,2010,2011,2012 "Exploration and Development" "Surface Drilling (million feet)",1.1,0.7,1.3,3,4.9,4.6,2.5,1,0.7,"W","W",1.2,1.7,2.7,5.1,5.1,3.7,4.9,6.3,7.2 "Drilling Expenditures (million dollars)1",5.7,1.1,2.6,7.2,20,18.1,7.9,5.6,2.7,"W","W",10.6,18.1,40.1,67.5,81.9,35.4,44.6,53.6,66.6 "Mine Production of Uranium" "(million pounds U3O8)",2.1,2.5,3.5,4.7,4.7,4.8,4.5,3.1,2.6,2.4,2.2,2.5,3,4.7,4.5,3.9,4.1,4.2,4.1,4.3 "Uranium Concentrate Production" "(million pounds U3O8)",3.1,3.4,6,6.3,5.6,4.7,4.6,4,2.6,2.3,2,2.3,2.7,4.1,4.5,3.9,3.7,4.2,4,4.1

11

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

8. U.S. uranium expenditures, 2003-2012 8. U.S. uranium expenditures, 2003-2012 million dollars Year Drilling Production Land and Other 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 43.5 33.7 319.2 2012 66.6 186.9 99.4 16.8 33.3 49.3 352.9 Drilling: All expenditures directly associated with exploration and development drilling. Production: All expenditures for mining, milling, processing of uranium, and facility expense.

12

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

2. U.S. uranium mine production and number of mines and sources, 2003-2012 2. U.S. uranium mine production and number of mines and sources, 2003-2012 Production / Mining Method 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Underground (estimated contained thousand pounds U3O8) 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 In-Situ Leaching (thousand pounds U3O8) W W 2,681 4,259 W W W W W W Other1 (thousand pounds U3O8) W W W W W W W W W W Total Mine Production (thousand pounds U3O8) E2,200 2,452 3,045 4,692 4,541 3,879 4,145 4,237 4,114 4,335 Number of Operating Mines Underground 1 2 4 5 6 10 14 4 5 6 Open Pit 0 0 0 0 0 0 0 0 0 0 In-Situ Leaching 2 3 4 5 5 6 4 4 5 5 Other Sources1 1 1 2 1 1 1 2 1 1 1

13

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

5. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status at end of the year, 2008-2012 5. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status at end of the year, 2008-2012 In-Situ-Leach Plant Owner In-Situ-Leach Plant Name County, State (existing and planned locations) Production Capacity (pounds U3O8 per year) Operating Status at End of the Year 2008 2009 2010 2011 2012 Cameco Crow Butte Operation Dawes, Nebraska 1,000,000 Operating Operating Operating Operating Operating Hydro Resources, Inc. Crownpoint McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Hydro Resources,Inc. Church Rock McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed

14

Process for continuous production of metallic uranium and uranium alloys  

DOE Patents (OSTI)

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.

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

1995-06-06T23:59:59.000Z

15

Domestic Uranium Production Report - Quarterly - Energy Information  

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

All Nuclear Reports All Nuclear Reports Domestic Uranium Production Report - Quarterly Data for 3rd Quarter 2013 | Release Date: October 31, 2013 | Next Release Date: February 2014 | full report Previous Issues Year: 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 3rd Quarter 2013 U.S. production of uranium concentrate in the third quarter 2013 was 1,171,278 pounds U3O8, down 16 percent from the previous quarter and up 12 percent from the third quarter 2012. Third quarter 2013 uranium production is at its highest level since 1999. During the third quarter 2013, U.S. uranium was produced at six U.S. uranium facilities. U.S. Uranium Mill in Production (State)

16

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

4. U.S. uranium mills by owner, location, capacity, and operating status at end of the year, 2008-2012 4. U.S. uranium mills by owner, location, capacity, and operating status at end of the year, 2008-2012 Mill Owner Mill Name County, State (existing and planned locations) Milling Capacity (short tons of ore per day) Operating Status at End of the Year 2008 2009 2010 2011 2012 Cotter Corporation Canon City Mill Fremont, Colorado 0 Standby Standby Standby Reclamation Demolished Denison White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating Operating Energy Fuels Resources Corporation Piñon Ridge Mill Montrose, Colorado 500 Developing Developing Developing Permitted And Licensed Partially Permitted And Licensed Kennecott Uranium Company/Wyoming Coal Resource Company Sweetwater Uranium Project Sweetwater, Wyoming 3,000 Standby Standby Standby Standby Standby

17

2012 Domestic Uranium Production Report  

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

7 7 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 Milling Capacity (short tons of ore per day) 2008 2009 2010 2011 2012 Cotter Corporation Canon City Mill Fremont, Colorado 0 Standby Standby Standby Reclamation Demolished EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating Operating Energy Fuels Resources Corporation Piñon Ridge Mill Montrose, Colorado 500 Developing Developing Developing Permitted And Licensed Partially Permitted And Licensed Kennecott Uranium Company/Wyoming Coal Resource Company Sweetwater Uranium Project Sweetwater, Wyoming 3,000 Standby Standby Standby Standby Standby Uranium One Americas, Inc. Shootaring Canyon Uranium Mill Garfield, Utah 750 Changing License To Operational Standby

18

2012 Domestic Uranium Production Report  

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

Domestic Uranium Domestic Uranium Production Report June 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. U.S. Energy Information Administration | 2012 Domestic Uranium Production Report ii Contacts This report was prepared by the staff of the Renewables and Uranium Statistics Team, Office of Electricity,

19

Uranium in Runoff from the Gulf of Mexico Distributive Province: Anomalous Concentrations  

Science Journals Connector (OSTI)

...calcium silicate hydrate zones. This densification...the two hydrated phases and makes the properties...calcium silicate hydrate zones and around...production and of the behavior of uranium during...illustrate the chemical behavior of ura-nium during...the phosphori,te sand. High uranium concentrations...

Roy F. Spalding; William M. Sackett

1972-02-11T23:59:59.000Z

20

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 State(s) 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Wyoming 134 139 181 195 245 301 308 348 424 512 Colorado and Texas 48 140 269 263 557 696 340 292 331 248 Nebraska and New Mexico 92 102 123 160 149 160 159 134 127 W Arizona, Utah, and Washington 47 40 75 120 245 360 273 281 W W Alaska, Michigan, Nevada, and South Dakota 0 0 0 16 25 30 W W W W California, Montana, North Dakota, Oklahoma, Oregon, and Virginia 0 0 0 0 9 17 W W W W Total 321 420 648 755 1,231 1,563 1,096 1,073 1,191 1,196 Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report" (2003-2012). Table 7. Employment in the U.S. uranium production industry by state, 2003-2012 person-years

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 2008 2009 2010 2011 2012 Cameco Crow Butte Operation Dawes, Nebraska 1,000,000 Operating Operating Operating Operating Operating Hydro Resources, Inc. Church Rock McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Hydro Resources, Inc. Crownpoint McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Lost Creek ISR LLC Lost Creek Project Sweetwater, Wyoming 2,000,000 Developing

22

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 million pounds U 3 O 8 $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 102.0 Properties Under Development for Production W W W Mines in Production W 21.4 W Mines Closed Temporarily and Closed Permanently W W 133.1 In-Situ Leach Mining W W 128.6 Underground and Open Pit Mining W W 175.4 Arizona, New Mexico and Utah 0 W 164.7 Colorado, Nebraska and Texas W W 40.8 Wyoming W W 98.5 Total 51.8 W 304.0 W = Data withheld to avoid disclosure of individual company data. Note: Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report"

23

2012 Domestic Uranium Production Report  

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

10. Uranium reserve estimates at the end of 2012" 10. Uranium reserve estimates at the end of 2012" "million pounds U3O8" "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" "Properties with Exploration Completed, Exploration Continuing, and Only Assessment Work","W","W",101.956759 "Properties Under Development for Production","W","W","W" "Mines in Production","W",21.40601,"W" "Mines Closed Temporarily and Closed Permanently","W","W",133.139239 "In-Situ Leach Mining","W","W",128.576534

24

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 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 2011 5,441 3,322 5,156 3,003 10,597 6,325 2012 5,112 3,447 5,970 3,709 11,082 7,156 NA = Not available. W = Data withheld to avoid disclosure of individual company data. Note: Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report" (2003-

25

2012 Domestic Uranium Production Report  

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

2. U.S. uranium mine production and number of mines and sources, 2003-2012" 2. U.S. uranium mine production and number of mines and sources, 2003-2012" "Production / Mining Method",2003,2004,2005,2006,2007,2008,2009,2010,2011,2012 "Underground" "(estimated contained thousand pounds U3O8)","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 "In-Situ Leaching" "(thousand pounds U3O8)","W","W",2681,4259,"W","W","W","W","W","W" "Other1" "(thousand pounds U3O8)","W","W","W","W","W","W","W","W","W","W"

26

Domestic Uranium Production Report - Energy Information Administration  

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

Domestic Uranium Production Report - Annual Domestic Uranium Production Report - Annual With Data for 2012 | Release Date: June 06, 2013 | Next Release Date: May 2014 |full report Previous domestic uranium production reports Year: 2011 2010 2009 2008 2007 2006 2005 2004 Go Drilling Figure 1. U.S. Uranium drilling by number of holes, 2004-2012 U.S. uranium exploration drilling was 5,112 holes covering 3.4 million feet in 2012. Development drilling was 5,970 holes and 3.7 million feet. Combined, total uranium drilling was 11,082 holes covering 7.2 million feet, 5 percent more holes than in 2011. Expenditures for uranium drilling in the United States were $67 million in 2012, an increase of 24 percent compared with 2011. Mining, production, shipments, and sales U.S. uranium mines produced 4.3 million pounds U3O8 in 2012, 5 percent more

27

2012 Domestic Uranium Production Report  

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

5 5 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 Production / Mining Method 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 (estimated contained thousand pounds U 3 O 8 ) 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 (thousand pounds U 3 O 8 ) W W 2,681 4,259 W W W W W W (thousand pounds U 3 O 8 ) 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 3,879 4,145 4,237 4,114 4,335 Underground 1 2 4 5 6 10 14 4 5 6 Open Pit 0 0 0 0 0 0 0 0 0 0 In-Situ Leaching 2 3 4 5 5 6 4 4 5 5 Other Sources 1 1 1 2 1 1 1 2 1 1 1 Total Mines and Sources 4 6 10 11 12 17 20 9 11 12 Other 1 Number of Operating Mines Table 2. U.S. uranium mine production and number of mines and sources, 2003-2012 Underground Open Pit In-Situ Leaching Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report" (2003-2012).

28

2012 Domestic Uranium Production Report  

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

7. Employment in the U.S. uranium production industry by state, 2003-2012" 7. Employment in the U.S. uranium production industry by state, 2003-2012" "person-years" "State(s)",2003,2004,2005,2006,2007,2008,2009,2010,2011,2012 "Wyoming",134,139,181,195,245,301,308,348,424,512 "Colorado and Texas",48,140,269,263,557,696,340,292,331,248 "Nebraska and New Mexico",92,102,123,160,149,160,159,134,127,"W" "Arizona, Utah, and Washington",47,40,75,120,245,360,273,281,"W","W" "Alaska, Michigan, Nevada, and South Dakota",0,0,0,16,25,30,"W","W","W","W" "California, Montana, North Dakota, Oklahoma, Oregon, and Virginia",0,0,0,0,9,17,"W","W","W","W"

29

2012 Domestic Uranium Production Report  

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

9 9 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 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 Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report" (2003-2012). Table 6. Employment in the U.S. uranium production industry by category, 2003-2012 person-years W = Data withheld to avoid disclosure of individual company data. Note: Totals may not equal sum of components because of independent rounding. 0 200 400 600 800 1,000 1,200 1,400 1,600 2004 2005 2006 2007 2008

30

2012 Domestic Uranium Production Report  

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

5. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status at end of the year, 2008-2012" 5. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status at end of the year, 2008-2012" "In-Situ-Leach Plant Owner","In-Situ-Leach Plant Name","County, State (existing and planned locations)","Production Capacity (pounds U3O8 per year)","Operating Status at End of the Year" ,,,,2008,2009,2010,2011,2012 "Cameco","Crow Butte Operation","Dawes, Nebraska",1000000,"Operating","Operating","Operating","Operating","Operating" "Hydro Resources, Inc.","Church Rock","McKinley, New Mexico",1000000,"Partially Permitted And Licensed","Partially Permitted And Licensed","Partially Permitted And Licensed","Partially Permitted And Licensed","Partially Permitted And Licensed"

31

Uranium 2014 resources, production and demand  

E-Print Network (OSTI)

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

Organisation for Economic Cooperation and Development. Paris

2014-01-01T23:59:59.000Z

32

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 Activity at U.S. Mills and In-Situ-Leach Plants 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Ore from Underground Mines and Stockpiles Fed to Mills 1 0 W W W 0 W W W W W Other Feed Materials 2 W W W W W W W W W W Total Mill Feed 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 (thousand pounds U 3 O 8 ) W W W W W W W W W W (thousand pounds U 3 O 8 ) E2,000 2,282 2,689 4,106 4,534 3,902 3,708 4,228 3,991 4,146 (thousand pounds U 3 O 8 ) E1,600 2,280 2,702 3,838 4,050 4,130 3,620 5,137 4,000 3,911 Deliveries (thousand pounds U 3 O 8 ) W W W 3,786 3,602 3,656 2,044 2,684 2,870 3,630 Weighted-Average Price (dollars per pound U 3 O 8 ) W W W 28.98 42.11 43.81 36.61 37.59 52.36 49.63 Notes: The 2003 annual amounts were estimated by rounding to the nearest 200,000 pounds to avoid disclosure of individual company data. Totals may not equal sum of components

33

Depleted Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

Depleted Uranium Depleted Uranium Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Depleted uranium is uranium that has had some of its U-235 content removed. Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce uranium having a higher concentration of uranium-235 than the 0.72% that occurs naturally (called "enriched" uranium) for use in U.S. national defense and civilian applications. "Depleted" uranium is also a product of the enrichment process. However, depleted uranium has been stripped of some of its natural uranium-235 content. Most of the Department of Energy's (DOE) depleted uranium inventory contains between 0.2 to 0.4 weight-percent uranium-235, well

34

2012 Domestic Uranium Production Report  

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

Domestic Uranium Production Report Domestic Uranium Production Report 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 Item 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 E2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Surface Drilling (million feet) 1.1 0.7 1.3 3.0 4.9 4.6 2.5 1.0 0.7 W W 1.2 1.7 2.7 5.1 5.1 3.7 4.9 6.3 7.2 Drilling Expenditures (million dollars) 1 5.7 1.1 2.6 7.2 20.0 18.1 7.9 5.6 2.7 W W 10.6 18.1 40.1 67.5 81.9 35.4 44.6 53.6 66.6 (million pounds U 3 O 8 ) 2.1 2.5 3.5 4.7 4.7 4.8 4.5 3.1 2.6 2.4 2.2 2.5 3.0 4.7 4.5 3.9 4.1 4.2 4.1 4.3 (million pounds U 3 O 8 ) 3.1 3.4 6.0 6.3 5.6 4.7 4.6 4.0 2.6 2.3 2.0 2.3 2.7 4.1 4.5 3.9 3.7 4.2 4.0 4.1 (million pounds U 3 O 8 ) 3.4 6.3 5.5 6.0 5.8 4.9 5.5 3.2 2.2 3.8 1.6 2.3 2.7 3.8 4.0 4.1 3.6 5.1 4.0 3.9 (person-years) 871 980 1,107 1,118 1,097 1,120 848 627 423 426 321 420 648 755 1,231 1,563 1,096 1,073 1,191 1,196

35

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

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

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

36

3rd Quarter 2014 Domestic Uranium Production Report  

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

Form EIA-851A and Form EIA-851Q, ""Domestic Uranium Production Report.""" " U.S. Energy Information Administration 3rd Quarter 2014 Domestic Uranium Production Report...

37

Uranium 2009 resources, production and demand  

E-Print Network (OSTI)

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

Organisation for Economic Cooperation and Development. Paris

2010-01-01T23:59:59.000Z

38

2012 Domestic Uranium Production Report  

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

11 11 2012 Domestic Uranium Production Report Release Date: June 6, 2013 Next Release Date: May 2014 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 49.3 352.9 Notes: Expenditures are in nominal U.S. dollars. Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report" (2003-2012). Reclamation Drilling: All expenditures directly associated with exploration and development drilling.

39

3rd Quarter 2013 Domestic Uranium Production Report  

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

3 3 3rd Quarter 2013 Domestic Uranium Production Report Release Date: October 31, 2013 Next Release Date: February 2014 Mills - conventional milling 1 0 0 0 1 1 0 0 0 0 0 0 0 1 0 1 1 1 0 Mills - other operations 2 2 3 2 2 2 1 1 0 0 1 1 1 0 1 0 0 0 1 In-Situ-Leach Plants 3 5 6 6 4 3 3 2 2 3 3 5 5 6 3 4 5 5 5 Byproduct Recovery Plants 4 2 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 9 11 9 7 6 4 3 2 3 4 6 6 7 4 5 6 6 6 End of 2005 End of 2006 End of 2007 End of 2008 End of 2009 3 Not including in-situ-leach plants that only produced uranium concentrate from restoration. 4 Uranium concentrate as a byproduct from phosphate production. Source: U.S. Energy Information Administration: Form EIA-851A and Form EIA-851Q, "Domestic Uranium Production Report." End of 2010 End of 2011 End of 2012 End of 3rd Quarter 2013 1 Milling uranium-bearing ore. 2 Not milling ore, but producing uranium concentrate from other (non-ore) materials.

40

Determination of uranium concentration in surface soil samples of Iran  

Science Journals Connector (OSTI)

The use of uranium-tipped antitank shells during the Iraq war (2003) caused serious concerns in Iran and the international media over possible contamination of the Iranian environment and consequent long-term health effects. After a shell explosion, uranium is discharged by fire into the air in the form of oxidised particles, which can be dispersed over a radius of several kilometres. Gamma ray spectrometry was used to determine uranium concentrations in soil samples collected from ten sites in Iranian sectors near the Iraqi border. All surface soil samples were taken from the top 5 cm from each site. The concentrations of 238U were assessed from 63 keV and 92 keV emissions of its first daughter nuclide, 234Th. To assess the isotopic ratio of 238U/235U, a secular equilibrium was ensured and the concentration of 235U under 186 keV was deduced. The 226Ra was determined through 295 keV and 352 keV gamma rays of 214Pb. The concentrations of 238U and activity ratios of 238U/235U were determined. The average of measurement activity ratio was 20.0, very close to the value of 21.5 for natural uranium, while the activity ratio of depleted uranium can be as high as 76.9. The analysis of ten surface soil samples from Iranian sites near the Iraqi border showed that uranium isotopes are in natural abundances.

A.A. Fathivand; J. Amidi

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

The CZTU uranium concentration analysis code  

SciTech Connect

A {sup 235}U analysis code, CZTU, has been written that can non- destructively evaluate the percentage of {sup 235}U in a uranium sample from the analysis of the emitted gamma rays. This code utilizes gamma spectra measured from room temperature Cadmium Zinc Telluride (CdZnTe or CZT) detectors. It has an accuracy midway between that obtained with sodium iodide and germanium crystal detectors. This report describes how to use the code, some results, limitations and design considerations.

Clark, D., LLNL

1998-07-17T23:59:59.000Z

42

Radon-222 Daughter Concentrations in Uranium Mine Atmospheres  

Science Journals Connector (OSTI)

... undertaken to measure the concentrations of 210Pb and 210Po in uranium mine atmospheres at various radon daughter concentration levels, and to determine the amount of 210Pb in the mine atmosphere ... atmosphere relative to that which would be produced from the decay of the short-lived radon daughters deposited in the lungs. Radium-226 was also measured in air so as ...

RICHARD L. BLANCHARD

1969-07-19T23:59:59.000Z

43

2012 Domestic Uranium Production Report  

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

4. U.S. uranium mills by owner, location, capacity, and operating status at end of the year, 2008-2012" 4. U.S. uranium mills by owner, location, capacity, and operating status at end of the year, 2008-2012" "Mill Owner","Mill Name","County, State (existing and planned locations)","Milling Capacity","Operating Status at End of the Year" ,,,"(short tons of ore per day)",2008,2009,2010,2011,2012 "Cotter Corporation","Canon City Mill","Fremont, Colorado",0,"Standby","Standby","Standby","Reclamation","Demolished" "EFR White Mesa LLC","White Mesa Mill","San Juan, Utah",2000,"Operating","Operating","Operating","Operating","Operating"

44

3rd Quarter 2013 Domestic Uranium Production Report  

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

2 2 U.S. Energy Information Administration / 3rd Quarter 2013 Domestic Uranium Production Report 3rd Quarter 2013 Domestic Uranium Production Report Release Date: October 31, 2013 Next Release Date: February 2014 Table 1. Total production of uranium concentrate in the United States, 1996 - 3rd Quarter 2013 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 1,018,683 983,330 981,948 973,585 3,975,545 2001 709,177 748,298 628,720 553,060 2,639,256 2002 620,952 643,432 579,723 E500,000 E2,344,107 2003 E400,000 E600,000 E400,000 E600,000

45

Increase in uranium concentration in streams draining Rocky Flats, Colorado  

Science Journals Connector (OSTI)

Uranium has been determined by fission track measurements of two suites of water samples taken at different times from a variety of surface waters in an area in central Colorado. Although this area surrounds the Rocky Flats nuclear plant at which parts for weapons are fabricated, the variations in U are inferred to be influenced most strongly by the distance of water flow across soil derived from the U-rich Laramie Formation. This flow produces progressive increases in U concentrations as flow proceeds eastward and hence is much more closely related to the local geochemistry and geology than to the presence of the Rocky Flats plant.

A.C. Delany; R.L. Fleischer

1978-01-01T23:59:59.000Z

46

President Truman Increases Production of Uranium and Plutonium | National  

National Nuclear Security Administration (NNSA)

Increases Production of Uranium and Plutonium | National Increases Production of Uranium and Plutonium | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > President Truman Increases Production of Uranium and Plutonium President Truman Increases Production of Uranium and Plutonium October 09, 1950

47

Capstone Depleted Uranium Aerosol Biokinetics, Concentrations, and Doses  

SciTech Connect

One of the principal goals of the Capstone Depleted Uranium (DU) Aerosol Study was to quantify and characterize DU aerosols generated inside armored vehicles by perforation with a DU penetrator. This study consequently produced a database in which the DU aerosol source terms were specified both physically and chemically for a variety of penetrator-impact geometries and conditions. These source terms were used to calculate radiation doses and uranium concentrations for various scenarios as part of the Capstone DU Human Health Risk Assessment (HHRA). This paper describes the scenario-related biokinetics of uranium, and summarizes intakes, chemical concentrations to the organs, and E(50) and HT(50) for organs and tissues based on exposure scenarios for personnel in vehicles at the time of perforation as well as for first responders. For a given exposure scenario (duration time and breathing rates), the range of DU intakes among the target vehicles and shots was not large, about a factor of 10, with the lowest being from a ventilated operational Abrams tank and the highest being for an unventilated Abrams with DU penetrator perforating DU armor. The ranges of committed effective doses were more scenario-dependent than were intakes. For example, the largest range, a factor of 20, was shown for scenario A, a 1-min exposure, whereas, the range was only a factor of two for the first-responder scenario (E). In general, the committed effective doses were found to be in the tens of mSv. The risks ascribed to these doses are discussed separately.

Guilmette, Raymond A.; Miller, Guthrie; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

48

RIB Production with Photofission of Uranium  

E-Print Network (OSTI)

The process of uranium photofission with electron beams of 20 div 50 MeV is considered in terms of the production of fission fragments. It is shown that in the interaction between an electron beam (25 MeV in energy and 20 mu A in intensity), produced by a compact accelerator of the microtron type, and a uranium target of about 40 g/cm^2 in thickness, an average of 1.5 cdot 10^11 fission events/second is generated. According to the calculations and test experiments, this corresponds to the yield of ^132 Sn and ^142 Xe isotopes of approximately 2 cdot 10^9/s. The results of experiments on the optimal design of the U-target are presented. Problems are discussed connected with the separation of isotopes and isobars for their furher acceleration up to energies of 5-18 MeV/n. The photofission reactions of a heavy nucleus are compared with other methods of RIB production of medium mass nuclei.

Oganessian, Yu T; Kliman, J; Maslov, O D; Starodub, G Ya; Belov, A G; Tretyakova, S P

2002-01-01T23:59:59.000Z

49

Uranium industry annual 1996  

SciTech Connect

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.

NONE

1997-04-01T23:59:59.000Z

50

3rd Quarter 2013 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" 2. Number of uranium mills and plants producing uranium concentrate in the United States" "Uranium Concentrate Processing Facilities","End of 1996","End of 1997","End of 1998","End of 1999","End of 2000","End of 2001","End of 2002","End of 2003","End of 2004","End of 2005","End of 2006","End of 2007","End of 2008","End of 2009","End of 2010","End of 2011","End of 2012","End of 3rd Quarter 2013" "Mills - conventional milling 1",0,0,0,1,1,0,0,0,0,0,0,0,1,0,1,1,1,0 "Mills - other operations 2",2,3,2,2,2,1,1,0,0,1,1,1,0,1,0,0,0,1 "In-Situ-Leach Plants 3",5,6,6,4,3,3,2,2,3,3,5,5,6,3,4,5,5,5

51

Determination of Uranium Metal Concentration in Irradiated Fuel Storage Basin Sludge Using Selective Dissolution  

SciTech Connect

Uranium metal corroding in water-saturated sludges now held in the US Department of Energy Hanford Site K West irradiated fuel storage basin can create hazardous hydrogen atmospheres during handling, immobilization, or subsequent transport and storage. Knowledge of uranium metal concentration in sludge thus is essential to safe sludge management and process design, requiring an expeditious routine analytical method to detect uranium metal concentrations as low as 0.03 wt% in sludge even in the presence of 30 wt% or higher total uranium concentrations.

Delegard, Calvin H.; Sinkov, Sergey I.; Chenault, Jeffrey W.; Schmidt, Andrew J.; Welsh, Terri L.; Pool, Karl N.

2014-03-01T23:59:59.000Z

52

3rd Quarter 2013 Domestic Uranium Production Report  

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

3rd Quarter 2013 Domestic Uranium Production Report 3rd Quarter 2013 Domestic Uranium Production Report 3rd Quarter 2013 Domestic Uranium Production Report Release Date: October 31, 2013 Next Release Date: February 2014 Capacity (short tons of ore per day) 2012 1st Quarter 2013 2nd Quarter 2013 3rd Quarter 2013 EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating-Processing Alternate Feed Energy Fuels Resources Corporation Piñon Ridge Mill Montrose, Colorado 500 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Permitted And Licensed Energy Fuels Wyoming Inc Sheep Mountain Fremont, Wyoming 725 - Undeveloped Undeveloped Undeveloped Kennecott Uranium Company/Wyoming Coal Resource Company Sweetwater Uranium Project Sweetwater, Wyoming 3,000

53

Temporal variability of uranium concentrations and 234 activity ratios in the Mississippi river and its tributaries  

E-Print Network (OSTI)

Temporal variability of uranium concentrations and 234 U/238 U activity ratios in the Mississippi Department of Geology and Geophysics, Texas A&M University, College Station, TX 77845, United States c/238 U activity ratios and total dissolved uranium concentrations in the Lower Mississippi River at New

54

Physicochemical Characterization of Capstone Depleted Uranium Aerosols I: Uranium Concentration in Aerosols as a Function of Time and Particle Size  

SciTech Connect

During the Capstone Depleted Uranium (DU) Aerosol Study, aerosols containing depleted uranium were produced inside unventilated armored vehicles (i.e., Abrams tanks and Bradley Fighting Vehicles) by perforation with large-caliber DU penetrators. These aerosols were collected and characterized, and the data were subsequently used to assess human health risks to personnel exposed to DU aerosols. The DU content of each aerosol sample was first quantified by radioanalytical methods, and selected samples, primarily those from the cyclone separator grit chambers, were analyzed radiochemically. Deposition occurred inside the vehicles as particles settled on interior surfaces. Settling rates of uranium from the aerosols were evaluated using filter cassette samples that collected aerosol as total mass over eight sequential time intervals. A moving filter was used to collect aerosol samples over time particularly within the first minute after the shot. The results demonstrate that the peak uranium concentration in the aerosol occurred in the first 10 s, and the concentration decreased in the Abrams tank shots to about 50% within 1 min and to less than 2% 30 min after perforation. In the Bradley vehicle, the initial (and maximum) uranium concentration was lower than those observed in the Abrams tank and decreased more slowly. Uranium mass concentrations in the aerosols as a function of particle size were evaluated using samples collected in the cyclone samplers, which collected aerosol continuously for 2 h post perforation. The percentages of uranium mass in the cyclone separator stages from the Abrams tank tests ranged from 38% to 72% and, in most cases, varied with particle size, typically with less uranium associated with the smaller particle sizes. Results with the Bradley vehicle ranged from 18% to 29% and were not specifically correlated with particle size.

Parkhurst, MaryAnn; Cheng, Yung-Sung; Kenoyer, Judson L.; Traub, Richard J.

2009-03-01T23:59:59.000Z

55

Uranium Industry Annual, 1992  

SciTech Connect

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

Not Available

1993-10-28T23:59:59.000Z

56

3rd Quarter 2014 Domestic Uranium Production Report  

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

2nd quarter 3rd quarter 4th quarter P Preliminary data. Source: U.S. Energy Information Administration: Form EIA-851A and Form EIA-851Q, "Domestic Uranium Production Report."...

57

Calculating Capstone Depleted Uranium Aerosol Concentrations from Beta Activity Measurements  

SciTech Connect

Beta activity measurements were used as surrogate measurements of uranium mass in aerosol samples collected during the field testing phase of the Capstone Depleted Uranium (DU) Aerosol Study. These aerosol samples generated by the perforation of armored combat vehicles were used to characterize the depleted uranium (DU) source term for the subsequent human health risk assessment (HHRA) of Capstone aerosols. Establishing a calibration curve between beta activity measurements and uranium mass measurements is straightforward if the uranium isotopes are in equilibrium with their immediate short-lived, beta-emitting progeny. For DU samples collected during the Capstone study, it was determined that the equilibrium between the uranium isotopes and their immediate short lived, beta-emitting progeny had been disrupted when penetrators had perforated target vehicles. Adjustments were made to account for the disrupted equilibrium and for wall losses in the aerosol samplers. Correction factors for the disrupted equilibrium ranged from 0.16 to 1, and the wall loss correction factors ranged from 1 to 1.92.

Szrom, Fran; Falo, Gerald A.; Parkhurst, MaryAnn; Whicker, Jeffrey J.; Alberth, David P.

2009-03-01T23:59:59.000Z

58

Production and Characterization of Monodisperse Plutonium, Uranium, and Mixed Uranium?Plutonium Particles for Nuclear Safeguard Applications  

Science Journals Connector (OSTI)

Production and Characterization of Monodisperse Plutonium, Uranium, and Mixed Uranium?Plutonium Particles for Nuclear Safeguard Applications ... In order to prevent nuclear proliferation, the isotopic analysis of uranium and plutonium microparticles has strengthened the means in international safeguards for detecting undeclared nuclear activities. ...

Y. Ranebo; N. Niagolova; N. Erdmann; M. Eriksson; G. Tamborini; M. Betti

2010-04-23T23:59:59.000Z

59

Domestic Uranium Production Report 3rd Quarter 2013  

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

Domestic Uranium Production Domestic Uranium Production Report 3rd Quarter 2013 October 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | 3rd Quarter 2013 Domestic Uranium Production Report ii This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. October 2013

60

Method for the production of uranium chloride salt  

DOE Patents (OSTI)

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.

Westphal, Brian R.; Mariani, Robert D.

2013-07-02T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Uranium industry annual 1998  

SciTech Connect

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

NONE

1999-04-22T23:59:59.000Z

62

Uranium industry annual 1994  

SciTech Connect

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

NONE

1995-07-05T23:59:59.000Z

63

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

E-Print Network (OSTI)

??The research in this thesis covers the design and implementation of a depleted uranium (DU) powder production system and the initial results of a DU-Zr-Mg (more)

Garnetti, David J.

2010-01-01T23:59:59.000Z

64

Method for making a uranium chloride salt product  

DOE Patents (OSTI)

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.

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

2004-10-05T23:59:59.000Z

65

3rd Quarter 2013 Domestic Uranium Production Report  

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

4. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status" 4. U.S. uranium in-situ-leach plants by owner, location, capacity, and operating status" "In-Situ-Leach Plant Owner","In-Situ-Leach Plant Name","County, State (existing and planned locations)","Production Capacity (pounds U3O8 per year)","Operating Status at End of" ,,,,2012,"1st Quarter 2013","2nd Quarter 2013","3rd Quarter 2013" "Cameco","Crow Butte Operation","Dawes, Nebraska",1000000,"Operating","Operating","Operating","Operating" "Hydro Resources, Inc.","Church Rock","McKinley, New Mexico",1000000,"Partially Permitted And Licensed","Partially Permitted And Licensed","Partially Permitted And Licensed","Partially Permitted And Licensed"

66

ARM - Evaluation Product - Droplet Number Concentration Value-Added Product  

NLE Websites -- All DOE Office Websites (Extended Search)

ProductsDroplet Number Concentration Value-Added ProductsDroplet Number Concentration Value-Added Product Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Evaluation Product : Droplet Number Concentration Value-Added Product 2005.01.01 - 2010.12.30 Site(s) SGP General Description Cloud droplet number concentration is an important factor in understanding aerosol-cloud interactions. As aerosol concentration increases, it is expected that droplet number concentration, Nd, will increase and droplet size decrease, for a given liquid water path (Twomey 1977), which will greatly affect cloud albedo as smaller droplets reflect more shortwave radiation. However, the magnitude and variability of these processes under different environmental conditions is still uncertain. McComiskey et al.

67

President Truman Increases Production of Uranium and Plutonium...  

National Nuclear Security Administration (NNSA)

Uranium and Plutonium Washington, DC President Truman approves a 1.4 billion expansion of Atomic Energy Commission facilities to produce uranium and plutonium for nuclear weapons...

68

Evaluation of Background Concentrations of Contaminants in an Unusual Desert Arroyo Near a Uranium Mill Tailings Disposal Cell - 12260  

SciTech Connect

The U.S. Department of Energy (DOE) Office of Legacy Management (LM) manages 27 sites that have groundwater containing uranium concentrations above background levels. The distal portions of the plumes merge into background groundwater that can have 50 ?g/L or more uranium. Distinguishing background from site-related uranium is often problematic, but it is critical to determining if remediation is warranted, establishing appropriate remediation goals, and evaluating disposal cell performance. In particular, groundwater at disposal cells located on the upper Cretaceous Mancos Shale may have relatively high background concentrations of uranium. Elevated concentrations of nitrate, selenium, and sulfate accompany the uranium. LM used geologic analogs and uranium isotopic signatures to distinguish background groundwater from groundwater contaminated by a former uranium processing site. The same suite of contaminants is present in groundwater near former uranium processing sites and in groundwater seeps emanating from the Mancos Shale over a broad area. The concentrations of these contaminants in Many Devils Wash, located near LM's Shiprock disposal cell, are similar to those in samples collected from many Mancos seeps, including two analog sites that are 8 to 11 km from the disposal cell. Samples collected from Many Devils Wash and the analog sites have high AR values (about 2.0)-in contrast, groundwater samples collected near the tailings disposal cell have AR values near 1.0. These chemical signatures raise questions about the origin of the contamination seeping into Many Devils Wash. (authors)

Bush, Richard P. [U.S. Department of Energy Office of Legacy Management (United States); Morrison, Stan J. [S.M. Stoller Corporation (United States)

2012-07-01T23:59:59.000Z

69

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

DOE Patents (OSTI)

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.

Herrmann, Steven Douglas

2014-05-27T23:59:59.000Z

70

Uranium industry annual 1995  

SciTech Connect

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

NONE

1996-05-01T23:59:59.000Z

71

Assessment of radon concentration and external gamma radiation level in the environs of Narwapahar uranium mine, India and its radiological significance  

Science Journals Connector (OSTI)

In the environs of uranium mining, milling and processing facilities and in the uranium mineralized terrain, a little higher ambient radon concentration and gamma radiation level may be expected in comparison ...

B. K. Rana; R. M. Tripathi; J. S. Meena

2011-11-01T23:59:59.000Z

72

3rd Quarter 2013 Domestic Uranium Production Report  

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

5 5 3rd Quarter 2013 Domestic Uranium Production Report Release Date: October 31, 2013 Next Release Date: February 2014 2012 1st Quarter 2013 2nd Quarter 2013 3rd Quarter 2013 Cameco Crow Butte Operation Dawes, Nebraska 1,000,000 Operating Operating Operating Operating Hydro Resources, Inc. Church Rock McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Hydro Resources, Inc. Crownpoint McKinley, New Mexico 1,000,000 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Lost Creek ISR, LLC, a subsidiary of Ur- Energy USA Inc. Lost Creek Project Sweetwater, Wyoming 2,000,000 Under Construction Under Construction

73

Uranium series isotopes concentration in sediments at San Marcos and Luis L. Leon reservoirs, Chihuahua, Mexico  

Science Journals Connector (OSTI)

Spatial and temporal distribution of the radioisotopes concentrations were determined in sediments near the surface and core samples extracted from two reservoirs located in an arid region close to Chihuahua City Mexico. At San Marcos reservoir one core was studied while from Luis L. Leon reservoir one core from the entrance and another one close to the wall were investigated. 232 Th -series 238 U -series 40 K and 137 Cs activity concentrations (AC Bq kg?1) were determined by gamma spectrometry with a high purity Ge detector. 238 U and 234 U ACs were obtained by liquid scintillation and alpha spectrometry with a surface barrier detector. Dating of core sediments was performed applying CRS method to 210 Pb activities. Results were verified by 137 Cs AC. Resulting activity concentrations were compared among corresponding surface and core sediments. High 238 U -series AC values were found in sediments from San Marcos reservoir because this site is located close to the Victorino uranium deposit. Low AC values found in Luis L. Leon reservoir suggest that the uranium present in the source of the Sacramento Chuviscar Rivers is not transported up to the Conchos River. Activity ratios (AR) 234 U / 238 U and 238 U / 226 Ra in sediments have values between 0.91.2 showing a behavior close to radioactive equilibrium in the entire basin. 232 Th / 238 U 228 Ra / 226 Ra ARs are witnesses of the different geological origin of sediments from San Marcos and Luis L. Leon reservoirs.

2014-01-01T23:59:59.000Z

74

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

75

Effect of Co-solutes on the Products and Solubility of Uranium...  

NLE Websites -- All DOE Office Websites (Extended Search)

JG Catalano, and DE Giammar.2014."Effect of Co-solutes on the Products and Solubility of Uranium(VI) Precipitated with Phosphate."Chemical Geology 364:66-75. doi:10.1016...

76

Uranium hydrogeochemical survey of well waters from an area around Pie Town, Catron County, West-Central New Mexico, including concentrations of twenty-three additional elements  

SciTech Connect

As part of the Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the National Uranium Resource Evaluation (NURE) sponsored by the US Department of Energy (DOE), the Los Alamos Scientific Laboratory (LASL) conducted a detailed hydrogeochemical survey of well waters in a 4250-km/sup 2/ area near Pie Town in west-central New Mexico. A total of 300 well samples was collected and analyzed for uranium and 23 other elements. The results of these analyses and carbonate and bicarbonate ion concentrations are presented in the Appendixes of this report. Uranium concentrations range from below the detection limit of 0.02 parts per billion (ppB) to 293.18 ppB and average 8.71 ppB. Samples containing high levels of uranium were collected from the Largo Creek valley west of Quemado, from a small area about 6 km east of Quemado, from a small area surrounding Pie Town, and from scattered locations in the area surrounding Adams Diggings north of Pie Town. Most of the samples containing high uranium concentrations were collected from wells associated with the volcanic sedimentary facies of the Datil formation. This formation is a likely source of mobile uranium that may be precipitating in the underlying Baca formation, a known uranium host unit. Bicarbonate ion concentration, while proportional to uranium concentration in some cases, is not a strong controlling factor in the uranium concentrations in samples from this area.

Morgan, T.L.; George, W.E.; Hensley, W.K.; Thomas, G.J.; Langhorst, A.L.

1980-10-01T23:59:59.000Z

77

Uranium: Environmental Pollution and Health Effects  

Science Journals Connector (OSTI)

Uranium is found ubiquitously in nature in low concentrations in soil, rock, and water. Naturally occurring uranium contains three isotopes, namely 238U, 235U, and 234U. All uranium isotopes have the same chemical properties, but they have different radiological properties. The main civilian use of uranium is to fuel nuclear power plants, whereas high enriched (in 235U) uranium is used in the military sector as nuclear explosives and depleted uranium (DU) as penetrators or tank shielding. Exposure to uranium may cause health problems due to its radiological (uranium is predominantly emitting alpha-particles) and chemical actions (heavy metal toxicity). Uranium uptake may occur by ingestion, inhalation, contaminated wounds, and embedded fragments especially for soldiers. Inhalation of dust is considered the major pathway for uranium uptake in workplaces. Soluble uranium compounds tend to quickly pass through the body, whereas insoluble uranium compounds pose a more serious inhalation exposure hazard. The kidney is the most sensitive organ for uranium chemotoxicity. An important indirect radiological effect of uranium is the increased risk of lung cancers from inhalation of the daughter products of radon, a noble gas in the uranium decay chains that transports uranium-derived radioactivity from soil into the indoor environment. No direct evidence about the carcinogenic effect of DU in humans is available yet.

D. Melo; W. Burkart

2011-01-01T23:59:59.000Z

78

Production of fullerenes using concentrated solar flux  

DOE Patents (OSTI)

A method of producing soot containing high amounts of fullerenes comprising: providing a primary concentrator capable of impingement of a concentrated beam of sunlight onto a carbon source to cause vaporization of carbon and subsequent formation of fullerenes, or providing a solar furnace having a primary concentrator with a focal point that concentrates a solar beam of sunlight; providing a reflective secondary concentrator having an entrance aperture and an exit aperture at the focal point of the solar furnace; providing a carbon source at the exit aperture of the secondary concentrator; supplying an inert gas over the carbon source to keep the secondary concentrator free from vaporized carbon; and impinging a concentrated beam of sunlight from the secondary concentrator on the carbon source to vaporize the carbon source into a soot containing high amounts of fullerenes.

Fields, Clark L. (Greeley, CO); Pitts, John Roland (Lakewood, CO); King, David E. (Lakewood, CO); Hale, Mary Jane (Golden, CO); Bingham, Carl E. (Denver, CO); Lewandowski, Allan A. (Evergreen, CO)

2000-01-01T23:59:59.000Z

79

Towards a desalination initiative using cogeneration with an advanced reactor type and uranium recovered from Moroccan phosphoric acid production  

Science Journals Connector (OSTI)

Morocco is known to be among the first few countries to produce phosphate and phosphoric acid. Moroccan phosphate contains substantial amounts of uranium. This uranium can be recovered from the phosphate ore as a by-product during the production of phosphoric acid. Uranium extraction processes linked with phosphoric acid fabrication have been used industrially in some countries. This is done mainly by solvent extraction. Although, the present price of uranium is low in the international market, such uranium recovery could be considered as a side product of phosphoric acid production. The price of uranium has a very small impact on the cost of nuclear energy obtained from it. This paper focuses on the extraction of uranium salt from phosphate rock. If uranium is recovered in Morocco in the proposed manner, it could serve as feed for a number of nuclear power plants. The natural uranium product would have to be either enriched or blended as mixed-oxide fuel to manufacture adequate nuclear fuel. Part of this fuel would feed a desalination initiative using a high temperature reactor of the new generation, chosen for its intrinsic safety, sturdiness, ease of maintenance, thermodynamic characteristics and long fuel life between reloads, that is, good economy. ?n international cooperation based on commercial contract schemes would concern: the general project and uranium extraction; uranium enrichment and fuel fabrication services; the nuclear power plant; and the desalination plant. This paper presents the overall feasibility of the general project with some quantitative preliminary figures and cost estimates.

Michel Lung; Abdelaali Kossir; Driss Msatef

2005-01-01T23:59:59.000Z

80

E-Print Network 3.0 - anthropogenic uranium concentration Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

Source: Oak Ridge National Laboratory Fossil Energy Program Collection: Fossil Fuels 6 geology and Ranger 1 open-pit uranium mine in Australia Summary: in ore formations with...

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Depleted uranium  

Science Journals Connector (OSTI)

The potential health effects arising from exposure to depleted uranium have been much in the news of late. Naturally occurring uranium contains the radioisotopes 238U (which dominates, at a current molar proportion of 99.3%), 235U and a small amount of 234U. Depleted uranium has an isotopic concentration of 235U that is below the 0.7% found naturally. This is either because the uranium has passed through a nuclear reactor which uses up some of the fissile 235U that fuels the fission chain-reaction, or because it is the uranium that remains when enriched uranium with an elevated concentration of 235U is produced in an enrichment plant, or because of a combination of these two processes. Depleted uranium has a lower specific activity than naturally occurring uranium because of the lower concentrations of the more radioactive isotopes 235U and 234U, but account must be taken of any contaminating radionuclides or exotic radioisotopes of uranium if the uranium has been irradiated. Uranium is a particularly dense element (about twice as dense as lead), and this property makes it useful in certain military applications, such as armour-piercing munitions. Depleted uranium, rather than natural uranium, is used because of its availability and, since the demise of the fast breeder reactor programme, the lack of alternative use. Depleted uranium weapons were used in the Gulf War of 1990 and also, to a lesser extent, more recently in the Balkans. This has led to speculation that depleted uranium may be associated with `Gulf War Syndrome', or other health effects that have been reported by military and civilian personnel involved in these conflicts and their aftermath. Although, on the basis of present scientific knowledge, it seems most unlikely that exposure to depleted uranium at the levels concerned could produce a detectable excess of adverse health effects, and in such a short timescale, the issue has become one of general concern and contention. As a consequence, any investigation needs to be thorough to produce sufficiently comprehensive evidence to stand up to close scrutiny and gain the support of the public, whatever the conclusions. Unfortunately, it is the nature of such inquiries that they take time, which is frustrating for some. In the UK, the Royal Society has instigated an independent investigation into the health effects of depleted uranium by a working group chaired by Professor Brian Spratt. This inquiry has been underway since the beginning of 2000. The working group's findings will be reviewed by a panel appointed by the Council of the Royal Society, and it is anticipated that the final report will be published in the summer of 2001. Further details can be found at www.royalsoc.ac.uk/templates/press/showpresspage.cfm?file=2001010801.txt. Nick Priest has summarised current knowledge on the toxicity (both radiological and chemical) of depleted uranium in a commentary in The Lancet (27 January 2001, 357 244-6). For those wanting to read a comprehensive review of the literature, in 1999 RAND published `A Review of the Scientific Literature as it Pertains to Gulf War Illnesses, Volume 7: Depleted Uranium' by Naomi Harley and her colleagues, which can be found at www.rand.org/publications/MR/MR1018.7/MR1018.7.html. An interesting article by Jan Olof Snihs and Gustav Akerblom entitled `Use of depleted uranium in military conflicts and possible impact on health and environment' was published in the December 2000 issue of SSI News (pp 1-8), and can be found at the website of the Swedish Radiation Protection Institute: www.ssi.se/tidningar/PDF/lockSSIn/SSI-news2000.pdf. Last year, a paper was published in the June issue of this Journal that is of some relevance to depleted uranium. McGeoghegan and Binks (2000 J. Radiol. Prot. 20 111-37) reported the results of their epidemiological study of the health of workers at the Springfields uranium production facility near Preston during 1946-95. This study included almost 14 000 radiation workers. Although organ-specific doses due to uranium are not yet available for these worker

Richard Wakeford

2001-01-01T23:59:59.000Z

82

Characterization of uranium corrosion product colloids by dynamic light scattering.  

SciTech Connect

The Department of Energy plans to dispose of approximately 2100 metric tons of spent metallic uranium fuel in the mined repository at Yucca Mountain. Laboratory studies at Argonne National Laboratory have shown that corrosion of metallic uranium fuel with groundwater generates significant quantities of stable colloids. This finding is considered very important in light of the recent report (1) of rapid subsurface transport of radionuclides at the Nevada Test Site via colloids. Thus, sparingly soluble radionuclides can be transported with the colloids through the subsurface aqueous environment to much greater distances than is predicted based on the aqueous volubility of the radionuclides alone. Accordingly, characterization of colloids generated by fuel corrosion is necessary for assessing the long-term fate and transport of radionuclides in the repository environment.

Mertz, C.; Bowers, D.; Goldberg, M.; Shelton-Davis, C.

2000-11-16T23:59:59.000Z

83

Radionuclide concentrations in agricultural products near the Hanford Site, 1982 through 1992  

SciTech Connect

The Pacific Northwest Laboratory reviewed monitoring data for agricultural products collected from 1982 through 1992 near the Hanford Site to determine radionuclide concentration trends. While samples were collected and analyzed, and results reported annual in Hanford Site environmental reports, an 11-year data set was reviewed for this report to increase the ability to assess trends and potential Hanford effects. Products reviewed included milk, chicken, eggs, beef, vegetables, fruit, wine, wheat, and alfalfa. To determine which radionuclides were detected sufficiently often to permit analysis for trends and effects, each radionuclide concentration and its associated uncertainty were ratioed. Radionuclides were considered routinely detectable if more than 50% of the ratios were between zero and one. Data for these radionuclides were then analyzed statistically, using analyses of variance. The statistical analyses indicated the following: for the most part, there were no measurable effects for Hanford operations; radionuclide concentrations in all products reviewed remained relatively low when compared to concentrations that would result in a 1-mrem effective dose equivalent to an individual; radionuclide concentrations are decreasing in general; however, {sup 90}Sr concentrations in all media and {sup 129}I in milk increased from 1982 to 1986, then decreased gradually for the remainder of the review period. The {sup 129}I concentrations may be correlated with processing of irradiated reactor fuel at the Plutonium-Uranium Extraction (PUREX) Plant.

Antonio, E.J.

1994-06-01T23:59:59.000Z

84

Uranium-238 and thorium-232 series concentrations in soil, radon-222 indoor and drinking water concentrations and dose assessment in the city of Aldama, Chihuahua, Mexico  

Science Journals Connector (OSTI)

High-resolution gamma spectrometry was used to determine the concentration of 40K, 238U and 232Th series in soil samples taken from areas surrounding the city of Aldama, in Chihuahua. Results of indoor air short-time sampling, with diffusion barrier charcoal detectors, revealed relatively high indoor radon levels, ranging from 29 to 422 Bq/m3; the radon concentrations detected exceeded 148 Bq/m3 in 76% of the homes tested. Additionally, liquid scintillation counting showed concentrations of radon in drinking water ranging from 4.3 to 42 kBq/m3. The high activity of 238U in soil found in some places may be a result of the uranium milling process performed 20 years ago in the area. High radon concentrations indoor and in water may be explained by assuming the presence of uranium-bearing rocks underneath of the city, similar to a felsic dike located near Aldama. The estimated annual effective dose of gamma radiation from the soil and radon inhalation was 3.83 mSv.

L. Colmenero Sujo; M.E. Montero Cabrera; L. Villalba; M. Rentera Villalobos; E. Torres Moye; M. Garca Len; R. Garca-Tenorio; F. Mireles Garca; E.F. Herrera Peraza; D. Snchez Aroche

2004-01-01T23:59:59.000Z

85

Concentration, distribution and characteristics of depleted uranium (DU) in the Kosovo ecosystem: A comparison with the uranium behavior in the environment uncontaminated by DU  

Science Journals Connector (OSTI)

The smear samples of the penetrator were analyzed for the determination of the uranium composition. The obtained relative composition (m/m) of uranium isotopes in all the smear samples is...238U, 0.000659-0.00069...

Guogang Jia; M. Belli; U. Sansone

86

Microsoft PowerPoint - Marsden - IPRC 2012- Uranium Product Purity.29 Aug 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

Purity Purity of Uranium Product from Electrochemical Recycling of Used Metallic Fuel K.C. Marsden B.R. Westphal M.N. Patterson B. Pesic 2012 IPRC August 26-29, 2012 Contents  Materials and Fuels Complex (MFC) of the INL  Fuel Conditioning Facility  Processing at the Fuel Conditioning Facility  Value of Uranium Product Purity  Inputs - FFTF Fuel and ER Salt  Dendrite Samples  Final Product Samples  Future Studies 2 Materials and Fuels Complex (MFC) of the INL  ~ 45 km west of Idaho Falls, ~800 employees  Location of former EBR-II reactor  Two hot cell facilities and multiple laboratories for research with irradiated materials - Irradiated Material Characterization Laboratory (IMCL) - Electron Microscopy Laboratory (EML) - Hot Fuel Examination Facility (HFEF) - Fuel Conditioning Facility (FCF) 3 Fuel Conditioning Facility (FCF)  Rectangular

87

Uranium ores and depleted uranium in the environment, with a reference to uranium in the biosphere from the Erzgebirge/Sachsen, Germany  

Science Journals Connector (OSTI)

The Erzgebirge (Ore Mountains) area in the eastern part of Germany was a major source of uranium for Soviet nuclear programs between 1945 and 1989. During this time, the former German Democratic Republic became the third largest uranium producer in the world. The high abundance of uranium in the geological formations of the Erzgebirge are mirrored in the discovery of uranium by M. Klaproth close to Freiberg City in 1789 and the description of the so-called Schneeberg disease, lung cancer caused in miners by the accumulation of the uranium decay product, radon, in the subsurfaces of shafts. Since 1991, remediation and mitigation of uranium at production facilities, rock piles and mill tailings has taken place. In parallel, efforts were initiated to assess the likely adverse effects of uranium mining to humans. The costs of these activities amount to about 6.5 109 Euro. A comparison with concentrations of depleted uranium at certain sites is given.

A Meinrath; P Schneider; G Meinrath

2003-01-01T23:59:59.000Z

88

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

DOE Patents (OSTI)

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.

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

2000-02-29T23:59:59.000Z

89

Investigations on the solubility of corrosion products on depleted uranium projectiles by simulated body fluids and the consequences on dose assessment  

Science Journals Connector (OSTI)

Ingestion and inhalation of corrosion products covering weathered penetrators made of depleted uranium (DU) represent potential radiological exposure pathways. ... juices. About 75 and 36% of the uranium in the c...

Udo C. Gerstmann; Wilfried Szymczak

2008-04-01T23:59:59.000Z

90

ARM Evaluation Product : Droplet Number Concentration Value-Added Product  

SciTech Connect

Cloud droplet number concentration is an important factor in understanding aerosol-cloud interactions. As aerosol concentration increases, it is expected that droplet number concentration, Nd, will increase and droplet size decrease, for a given liquid water path (Twomey 1977), which will greatly affect cloud albedo as smaller droplets reflect more shortwave radiation. However, the magnitude and variability of these processes under different environmental conditions is still uncertain. McComiskey et al. (2009) have implemented a method, based on Boers and Mitchell (1994), for calculating Nd from ground-based remote sensing measurements of optical depth and liquid water path. They show that the magnitude of the aerosol-cloud interactions (ACI) varies with a range of factors, including the relative value of the cloud liquid water path (LWP), the aerosol size distribution, and the cloud updraft velocity. Estimates of Nd under a range of cloud types and conditions and at a variety of sites are needed to further quantify the impacts of aerosol cloud interactions.

Riihimaki, Laura

2014-05-15T23:59:59.000Z

91

Biomedical Engineering Graduate Concentration Fall 2014 Medical Product Development  

E-Print Network (OSTI)

Biomedical Engineering Graduate Concentration ­ Fall 2014 Medical Product Development Advisor: Jan Stegemann, Ph.D. MEDICAL PRODUCT DESIGN AND DEVELOPMENT (both courses are required): BIOMEDE 599.002 Graduate BME Innovative Design Team (3) (I) BIOMEDE 599.004 Graduate BME Innovative Design Team (4) (II

Eustice, Ryan

92

3rd Quarter 2013 Domestic Uranium Production Report  

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

500000,2344107 500000,2344107 2003,400000,600000,400000,600000,2000000 2004,600000,400000,588738,600000,2282406 2005,709600,630053,663068,686456,2689178 2006,931065,894268,1083808,1196485,4105626 2007,1162737,1119536,1075460,1175845,4533578 2008,810189,1073315,980933,1037946,3902383 2009,880036,982760,956657,888905,3708358 2010,876084,1055102,1150725,1146281,4228192 2011,1063047,1189083,846624,892013,3990767 2012,1078404,1061289,1048018,957936,4145647 "P2013",1147031,1394232,1171278,"NA","--" "E = Estimated data." "P = Preliminary data." "NA = Not available." "-- = Not applicable." "Notes: The reported 4th quarter 2002 production amount was adjusted by rounding to the nearest 100,000 pounds to avoid disclosure of individual company data. This also affects the 2002 annual production. The reported 2003 and 1st, 2nd, and 4th quarter 2004 production amounts were adjusted by rounding to the nearest 200,000 pounds to avoid disclosure of individual company data. The reported 2004 total is the actual production for 2004. Totals may not equal sum of components because of independent rounding."

93

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED 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 Draft Supplement Analysis .............................. 1 1.2 Background ....................................................................................................... 3 1.3 Proposed Actions Considered in this Draft Supplement Analysis.................... 4

94

Evaluation of the effect of implanted depleted uranium on male reproductive success, sperm concentration, and sperm velocity  

SciTech Connect

Depleted uranium (DU) projectiles have been used in battle in Iraq and the Balkans and will continue to be a significant armor-penetrating munition for the US military. As demonstrated in the Persian Gulf War, battle injury from DU projectiles and shrapnel is a possibility, and removal of embedded DU fragments from the body is not always practical because of their location in the body or their small size. Previous studies in rodents have demonstrated that implanted DU mobilizes and translocates to the gonads, and natural uranium may be toxic to spermatazoa and the male reproductive tract. In this study, the effects of implanted DU pellets on sperm concentration, motility, and male reproductive success were evaluated in adult (P1) Sprague-Dawley rats implanted with 0, 12, or 20, DU pellets of 1x2 mm or 12 or 20 tantalum (Ta) steel pellets of 1x2 mm. Twenty DU pellets of 1x2 mm (760 mg) implanted in a 500-g rat are equal to approximately 0.2 pound of DU in a 154-lb (70-kg) person. Urinary analysis found that male rats implanted with DU were excreting uranium at postimplantation days 27 and 117 with the amount dependent on dose. No deaths or evidence of toxicity occurred in P1 males over the 150-day postimplantation study period. When assessed at postimplantation day 150, the concentration, motion, and velocity of sperm isolated from DU-implanted animals were not significantly different from those of sham surgery controls. Velocity and motion of sperm isolated from rats treated with the positive control compound {alpha}-chlorohydrin were significantly reduced compared with sham surgery controls. There was no evidence of a detrimental effect of DU implantation on mating success at 30-45 days and 120-145 days postimplantation. The results of this study suggest that implantation of up to 20 DU pellets of 1x2 mm in rats for approximately 21% of their adult lifespan does not have an adverse impact on male reproductive success, sperm concentration, or sperm velocity.

Arfsten, Darryl P. [Naval Health Research Center Detachment, Environmental Health Effects Laboratory, Wright-Patterson AFB, OH 45433 (United States)]. E-mail: darryl.arfsten@wpafb.af.mil; Schaeffer, David J. [Department of Veterinary Biosciences, University of Illinois at Urbana Champaign, Urbana, IL 61802 (United States); Johnson, Eric W. [Naval Health Research Center Detachment, Environmental Health Effects Laboratory, Wright-Patterson AFB, OH 45433 (United States); Robert Cunningham, J. [Naval Health Research Center Detachment, Environmental Health Effects Laboratory, Wright-Patterson AFB, OH 45433 (United States); Still, Kenneth R. [Naval Health Research Center Detachment, Environmental Health Effects Laboratory, Wright-Patterson AFB, OH 45433 (United States); Wilfong, Erin R. [Naval Health Research Center Detachment, Environmental Health Effects Laboratory, Wright-Patterson AFB, OH 45433 (United States)

2006-02-15T23:59:59.000Z

95

Improved Product Energy Intensity Benchmarking Metrics for Thermally Concentrated Food Products  

Science Journals Connector (OSTI)

Improved Product Energy Intensity Benchmarking Metrics for Thermally Concentrated Food Products ... Sogut, Z.; Ilten, N.; Oktay, Z.Energetic and exergetic performance evaluation of the quadruple-effect evaporator unit in tomato paste evaporation Energy 2010, 35, 3821 3826 ...

Michael E. Walker; Craig S. Arnold; David J. Lettieri; Margot J. Hutchins; Eric Masanet

2014-09-12T23:59:59.000Z

96

Design, production, and evaluation of a zircaloy-clad uranium target for an intense pulsed neutron source application  

SciTech Connect

The design of a Zircaloy-2-clad uranium alloy (450 ppm carbon, 250 ppm iron, 350 ppm silicon) target that can function as a pulsed spallation neutron source on interaction of a pulsed 500-MeV proton beam with the uranium nuclei is determined by consideration of irradiation damage, energy deposition, and thermal cycling effects in the target. The designed target is comprised of eight watercooled Zircaloy-2-clad uranium alloy disks, 10 cm in diameter and 2.7 cm thick operating at a maximum uranium alloy centerline temperature of 330/sup 0/C. The production of the Zircaloy-2-clad uranium alloy disks involves remelting of the cast uranium alloy by the consumable electrode technique and bonding of the Zircaloy-2 to the uranium alloy by subjecting the composite to an isostatic-helium pressure at 840/sup 0/C. The lifetime of the disks in the target before cracking of the Zircaloy-2 cladding owing to lowfrequency thermal cycling fatigue is estimated from stress calculations to be about 500 days. The results of thermal cycling tests on a disk tend to confirm the results of the stress calculations.

Loomis, B.A.; Fogle, G.L.; Gerber, S.B.; Thresh, H.R.

1981-12-01T23:59:59.000Z

97

Experimental Measurements of Short-Lived Fission Products from Uranium, Neptunium, Plutonium and Americium  

SciTech Connect

Fission yields are especially well characterized for long-lived fission products. Modeling techniques incorporate numerous assumptions and can be used to deduce information about the distribution of short-lived fission products. This work is an attempt to gather experimental (model-independent) data on the short-lived fission products. Fissile isotopes of uranium, neptunium, plutonium and americium were irradiated under pulse conditions at the Washington State University 1 MW TRIGA reactor to achieve ~108 fissions. The samples were placed on a HPGe (high purity germanium) detector to begin counting in less than 3 minutes post irradiation. The samples were counted for various time intervals ranging from 5 minutes to 1 hour. The data was then analyzed to determine which radionuclides could be quantified and compared to the published fission yield data.

Metz, Lori A.; Payne, Rosara F.; Friese, Judah I.; Greenwood, Lawrence R.; Kephart, Jeremy D.; Pierson, Bruce D.

2009-11-01T23:59:59.000Z

98

Cost Analysis of a Concentrator Photovoltaic Hydrogen Production System  

SciTech Connect

The development of efficient, renewable methods of producing hydrogen are essential for the success of the hydrogen economy. Since the feedstock for electrolysis is water, there are no harmful pollutants emitted during the use of the fuel. Furthermore, it has become evident that concentrator photovoltaic (CPV) systems have a number of unique attributes that could shortcut the development process, and increase the efficiency of hydrogen production to a point where economics will then drive the commercial development to mass scale.

Thompson, J. R.; McConnell, R. D.; Mosleh, M.

2005-08-01T23:59:59.000Z

99

Concentrations and activity ratios of uranium isotopes in groundwater from Donana National Park, South of Spain  

SciTech Connect

The levels and distribution of natural radionuclides in groundwaters from the unconfined Almonte-Marismas aquifer, upon which Donana National Park is located, have been analysed. Most sampled points were multiple piezometers trying to study the vertical distribution of the hydrogeochemical characteristics in the aquifer. Temperature, pH, electrical conductivity, dissolved oxygen and redox potential were determined in the field. A large number of parameters, physico-chemical properties, major and minor ions, trace elements and natural radionuclides (U-isotopes, Th-isotopes, Ra-isotopes and {sup 210}Po), were also analysed. In the southern zone, where aeolian sands crop out, water composition is of the sodium chloride type, and the lower U-isotopes concentrations have been obtained. As water circulates through the aquifer, bicarbonate and calcium concentrations increase slightly, and higher radionuclides concentrations were measured. Finally, we have demonstrated that {sup 234}U/{sup 238}U activity ratios can be used as markers of the type of groundwater and bedrock, as it has been the case for old waters with marine origin confined by a marsh in the south-east part of aquifer.

Bolivar, J. P.; Olias, M.; Gonzalez-Garcia, F. [Department of Applied Physics, University of Huelva, Campus de El Carmen, 21071-Huelva (Spain); Garcia-Tenorio, R. [Department of Applied Physics II, University of Sevilla, ETSA Arquitectura, 41012-Sevilla (Spain)

2008-08-07T23:59:59.000Z

100

EPA Update: NESHAP Uranium Activities  

E-Print Network (OSTI)

for underground uranium mining operations (Subpart B) EPA regulatory requirements for operating uranium mill for Underground Uranium Mining Operations (Subpart B) #12;5 EPA Regulatory Requirements for Underground Uranium uranium mines include: · Applies to 10,000 tons/yr ore production, or 100,000 tons/mine lifetime · Ambient

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While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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101

CONCENTRATES  

Science Journals Connector (OSTI)

The Department of Energy last week denied $2 billion in loan guarantees sought by the global energy company USEC to continue construction of its partially complete centrifuge-based uranium enrichment facility in Piketon, Ohio, which would create low-enrichment uranium (LEU) fuel for nuclear power plants. ... DOE did, however, offer USEC some $45 million in grants for further research. ... Currently, USEC produces about half the nations LEU reactor fuel primarily by down-blending Russian bomb-grade uranium, along with using an older, noncentrifuge-based enrichment technology. ...

2009-08-03T23:59:59.000Z

102

Case Study/ Effects of Groundwater Development on Uranium  

E-Print Network (OSTI)

Case Study/ Effects of Groundwater Development on Uranium: Central Valley, California, USA Abstract Uranium (U) concentrations in groundwater in several parts of the eastern San Joaquin Valley products sold (U.S. Department of 1Corresponding author: U.S. Geological Survey, California Water Science

103

A process for reducing the licensing burden for new products containing depleted uranium.  

SciTech Connect

This report is intended to provide guidance on the process for petitioning the U.S. Nuclear Regulatory Commission (NRC) to initiate a rulemaking that could reduce the licensing burden for new products containing depleted uranium (DU), which are being investigated by the DU Uses Research and Development (R&D) Program at Oak Ridge National Laboratory (ORNL). The focus is on requirements of the NRC rulemaking process applicable to establishing new exemptions or general licenses for products and devices containing source material. NRC policies and guidance regarding such requirements are described, including a 1965 policy statement on approval of new exemptions for products containing radionuclides (''Federal Register'', Volume 30, page 3462 [30 FR 3462]; March 16, 1965) and Regulatory Guide 6.7, which addresses the contents of environmental reports that support rulemaking petitions seeking exemptions for radionuclide-containing products. Methodologies for calculating radiological and nonradiological impacts on human health (i.e., risks) associated with distributing, using, and disposing of DU-containing products are presented. Also, methodologies for completing assessments of the potential effects of accidents involving new DU-containing products and of product misuse are described. The report recommends that the U.S. Department of Energy formulate a regulatory plan for deployment of DU-containing products in areas that are not already radiologically controlled. Such a plan is needed because deployment of new DU-containing products may be difficult under existing NRC licensing requirements. To provide a basis for the regulatory plan, it is recommended that detailed assessments of the radiological and nonradiological risks of distributing, using, and disposing of DU-containing products be conducted. Such assessments should be initiated as soon as sufficient data are available from the ongoing DU Uses R&D Program at ORNL to support the analyses.

Ranek, N. L.; Kamboj, S.; Hartmann, H. M.; Avci, H.

2004-01-06T23:59:59.000Z

104

FAQ 1-What is uranium?  

NLE Websites -- All DOE Office Websites (Extended Search)

What is uranium? What is uranium? What is uranium? Uranium is a radioactive element that occurs naturally in low concentrations (a few parts per million) in soil, rock, and surface and groundwater. It is the heaviest naturally occurring element, with an atomic number of 92. Uranium in its pure form is a silver-colored heavy metal that is nearly twice as dense as lead. In nature, uranium atoms exist as several isotopes: primarily uranium-238, uranium-235, and a very small amount of uranium-234. (Isotopes are different forms of an element that have the same number of protons in the nucleus, but a different number of neutrons.) In a typical sample of natural uranium, most of the mass (99.27%) consists of atoms of uranium-238. About 0.72% of the mass consists of atoms of uranium-235, and a very small amount (0.0055% by mass) is uranium-234.

105

8 - Uranium  

Science Journals Connector (OSTI)

Release of uranium (U) to the environment is mainly through the nuclear fuel cycle. In oxic waters, U(VI) is the predominant redox state, while U(IV) is likely to be encountered in anoxic waters. The free uranyl ion ( UO 2 2 + ) dominates dissolved U speciation at low pH while complexes with hydroxides and carbonates prevail in neutral and alkaline conditions. Whether the toxicity of U(VI) to fish can be predicted based on its free ion concentration remains to be demonstrated but a strong influence of pH has been shown. In the field, U accumulates in bone, liver, and kidney, but does not biomagnify. There is certainly potential for uptake of U via the gill based on laboratory studies; however, diet and/or sediment may be the major route of uptake, and may vary with feeding strategy. Uranium toxicity is low relative to many other metals, and is further reduced by increased calcium, magnesium, carbonates, phosphate, and dissolved organic matter in the water. Inside fish, U produces reactive oxygen species and causes oxidative damage at the cellular level. The radiotoxicity of enriched U has been compared with chemical toxicity and it has been postulated that both may work through a mechanism of production of reactive oxygen species. In practical terms, the potential for chemotoxicity of U outweighs the potential for radiotoxicity. The toxicokinetics and toxicodynamics of U are well understood in mammals, where bone is a stable repository and the kidney the target organ for toxic effects from high exposure concentrations. Much less is known about fish, but overall, U is one of the less toxic metals.

Richard R. Goulet; Claude Fortin; Douglas J. Spry

2011-01-01T23:59:59.000Z

106

A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

3-01 3-01 A Process for Reducing the Licensing Burden for New Products Containing Depleted Uranium Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory, a U.S. Department of Energy Office of Science laboratory, is operated by The University of Chicago under contract W-31-109-Eng-38. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor The University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes

107

Uranium hydrogeochemical and stream sediment reconnaissance data release for the Dubois NTMS Quadrangle, Idaho/Montana, including concentrations of forty-five additional elements  

SciTech Connect

Totals of 1024 water samples and 1600 sediment samples were collected from 1669 locations in the Dubois quadrangle. Water samples were taken at streams, springs, and wells; sediment samples were collected from streams and springs. All field and analytical data are presented for waters in Appendix I-A and for sediments in I-B. All elemental analyses were performed at the LASL. Water samples were initially analyzed for uranium by fluorometry. All water samples containing more than the upper detection limit of uranium were reanalyzed by delayed neutron counting. Sediments were analyzed for uranium and thorium as well as aluminum, antimony, arsenic, barium, beryllium, bismuth, cadmium, calcium, cerium, cesium, chlorine, chromium, cobalt, copper, dysprosium, europium, gold, hafnium, iron, lanthanum, lead, lithium, lutetium, magnesium, manganese, nickel, niobium, potassium rubidium, samarium, scandium, selenium, silver, sodium, strontium, tantalum, terbium, tin, titanium, tungsten, vanadium, ytterbium, zinc and zirconium. All sediments were analyzed for uranium by delayed-neutron counting. Other elemental concentrations in sediments were determined by neutron-activation analysis for 30 elements, by x-ray fluorescence for 12 elements, and by arc-source emission spectrography for 2 elements. Analytical results for sediments are reported as parts per million.

LaDelfe, C.M.

1980-08-01T23:59:59.000Z

108

Uranium hexafluoride public risk  

SciTech Connect

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

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

1994-08-01T23:59:59.000Z

109

Fragment Production in the Interaction of 5.5-GeV Protons with Uranium  

Science Journals Connector (OSTI)

The energy spectra of nuclear fragments produced by the interaction of 5.5-GeV protons with uranium have been determined at several laboratory angles by means of dEdx-E measurements with semiconductor-detector telescopes. Individual isotopes of the elements from hydrogen to carbon were resolved, and from nitrogen to argon the study was continued for the elements without isotopic separation. The evaporation-like energy spectra were integrated to obtain angular distributions and total cross sections for the isotopes of helium through carbon. Total cross sections for many rare isotopes were also estimated. The yield surface constructed from these cross sections has a ridge-like shape positioned one neutron in excess of the line of ? stability. The yields fall off more steeply on the neutron-deficient side and exhibit odd-even effects reflecting those of the mass surface. The energy spectra of the neutron-deficient isotopes differ from the others in that the high-energy parts of the spectra are more pronounced and flatter, and the angular distributions are more forward peaked.Some of the energy spectra were fitted with calculated curves based on the isotropic evaporation of fragments from a system moving along the beam axis. The apparent Coulomb barriers obtained from this analysis were about one half the nominal Coulomb barriers, and the apparent nuclear temperatures fell in the 10- to 13-MeV range. For the highest-energy fragments observed at 90 the apparent temperatures rose to 20 MeV. From the forward-backward shifts in energy it was deduced that the average velocity of the moving system is about 0.006c and that there is a positive correlation between this velocity and the velocity of the fragments in the moving system. However, all of the data are more peaked forward in intensity than can be explained by this simple two-step model.Radiochemical cross sections are also presented for the production of Be7 from uranium, silver, and aluminum, and for Na22 from aluminum.

A. M. Poskanzer; Gilbert W. Butler; Earl K. Hyde

1971-02-01T23:59:59.000Z

110

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

SciTech Connect

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.

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

2006-04-01T23:59:59.000Z

111

Fission Product Yields of Uranium Bombarded with Deuterons of Various Energies (20-190 Mev)  

Science Journals Connector (OSTI)

The formation cross sections of Sr89, Zr97, Pd109, Pd112, Ag111, and Ba140 were measured from the bombardment of natural uranium with deuterons of various energies (20-190 Mev).

Harry G. Hicks; Peter C. Stevenson; Richard S. Gilbert; William H. Hutchin

1955-12-01T23:59:59.000Z

112

The Concentration and Distribution of Depleted Uranium (DU) and Beryllium (Be) in Soil and Air on Illeginni Island at Kwajalein Atoll  

SciTech Connect

Re-entry vehicles on missiles launched at Vandenberg Air Force base in California re-enter at the Western Test Range, the Regan Test Site (RTS) at Kwajalein Atoll. An environmental Assessment (EA) was written at the beginning of the program to assess potential impact of Depleted Uranium (DU) and Beryllium (Be), the major RV materials of interest from a health and environmental perspective. The chemical and structural form of DU and Be in RVs is such that they are insoluble in soil water and sea water. Consequently, residual concentrations of DU and Be observed in soil on the island are not expected to be toxic to plant life because there is essentially no soil to plant uptake. Similarly, due to their insolubility in sea water there is no uptake of either element by marine biota including fish, mollusks, shellfish and sea mammals. No increase in either element has been observed in sea life around Illeginni Island where deposition of DU and Be has occurred. The critical terrestrial exposure pathway for U and Be is inhalation. Concentration of both elements in air over the test period (1989 to 2006) is lower by a factor of 10,000 than the most restrictive U.S. guideline for the general public. Uranium concentrations in air are also lower by factors of 10 to 100 than concentrations of U in air in the U.S. measured by the EPA (Keith et al., 1999). U and Be concentrations in air downwind of deposition areas on Illeginni Island are essentially indistinguishable from natural background concentrations of U in air at the atolls. Thus, there are no health related issues associated with people using the island.

Robison, W L; Hamilton, T F; Martinelli, R E; Gouveia, F J; Lindman, T R; Yakuma, S C

2006-04-27T23:59:59.000Z

113

Thermochemical Production of Fuels with Concentrated Solar Energy  

Science Journals Connector (OSTI)

This review article develops some of the underlying science for converting concentrated solar energy into chemical fuels and presents examples of solar thermochemical processes and...

Steinfeld, Aldo; Weimer, Alan W

2010-01-01T23:59:59.000Z

114

Inositol hexaphosphate: a potential chelating agent for uranium  

Science Journals Connector (OSTI)

......and staining pigments. Depleted uranium, a by-product of uranium...177-193. 2 World Health Organization (WHO). Uranium in drinking-water...the lethal effect of oral uranium poisoning. Health Phys. (2000) 78(6......

D. Cebrian; A. Tapia; A. Real; M. A. Morcillo

2007-11-01T23:59:59.000Z

115

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

SciTech Connect

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.

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

1991-12-31T23:59:59.000Z

116

Estimating concentrations of heat producing elements in the crust near the Sudbury Neutrino Observatory, Ontario, Canada  

E-Print Network (OSTI)

the concentrations of uranium and thorium in the crust must be determined precisely for the future geoneutrino with measure- ments on outcrop and core samples, and with heat flow data. The concentrations of uranium, thorium, and po- tassium from radiometric surveys are correlated with geology, but heat production

117

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

E-Print Network (OSTI)

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

American Society for Testing and Materials. Philadelphia

2005-01-01T23:59:59.000Z

118

Relationship between Air Concentration of Radioactive Fission Products and Fallout  

Science Journals Connector (OSTI)

... with rain or snow. This seems to be true for recent material from the 'Teapot' tests as well as for old fission products collected between December 1954 and February ...

I. H. BLIFFORD; L. B. LOCKHART; R. A. BAUS

1956-05-26T23:59:59.000Z

119

CONCENTRATES  

Science Journals Connector (OSTI)

Worldwide, chemical industry products reduced emissions of greenhouse gases far more than the emissions generated in making these products, according to a study by McKinsey & Co. ... Next came compact fluorescent lighting, fertilizers, and lightweight composite materials. ...

2009-07-13T23:59:59.000Z

120

Nuclear Fuel Facts: Uranium | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Uranium Management and Uranium Management and Policy » Nuclear Fuel 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 minerals such as uraninite. Uranium ore can be mined from open pits or underground excavations. The ore can then be crushed and treated at a mill to separate the valuable uranium from the ore. Uranium may also be dissolved directly from the ore deposits

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

FAQ 5-Is uranium radioactive?  

NLE Websites -- All DOE Office Websites (Extended Search)

Is uranium radioactive? Is uranium radioactive? Is uranium radioactive? All isotopes of uranium are radioactive, with most having extremely long half-lives. Half-life is a measure of the time it takes for one half of the atoms of a particular radionuclide to disintegrate (or decay) into another nuclear form. Each radionuclide has a characteristic half-life. Half-lives vary from millionths of a second to billions of years. Because radioactivity is a measure of the rate at which a radionuclide decays (for example, decays per second), the longer the half-life of a radionuclide, the less radioactive it is for a given mass. The half-life of uranium-238 is about 4.5 billion years, uranium-235 about 700 million years, and uranium-234 about 25 thousand years. Uranium atoms decay into other atoms, or radionuclides, that are also radioactive and commonly called "decay products." Uranium and its decay products primarily emit alpha radiation, however, lower levels of both beta and gamma radiation are also emitted. The total activity level of uranium depends on the isotopic composition and processing history. A sample of natural uranium (as mined) is composed of 99.3% uranium-238, 0.7% uranium-235, and a negligible amount of uranium-234 (by weight), as well as a number of radioactive decay products.

122

Uranium industry annual 1993  

SciTech Connect

Uranium production in the United States has declined dramatically from a peak of 43.7 million pounds U{sub 3}O{sub 8} (16.8 thousand metric tons uranium (U)) in 1980 to 3.1 million pounds U{sub 3}O{sub 8} (1.2 thousand metric tons U) in 1993. This decline is attributed to the world uranium market experiencing oversupply and intense competition. Large inventories of uranium accumulated when optimistic forecasts for growth in nuclear power generation were not realized. The other factor which is affecting U.S. uranium production is that some other countries, notably Australia and Canada, possess higher quality uranium reserves that can be mined at lower costs than those of the United States. Realizing its competitive advantage, Canada was the world`s largest producer in 1993 with an output of 23.9 million pounds U{sub 3}O{sub 8} (9.2 thousand metric tons U). The U.S. uranium industry, responding to over a decade of declining market prices, has downsized and adopted less costly and more efficient production methods. The main result has been a suspension of production from conventional mines and mills. Since mid-1992, only nonconventional production facilities, chiefly in situ leach (ISL) mining and byproduct recovery, have operated in the United States. In contrast, nonconventional sources provided only 13 percent of the uranium produced in 1980. ISL mining has developed into the most cost efficient and environmentally acceptable method for producing uranium in the United States. The process, also known as solution mining, differs from conventional mining in that solutions are used to recover uranium from the ground without excavating the ore and generating associated solid waste. This article describes the current ISL Yang technology and its regulatory approval process, and provides an analysis of the factors favoring ISL mining over conventional methods in a declining uranium market.

Not Available

1994-09-01T23:59:59.000Z

123

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

SciTech Connect

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.

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

2014-01-01T23:59:59.000Z

124

CALIBRATION OF THE HB LINE ACTIVE WELL NEUTRON COINCIDENCE COUNTER FOR MEASUREMENT OF LANL 3013 HIGHLY ENRICHED URANIUM PRODUCT SPLITS  

SciTech Connect

In this paper we describe set-up, calibration, and testing of the F-Area Analytical Labs active well neutron coincidence counter(HV-221000-NDA-X-1-DK-AWCC-1)in SRNL for use in HB-Line to enable assay of 3013EU/Pu metal product. The instrument was required within a three-month window for availability upon receipt of LANL Category IV uranium oxide samples into the SRS HB-Line facility. We describe calibration of the instrument in the SRNL nuclear nondestructive assay facility in the range 10-400 g HEU for qualification and installation in HB-Line for assay of the initial suite of product samples.

Dewberry, R; Donald02 Williams, D; Rstephen Lee, R; David-W Roberts, D; Leah Arrigo, L

2008-01-22T23:59:59.000Z

125

Welding of uranium and uranium alloys  

SciTech Connect

The major reported work on joining uranium comes from the USA, Great Britain, France and the USSR. The driving force for producing this technology base stems from the uses of uranium as a nuclear fuel for energy production, compact structures requiring high density, projectiles, radiation shielding, and nuclear weapons. This review examines the state-of-the-art of this technology and presents current welding process and parameter information. The welding metallurgy of uranium and the influence of microstructure on mechanical properties is developed for a number of the more commonly used welding processes.

Mara, G.L.; Murphy, J.L.

1982-03-26T23:59:59.000Z

126

FAQ 7-How is depleted uranium produced?  

NLE Websites -- All DOE Office Websites (Extended Search)

How is depleted uranium produced? How is depleted uranium produced? How is depleted uranium produced? Depleted uranium is produced during the uranium enrichment process. In the United States, uranium is enriched through the gaseous diffusion process in which the compound uranium hexafluoride (UF6) is heated and converted from a solid to a gas. The gas is then forced through a series of compressors and converters that contain porous barriers. Because uranium-235 has a slightly lighter isotopic mass than uranium-238, UF6 molecules made with uranium-235 diffuse through the barriers at a slightly higher rate than the molecules containing uranium-238. At the end of the process, there are two UF6 streams, with one stream having a higher concentration of uranium-235 than the other. The stream having the greater uranium-235 concentration is referred to as enriched UF6, while the stream that is reduced in its concentration of uranium-235 is referred to as depleted UF6. The depleted UF6 can be converted to other chemical forms, such as depleted uranium oxide or depleted uranium metal.

127

Sodium sulfide leaching of low-grade jamesonite concentrate in production of sodium pyroantimoniate  

Science Journals Connector (OSTI)

Sodium sulfide leaching of a low-grade jamesonite concentrate in the production of sodium pyroantimoniate through the air oxidation process and the influencing factors on the leaching rate of antimony were...

Tian-zu Yang PhD; Ming-xi Jiang

2005-06-01T23:59:59.000Z

128

recycled_uranium.cdr  

Office of Legacy Management (LM)

Recycled Uranium and Transuranics: 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 elements in the uranium feed and waste products throughout the U.S. Department of Energy (DOE) national complex. Subsequently, a DOE agency-wide Recycled Uranium Mass Balance Project (RUMBP) was initiated. For the Weldon Spring Uranium Feed Materials Plant (WSUFMP or later referred to as Weldon Spring),

129

Removing petroleum products from coke-plant wastewater by means of coal concentrates and coking products  

Science Journals Connector (OSTI)

The use of raw materials and products at OAO Moskoks in absorbing petroleum products is explored. These materials are compared with mass-produced carbon absorbers. The possibility of producing carbon adsorbent...

N. P. Zubakhin; V. N. Klushin; D. A. Dmitrieva; E. V. Zenkova

2011-04-01T23:59:59.000Z

130

Uranium Pollution of Meat in Tien-Shan  

Science Journals Connector (OSTI)

Uranium in water, soil, fodder and food products (especially meat) was studied in areas of former Soviet uranium industry in Tien-Shan 19501970. Uranium environment migration was very intensive in Tien-Shan, due...

Rustam Tuhvatshin; Igor Hadjamberdiev

2008-01-01T23:59:59.000Z

131

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

E-Print Network (OSTI)

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

Lam, Oanh Phi

2010-01-01T23:59:59.000Z

132

Depleted uranium management alternatives  

SciTech Connect

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.

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

1994-08-01T23:59:59.000Z

133

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

SciTech Connect

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

NONE

1995-07-05T23:59:59.000Z

134

Simulating the Value of Concentrating Solar Power with Thermal Energy Storage in a Production Cost Model  

SciTech Connect

Concentrating solar power (CSP) deployed with thermal energy storage (TES) provides a dispatchable source of renewable energy. The value of CSP with TES, as with other potential generation resources, needs to be established using traditional utility planning tools. Production cost models, which simulate the operation of grid, are often used to estimate the operational value of different generation mixes. CSP with TES has historically had limited analysis in commercial production simulations. This document describes the implementation of CSP with TES in a commercial production cost model. It also describes the simulation of grid operations with CSP in a test system consisting of two balancing areas located primarily in Colorado.

Denholm, P.; Hummon, M.

2012-11-01T23:59:59.000Z

135

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

SciTech Connect

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

Not Available

1990-01-01T23:59:59.000Z

136

Concentrations of Naturally Occuring Radionuclides and Fission Products in Brick Samples Fabricated and Used in and Around Greater Dhaka City  

Science Journals Connector (OSTI)

...Radiation Protection Dosimetry Article Concentrations of Naturally Occuring Radionuclides and Fission Products in Brick Samples...measures to minimise the harmful effects of ionising radiation. The radium equivalent activity concentrations......

S. Roy; M.S. Alam; F.K. Miah; B. Alam

2000-04-01T23:59:59.000Z

137

Solar trough concentration for fresh water production and waste water treatment  

Science Journals Connector (OSTI)

The present paper examines the concept of utilizing trough type solar concentration plants for water production, remediation and waste treatment. Solar trough plants are a mature technology which deserves to be diffused throughout the European Union and in the partner countries of the Mediterranean Area. The present study is intended to find applications of the solar through concentration technology beyond heat and refrigeration. At the present stage, a number of possibilities have been identified; the main ones which will be considered here are related to clean water production by processes such as solar distillation, atmospheric condensation, and waste processing. Although the technical feasibility of the proposed applications is not in discussion, before attempting to put such applications into practice, well discuss their potential economical and environmental benefits in comparison to existing solutions.

A. Scrivani; T. El Asmar; U. Bardi

2007-01-01T23:59:59.000Z

138

Uranium Resources Inc URI | Open Energy Information  

Open Energy Info (EERE)

Uranium Resources Inc URI Uranium Resources Inc URI Jump to: navigation, search Name Uranium Resources, Inc. (URI) Place Lewisville, Texas Zip 75067 Product Uranium Resources, Inc. (URI) is primarily engaged in the business of acquiring, exploring, developing and mining uranium properties using the in situ recovery (ISR) or solution mining process. References Uranium Resources, Inc. (URI)[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Uranium Resources, Inc. (URI) is a company located in Lewisville, Texas . References ↑ "Uranium Resources, Inc. (URI)" Retrieved from "http://en.openei.org/w/index.php?title=Uranium_Resources_Inc_URI&oldid=352580" Categories: Clean Energy Organizations

139

Statistical data of the uranium industry  

SciTech Connect

Data are presented on US uranium reserves, potential resources, exploration, mining, drilling, milling, and other activities of the uranium industry through 1980. The compendium reflects the basic programs of the Grand Junction Office. Statistics are based primarily on information provided by the uranium exploration, mining, and milling companies. Data on commercial U/sub 3/O/sub 8/ sales and purchases are included. Data on non-US uranium production and resources are presented in the appendix. (DMC)

none,

1981-01-01T23:59:59.000Z

140

Predicting New Hampshire Indoor Radon Concentrations from geologic information and other covariates  

E-Print Network (OSTI)

uranium concentrations (NURE). Fig. 3. Geologic map of Newuranium concentrations (NURE). New Hampshire Geology Geol.Uranium Resource Evaluation (NURE), which were processed (

Apte, M.G.

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Normalisation of spot urine samples to 24-h collection for assessment of exposure to uranium  

Science Journals Connector (OSTI)

......exposed to depleted uranium. Intern...Environ. Health (2006...concentrations of depleted uranium and radiation...shrapnel. Health Phys (2005...Haldimann M. Depleted uranium in Kosovo...workers. Health Phys (2002......

R. Marco; E. Katorza; R. Gonen; U. German; A. Tshuva; O. Pelled; O. Paz-Tal; A. Adout; Z. Karpas

2008-06-01T23:59:59.000Z

142

Uranium hexafluoride handling. Proceedings  

SciTech Connect

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.

Not Available

1991-12-31T23:59:59.000Z

143

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

SciTech Connect

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.

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

2005-07-11T23:59:59.000Z

144

Uranium Metal: Potential for Discovering Commercial Uses  

NLE Websites -- All DOE Office Websites (Extended Search)

Uranium Metal Uranium Metal Potential for Discovering Commercial Uses Steven M. Baker, Ph.D. Knoxville Tn 5 August 1998 Summary Uranium Metal is a Valuable Resource 3 Large Inventory of "Depleted Uranium" 3 Need Commercial Uses for Inventory  Avoid Disposal Cost  Real Added Value to Society 3 Uranium Metal Has Valuable Properties  Density  Strength 3 Market will Come if Story is Told Background The Nature of Uranium Background 3 Natural Uranium: 99.3% U238; 0.7% U 235 3 U235 Fissile  Nuclear Weapons  Nuclear Reactors 3 U238 Fertile  Neutron Irradiation of U238 Produces Pu239  Neutrons Come From U235 Fission  Pu239 is Fissile (Weapons, Reactors, etc.) Post World War II Legacy Background 3 "Enriched" Uranium Product  Weapons Program 

145

Uranium industry annual 1997  

SciTech Connect

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

NONE

1998-04-01T23:59:59.000Z

146

URANIUM IN ALKALINE ROCKS  

E-Print Network (OSTI)

Greenland," in Uranium Exploration Geology, Int. AtomicOklahoma," 1977 Nure Geology Uranium Symposium, Igneous HostMcNeil, M. , 1977. "Geology of Brazil's Uranium and Thorium

Murphy, M.

2011-01-01T23:59:59.000Z

147

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

E-Print Network (OSTI)

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

Di Camillo, Nicole G.

2011-01-01T23:59:59.000Z

148

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

E-Print Network (OSTI)

Renewable Energy Production .Benefits and Renewable Energy Production One source ofauspicious source of renewable energy production from such

Di Camillo, Nicole G.

2011-01-01T23:59:59.000Z

149

Simulation of uranium aluminide dissolution in a continuous aluminum dissolver system  

SciTech Connect

This mission of the Idaho Chemical Processing Plant (ICPP) is to recover highly-enriched uranium from spent nuclear reactor fuel. One fuel type is dissolved in mercury-catalyzed nitric acid, and the uranium is extracted from the resulting dissolver product by an organic solvent. This fuel is composed of an aluminum-alloy-clad matrix of particulate uranium aluminide, which dissolves more slowly than the cladding. Because of the content of fissile {sup 235}U, suspended uranium aluminide or dissolved uranyl nitrate can form a critical mass under some circumstances. The dissolver and piping are geometrically favorable from the criticality standpoint, so the digester is where a criticality event would be most likely to occur. In the digester, the mass limit for {sup 235}U (as suspended uranium aluminide particles) is approximately 790 g. depending on the uranyl nitrate concentration. In a clear dissolver product (no suspended UAl{sub 3}), the concentration limit is 7 g {sup 235}U/L (as uranyl nitrate). Both limits are substantially below the lowest values at which a criticality event could possibly occur. This document a dynamic model of uranium aluminide dissolution in a continuous dissolver system, report typical calculated results, and advance appropriate conclusions.

Evans, D.R.; Farman, R.F.; Christian, J.D.

1990-02-28T23:59:59.000Z

150

Estimating the lung burden from exposure to aerosols of depleted uranium  

Science Journals Connector (OSTI)

......from exposure to aerosols of depleted uranium Marcelo Valdes * * Corresponding...Following exposure to aerosols of depleted uranium (DU), biological samples...uranyl phosphates. INTRODUCTION Depleted uranium (DU) is a waste product of......

Marcelo Valds

2009-02-01T23:59:59.000Z

151

Colorimetric detection of uranium in water  

DOE Patents (OSTI)

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.

DeVol, Timothy A. (Clemson, SC); Hixon, Amy E. (Piedmont, SC); DiPrete, David P. (Evans, GA)

2012-03-13T23:59:59.000Z

152

Goodbye Pareto Principle, Hello Long Tail: The Effect of Search Costs on the Concentration of Product Sales  

E-Print Network (OSTI)

Many markets have historically been dominated by a small number of best-selling products. The Pareto principle, also known as the 80/20 rule, describes this common pattern of sales concentration. However, information ...

Brynjolfsson, Erik

153

What is Depleted Uranium?  

NLE Websites -- All DOE Office Websites (Extended Search)

What is Uranium? What is Uranium? Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects What is Uranium? Physical and chemical properties, origin, and uses of uranium. Properties of Uranium Uranium is a radioactive element that occurs naturally in varying but small amounts in soil, rocks, water, plants, animals and all human beings. It is the heaviest naturally occurring element, with an atomic number of 92. In its pure form, uranium is a silver-colored heavy metal that is nearly twice as dense as lead. In nature, uranium atoms exist as several isotopes, which are identified by the total number of protons and neutrons in the nucleus: uranium-238, uranium-235, and uranium-234. (Isotopes of an element have the

154

Concentrating-collector mass-production feasibility. Volume I. Final report  

SciTech Connect

The Performance Prototype Trough (PPT) Concentrating Collector consists of four 80-foot modules in a 320-foot row. The collector was analyzed, including cost estimates and manufacturing processes to produce collectors in volumes from 100 to 100,000 modules per year. The four different reflector concepts considered were the sandwich reflector structure, sheet metal reflector structure, molded reflector structure, and glass laminate structure. The sheet metal and glass laminate structures are emphasized with their related structure concepts. A preliminary manufacturing plan is offered that includes: documentation of the manufacturing process with production flow diagrams; labor and material costs at various production levels; machinery and equipment requirements including preliminary design specifications; and capital investment costs for a new plant. Of five reflector designs considered, the two judged best and considered at length are thin annealed glass and steel laminate on steel frame panel and thermally sagged glass. Also discussed are market considerations, costing and selling price estimates, design cost analysis and make/buy analysis. (LEW)

Not Available

1981-11-02T23:59:59.000Z

155

Cleaning Products and Air Fresheners: Emissions and Resulting Concentrations of Glycol Ethers and Terpenoids  

E-Print Network (OSTI)

with realistic air-exchange and product usage rates, theand total rate of air freshener product volatilization (26, 589-597. Cleaning Product and Air Freshener Emissions (

Singer, Brett C.; Destaillat, Hugo; Hodgson, Alfred T.; Nazaroff, William W.

2005-01-01T23:59:59.000Z

156

A review of uranium economics  

Science Journals Connector (OSTI)

The recent increase in the demand for power for commercial use, the challenges facing fossil fuel use and the prospective of cheap nuclear power motivate different countries to plan for the use of nuclear power. This paper reviews many aspects of uranium economics, which includes the advantages and disadvantages of nuclear power, comparisons with other sources of power, nuclear power production and requirements, the uranium market, uranium pricing, spot price and long-term price indicators, and the cost of building a nuclear power facility.

A.K. Mazher

2009-01-01T23:59:59.000Z

157

Uranium Mining and Enrichment  

NLE Websites -- All DOE Office Websites (Extended Search)

Overview Presentation » Uranium Mining and Enrichment Overview Presentation » Uranium Mining and Enrichment Uranium Mining and Enrichment Uranium is a radioactive element that occurs naturally in the earth's surface. Uranium is used as a fuel for nuclear reactors. Uranium-bearing ores are mined, and the uranium is processed to make reactor fuel. In nature, uranium atoms exist in several forms called isotopes - primarily uranium-238, or U-238, and uranium-235, or U-235. In a typical sample of natural uranium, most of the mass (99.3%) would consist of atoms of U-238, and a very small portion of the total mass (0.7%) would consist of atoms of U-235. Uranium Isotopes Isotopes of Uranium Using uranium as a fuel in the types of nuclear reactors common in the United States requires that the uranium be enriched so that the percentage of U-235 is increased, typically to 3 to 5%.

158

Estimation of 235U concentration in some depleted uranium samples by high resolution gamma-ray spectrometry using 185 keV and 1001 keV gamma-energies of 235U and 234mPa  

Science Journals Connector (OSTI)

The identification of isotopic composition of depleted uranium obtained after the reprocessing of spent fuel...235U in the reprocessed uranium will be lower and their depletion depends ... of the reactor and burn...

S. Anilkumar; A. K. Deepa; K. Narayani

2007-10-01T23:59:59.000Z

159

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

E-Print Network (OSTI)

plants (U.S. DOE/EIA 2003a, 2003b, 2006). Uranium exploration, mining, and ore processing left a legacy of abandoned uranium mines. The major studies supporting this scoping analysis include EPA's 1983 Report to Congress on the Potential Health and Environmental Hazards of Uranium Mine Wastes (U.S. EPA 1983a, b, c

160

The End of Cheap Uranium  

E-Print Network (OSTI)

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

Michael Dittmar

2011-06-21T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Indoor Radon and Its Decay Products: Concentrations, Causes, and Control Strategies  

E-Print Network (OSTI)

Radon and Its Decay Products in Indoor Air, Wiley, New York.radon daughter products in indoor air, Radiat. Prot. Dosim..and their decay products in indoor air, Health Phys. , 34,

Nero, A.V.

2008-01-01T23:59:59.000Z

162

Estimating terrestrial uranium and thorium by antineutrino flux measurements  

E-Print Network (OSTI)

of uranium and thorium concentrations in geological reservoirs relies largely on geochemi- cal modelEstimating terrestrial uranium and thorium by antineutrino flux measurements Stephen T. Dye, and approved November 16, 2007 (received for review July 11, 2007) Uranium and thorium within the Earth produce

Mcdonough, William F.

163

Thorium, uranium and rare earth elements content in lanthanide concentrate (LC) and water leach purification (WLP) residue of Lynas advanced materials plant (LAMP)  

SciTech Connect

Lynas Advanced Materials Plant (LAMP) has been licensed to produce the rare earths elements since early 2013 in Malaysia. LAMP processes lanthanide concentrate (LC) to extract rare earth elements and subsequently produce large volumes of water leach purification (WLP) residue containing naturally occurring radioactive material (NORM). This residue has been rising up the environmental issue because it was suspected to accumulate thorium with significant activity concentration and has been classified as radioactive residue. The aim of this study is to determine Th-232, U-238 and rare earth elements in lanthanide concentrate (LC) and water leach purification (WLP) residue collected from LAMP and to evaluate the potential radiological impacts of the WLP residue on the environment. Instrumental Neutron Activation Analysis and ?-spectrometry were used for determination of Th, U and rare earth elements concentrations. The results of this study found that the concentration of Th in LC was 1289.7 129 ppm (5274.9 527.6Bq/kg) whereas the Th and U concentrations in WLP were determined to be 1952.917.6 ppm (7987.4 71.9 Bq/kg) and 17.2 2.4 ppm respectively. The concentrations of Th and U in LC and WLP samples determined by ?- spectrometry were 1156 ppm (4728 22 Bq/kg) and 18.8 ppm and 1763.2 ppm (7211.4 Bq/kg) and 29.97 ppm respectively. This study showed that thorium concentrations were higher in WLP compare to LC. This study also indicate that WLP residue has high radioactivity of {sup 232}Th compared to Malaysian soil natural background (63 - 110 Bq/kg) and come under preview of Act 304 and regulations. In LC, the Ce and Nd concentrations determined by INAA were 13.2 0.6% and 4.7 0.1% respectively whereas the concentrations of La, Ce, Nd and Sm in WLP were 0.36 0.04%, 1.6%, 0.22% and 0.06% respectively. This result showed that some amount of rare earth had not been extracted and remained in the WLP and may be considered to be reextracted.

AL-Areqi, Wadeeah M., E-mail: walareqi@yahoo.com; Majid, Amran Ab., E-mail: walareqi@yahoo.com; Sarmani, Sukiman, E-mail: walareqi@yahoo.com [Nuclear Science Programme, School of Chemical Sciences and Food Technology, Faculty of Science and Technology, Universiti Kebangsaan Malaysia, 43600 Bangi (Malaysia)

2014-02-12T23:59:59.000Z

164

Depleted Uranium Health Effects  

NLE Websites -- All DOE Office Websites (Extended Search)

Depleted Uranium Health Effects Depleted Uranium Health Effects Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Depleted Uranium Health Effects Discussion of health effects of external exposure, ingestion, and inhalation of depleted uranium. Depleted uranium is not a significant health hazard unless it is taken into the body. External exposure to radiation from depleted uranium is generally not a major concern because the alpha particles emitted by its isotopes travel only a few centimeters in air or can be stopped by a sheet of paper. Also, the uranium-235 that remains in depleted uranium emits only a small amount of low-energy gamma radiation. However, if allowed to enter the body, depleted uranium, like natural uranium, has the potential for both chemical and radiological toxicity with the two important target organs

165

THE EFFECT OF ANOLYTE PRODUCT ACID CONCENTRATION ON HYBRID SULFUR CYCLE PERFORMANCE  

SciTech Connect

The Hybrid Sulfur (HyS) cycle (Fig. 1) is one of the simplest, all-fluids thermochemical cycles that has been devised for splitting water with a high-temperature nuclear or solar heat source. It was originally patented by Brecher and Wu in 1975 and extensively developed by Westinghouse in the late 1970s and early 1980s. As its name suggests, the only element used besides hydrogen and oxygen is sulfur, which is cycled between the +4 and +6 oxidation states. HyS comprises two steps. One is the thermochemical (>800 C) decomposition of sulfuric acid (H{sub 2}SO{sub 4}) to sulfur dioxide (SO{sub 2}), oxygen (O{sub 2}), and water. H{sub 2}SO{sub 4} = SO{sub 2} + 1/2 O{sub 2} + H{sub 2}O. The other is the SO{sub 2}-depolarized electrolysis of water to H{sub 2}SO{sub 4} and hydrogen (H{sub 2}), SO{sub 2} + 2 H{sub 2}O = H{sub 2}SO{sub 4} + H{sub 2}, E{sup o} = -0.156 V, explaining the 'hybrid' designation. These two steps taken together split water into H{sub 2} and O{sub 2} using heat and electricity. Researchers at the Savannah River National Laboratory (SRNL) and at the University of South Carolina (USC) have successfully demonstrated the use of proton exchange membrane (PEM) electrolyzers (Fig. 2) for the SO{sub 2}-depolarized electrolysis (sulfur oxidation) step, while Sandia National Laboratories (SNL) successfully demonstrated the high-temperature sulfuric acid decomposition (sulfur reduction) step using a bayonet-type reactor (Fig. 3). This latter work was performed as part of the Sulfur-Iodine (SI) cycle Integrated Laboratory Scale demonstration at General Atomics (GA). The combination of these two operations results in a simple process that will be more efficient and cost-effective for the massive production of hydrogen than alkaline electrolysis. Recent developments suggest that the use of PEMs other than Nafion will allow sulfuric acid to be produced at higher concentrations (>60 wt%), offering the possibility of net thermal efficiencies around 50% (HHV basis). The effect of operation at higher anolyte concentrations on the flowsheet, and on the net thermal efficiency for a nuclear-heated HyS process, is examined and quantified.

Gorensek, M.; Summers, W.

2010-03-24T23:59:59.000Z

166

Uranium biokinetics in gavaged young adult female rats.  

E-Print Network (OSTI)

??Blood, liver, kidney, femur, and ovaries were assayed from female Wistar rats following oral administration of uranyl nitrate. Three uranium concentrations were studied for six (more)

Keizer, Philip John

1986-01-01T23:59:59.000Z

167

Maximal Replacement of Forage and Concentrate with a New Wet Corn Milling Product for Lactating Dairy Cows  

Science Journals Connector (OSTI)

Three experiments were conducted to determine the maximal amount of concentrate and forage that could be replaced with a new wet corn milling product. The corn milling product contained 23.1% crude protein, 9.9% ruminally undegradable protein, 13.7% acid detergent fiber, 40.3% neutral detergent fiber, and 2.6% ether extract (% of dry matter; DM). In experiment 1, 16 Holstein cows were assigned to one of four diets in a replicated 4 4 Latin square design with 28-d periods. The four diets contained 54.3% forage (alfalfa:corn silages, 1:1 DM basis) with the wet corn milling product replacing 0, 50, 75, or 100% of the concentrate portion (corn and soybean meal) of the diet (DM basis). The diets containing wet corn milling product resulted in 7.8% lower DM intake, equivalent milk production (28.5 kg/d), and 13.6% greater efficiency of 4% fat-corrected milk (FCM) production than the control diet. There was no effect of diet on ruminal pH. In experiment 2, 16 Holstein cows were assigned to one of four diets in a replicated 4 4 Latin square design with 28-d periods. The 100% concentrate replacement diet from experiment 1 was used as control diet. For the test diets, forage was replaced with 15, 30, or 45% of the corn milling product (DM basis). Efficiency of FCM production (1.16) was not affected by diet. Rumination time was reduced for the 30 and 45% forage replacement diets, but ruminal pH was unaffected. In experiment 3, 30 Holstein cows were assigned at parturition to either a control diet (no corn milling product) or a diet containing 40% corn milling feed in place of both forage and concentrate (optimal levels from experiments 1 and 2) for 9 wk. The diet containing corn milling feed resulted in 21% greater efficiency of FCM production than the control diet. These results indicate that a new feed product based on wet corn milling ingredients has the potential to effectively replace all of the concentrate and up to 45% of the forage in the diet for lactating dairy cows.

K. Boddugari; R.J. Grant; R. Stock; M. Lewis

2001-01-01T23:59:59.000Z

168

Concentration of Beryllium (Be) and Depleted Uranium (DU) in Marine Fauna and Sediment Samples from Illeginni and Boggerik Islands at Kwajalein Atoll  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) personnel have supported US Air Force (USAF) ballistic missile flight tests for about 15 years for Peacekeeper and Minuteman missiles launched at Vandenberg Air Force Base (VAFB). Associated re-entry vehicles (RV's) re-enter at Regan Test Site (RTS) at the US Army base at Kwajalein Atoll (USAKA) where LLNL has supported scoring, recovery operations for RV materials, and environmental assessments. As part of ongoing USAF ballistic missile flight test programs, LLNL is participating in an updated EA being written for flights originating at VFAB. Marine fauna and sediments (beach-sand samples) were collected by US Fish and Wildlife Service (USFWS), National Marine Fisheries Service (NMFS), and LLNL at Illeginni Island and Boggerik Island (serving as a control site) at Kwajalein Atoll. Data on the concentration of DU (hereafter, U) and Be in collected samples was requested by USFWS and NMFS to determine whether or not U and Be in RV's entering the Illeginni area are increasing U and Be concentrations in marine fauna and sediments. LLNL agreed to do the analyses for U and Be in support of the EA process and provide a report of the results. There is no statistically significant difference in the concentration of U and Be in six species of marine fauna from Illeginni and Boggerik Islands (p - 0.14 for U and p = 0.34 for Be). Thus, there is no evidence that there has been any increase in U and Be concentrations in marine fauna as a result of the missile flight test program. Concentration of U in beach sand at Illeginni is the same as soil and beach sand in the rest of the Marshall Islands and again reflects an insignificant impact from the flight test program. Beach sand from Illeginni has a mean concentration of Be higher than that from the control site, Boggeik Island. Seven of 21 samples from Ileginni had detectable Be. Four samples had a concentration of Be ranging from 4 to 7 ng g {sup -1} (4 to 7 parts per billion (ppb)), one was 17 ppb, one was 0.14 parts per million (ppm), and one was 0.48 ppm. These extremely low concentrations of an insoluble form of Be again indicate no impact on marine life or human health at Illeginni as a result of the missile flight test program. Concentration of Fe in marine fauna muscle tissue is much higher at Illeginni Island than at Boggerik Island (control site) as a result of legacy iron piers, dump sites for iron metal along the island, and scrap iron randomly distributed along extensive portions of the reef line as part of programs conducted in the 1960's through 1980's that were not part of the recent flight test program.

Robison, W L; Hamilton, T F; Martinelli, R E; Kehl, S R; Lindman, T R

2005-02-24T23:59:59.000Z

169

Statistical data of the uranium industry  

SciTech Connect

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

none,

1982-01-01T23:59:59.000Z

170

Long Tails vs. Superstars: The Effect of Information Technology on Product Variety and Sales Concentration Patterns  

E-Print Network (OSTI)

The Internet and related information technologies are transforming the distribution of product sales across products, and these effects are likely to grow in coming years. Both the Long Tail and the Superstar effect are ...

Brynjolfsson, Erik

171

Neurotoxicity of depleted uranium  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a byproduct of the enrichment process of uranium for its more radioactive isotopes to be ... neurotoxicity of DU. This review reports on uranium uses and its published health effects, wit...

George C. -T. Jiang; Michael Aschiner

2006-04-01T23:59:59.000Z

172

Summary of: Simulating the Value of Concentrating Solar Power with Thermal Energy Storage in a Production Cost Model (Presentation)  

SciTech Connect

Concentrating solar power (CSP) deployed with thermal energy storage (TES) provides a dispatchable source of renewable energy. The value of CSP with TES, as with other potential generation resources, needs to be established using traditional utility planning tools. Production cost models, which simulate the operation of grid, are often used to estimate the operational value of different generation mixes. CSP with TES has historically had limited analysis in commercial production simulations. This document describes the implementation of CSP with TES in a commercial production cost model. It also describes the simulation of grid operations with CSP in a test system consisting of two balancing areas located primarily in Colorado.

Denholm, P.; Hummon, M.

2013-02-01T23:59:59.000Z

173

Development of a Monitoring Framework for the Detection of Diversion of Intermediate Products in a Generic Natural Uranium Conversion Plant.  

E-Print Network (OSTI)

??The objective of this work is the development of an on-line monitoring and data analysis framework that could detect the diversion of intermediate products such (more)

Ladd-Lively, Jennifer L.

2013-01-01T23:59:59.000Z

174

Excess Uranium Management  

Energy.gov (U.S. Department of Energy (DOE))

The Department is issuing a Request for Information on the effects of DOE transfers of excess uranium on domestic uranium mining, conversion, and enrichment industries.

175

Production of Si by vacuum carbothermal reduction of SiO2 using concentrated solar energy  

Science Journals Connector (OSTI)

Using concentrated solar radiation as the energy source of high-temperature process heat, the carbothermal reduction of silica to silicon was examined thermodynamically and demonstrated experimentally at vacuu...

Peter G. Loutzenhiser; Ozan Tuerk; Aldo Steinfeld

2010-09-01T23:59:59.000Z

176

Cultivation of algae on highly concentrated municipal wastewater as an energy crop for biodiesel production.  

E-Print Network (OSTI)

??There has been renewed interest in bio-fuel production over the past decade due to the sharp rise in fossil fuel prices and increasing concerns about (more)

Li, Yecong

2012-01-01T23:59:59.000Z

177

Nuclear & Uranium - U.S. Energy Information Administration (EIA)  

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

Nuclear & Uranium Nuclear & Uranium Glossary › FAQS › Overview Data Summary Uranium & Nuclear Fuel Nuclear Power Plants Radioactive Waste International All Nuclear Data Reports Analysis & Projections Most Requested Nuclear Plants and Reactors Projections Uranium All Reports EIA's latest Short-Term Energy Outlook for electricity › chart showing U.S. electricity generation by fuel, all sectors Source: U.S. Energy Information Administration, Short-Term Energy Outlook, released monthly. Quarterly uranium production data › image chart of Quarterly uranium production as described in linked report Source: U.S. Energy Information Administration, Domestic Uranium Production Report - Quarterly, 3rd Quarter 2013, October 31, 2013. Uprates can increase U.S. nuclear capacity substantially without building

178

High grade uranium resources in the United States : an overview  

E-Print Network (OSTI)

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

Graves, Richard E.

1974-01-01T23:59:59.000Z

179

Uranium at Y-12: Inspection | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

radiography. Inspectors examine enriched uranium products using coordinate measuring machines, microscopy, laser inspection machines and other instruments. Technicians use X-rays...

180

Responses of primary production and total carbon storage to changes in climate and atmospheric CO? concentration  

E-Print Network (OSTI)

The authors used the terrestrial ecosystem model (TEM, version 4.0) to estimate global responses of annual net primary production (NPP) and total carbon storage to changes in climate and atmospheric CO2, driven by the ...

Xiao, Xiangming.; Kicklighter, David W.; Melillo, Jerry M.; McGuire, A. David.; Stone, Peter H.; Sokolov, Andrei P.

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Performance and fate of organics in a pilot MBRNF for treating antibiotic production wastewater with recycling NF concentrate  

Science Journals Connector (OSTI)

Abstract A double membrane system comprising a membrane bioreactor (MBR) combined with a nanofiltration (NF) membrane was investigated on a pilot scale for the treatment of antibiotic production wastewater over a three-month period at a pharmaceutical company in Wuxi, China. By recycling the NF concentrate, the combined MBRNF process was shown to be effective for the treatment of antibiotic production wastewater, resulting in excellent water quality and a high water yield of 925.6%. The water quality of the pilot-scale MBRNF process was excellent; e.g., the concentrations of TOC, NH4+-N, TP were stable at 5.52, 0.68, 0.34mgL?1, respectively, and the values of turbidity and conductivity of the NF permeate were 0.15 NTU and 2.5mScm?1, respectively; these values meet Chinas water quality standard requirements for industrial use (GB21903-2008). Not only were the antibiotic removal rates of spiramycin (SPM) and new spiramycin (NSPM) over 95%, the acute toxicity was also drastically reduced by the MBRNF pilot system. The main organics in the MBR effluent were proteins, polysaccharides, and humic-like substances; they were almost completely retained by the NF membrane and further biodegraded in the MBR because the NF concentrate was recycled. The microbial community of the MBR did not significantly change with the recycling of the NF concentrate.

Jianxing Wang; Kun Li; Yuansong Wei; Yutao Cheng; Dongbin Wei; Mingyue Li

2014-01-01T23:59:59.000Z

182

Effect of Gadolinium Doping on the Air Oxidation of Uranium Dioxide  

SciTech Connect

Researchers at the Pacific Northwest National Laboratory (PNNL) investigated the effects of gadolinia concentration on the air oxidization of gadolinia-doped uranium dioxide using thermogravimetry and differential scanning calorimetry to determine if such doping could improve uranium dioxide's stability as a nuclear fuel during potential accident scenarios in a nuclear reactor or during long-term disposal. We undertook this study to determine whether the resistance of the uranium dioxide to oxidation to the orthorhombic U3O8 with its attendant crystal expansion could be prevented by addition of gadolinia. Our studies found that gadolinium has little effect on the thermal initiation of the first step of the reported two-step air oxidation of UO2; however, increasing gadolinia content does stabilize the initial tetragonal or cubic product allowing significant oxidation before the second expansive step to U3O8 begins.

Scheele, Randall D.; Hanson, Brady D.; Cumblidge, Stephen E.; Jenson, Evan D.; Kozelisky, Anne E.; Sell, Rachel L.; MacFarlan, Paul J.; Snow, Lanee A.

2004-12-04T23:59:59.000Z

183

Plutonium recovery from spent reactor fuel by uranium displacement  

DOE Patents (OSTI)

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.

Ackerman, J.P.

1992-03-17T23:59:59.000Z

184

Uranium in natural waters sampled within former uranium mining sites in Kazakhstan and Kyrgyzstan  

Science Journals Connector (OSTI)

New data are presented on 238U concentrations in surface and ground waters sampled at selected uranium mining sites in Kazakhstan and Kyrgyzstan and in water supplies of settlements located in the vicinity of the...

B. M. Uralbekov; B. Smodis; M. Burkitbayev

2011-09-01T23:59:59.000Z

185

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

SciTech Connect

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.

Li, D.; Kaplan, D.

2012-02-29T23:59:59.000Z

186

The End of Cheap Uranium  

E-Print Network (OSTI)

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

Dittmar, Michael

2011-01-01T23:59:59.000Z

187

Uranium Hexafluoride (UF6)  

NLE Websites -- All DOE Office Websites (Extended Search)

Hexafluoride (UF6) Hexafluoride (UF6) Uranium Hexafluoride (UF6) line line Properties of UF6 UF6 Health Effects Uranium Hexafluoride (UF6) Physical and chemical properties of UF6, and its use in uranium processing. Uranium Hexafluoride and Its Properties Uranium hexafluoride is a chemical compound consisting of one atom of uranium combined with six atoms of fluorine. It is the chemical form of uranium that is used during the uranium enrichment process. Within a reasonable range of temperature and pressure, it can be a solid, liquid, or gas. Solid UF6 is a white, dense, crystalline material that resembles rock salt. UF6 crystals in a glass vial image UF6 crystals in a glass vial. Uranium hexafluoride does not react with oxygen, nitrogen, carbon dioxide, or dry air, but it does react with water or water vapor. For this reason,

188

Carbonate Leaching of Uranium from Contaminated Soils  

Science Journals Connector (OSTI)

Uranium (U) was successfully removed from contaminated soils from the Fernald Environmental Management Project (FEMP) site near Fernald, Ohio. ... The concentrations of uranium and other metals in the effluent were analyzed using a Varian Liberty 200 inductively coupled plasma atomic emission spectrophotometer (ICP-AES) or a kinetic phosphorescence analyzer (KPA). ... When 30% hydrogen peroxide (H2O2) was added prior to the carbonate solution, no increase in the removal of uranium was detected (data not shown) due to effervescence with heating, liberating carbon dioxide, and thus preventing uniform distribution of H2O2. ...

C. F. V. Mason; W. R. J. R. Turney; B. M. Thomson; N. Lu; P. A. Longmire; C. J. Chisholm-Brause

1997-09-30T23:59:59.000Z

189

Capstone Depleted Uranium Aerosols: Generation and Characterization  

SciTech Connect

In a study designed to provide an improved scientific basis for assessing possible health effects from inhaling depleted uranium (DU) aerosols, a series of DU penetrators was fired at an Abrams tank and a Bradley fighting vehicle. A robust sampling system was designed to collect aerosols in this difficult environment and continuously monitor the sampler flow rates. Aerosols collected were analyzed for uranium concentration and particle size distribution as a function of time. They were also analyzed for uranium oxide phases, particle morphology, and dissolution in vitro. The resulting data provide input useful in human health risk assessments.

Parkhurst, MaryAnn; Szrom, Fran; Guilmette, Ray; Holmes, Tom; Cheng, Yung-Sung; Kenoyer, Judson L.; Collins, John W.; Sanderson, T. Ellory; Fliszar, Richard W.; Gold, Kenneth; Beckman, John C.; Long, Julie

2004-10-19T23:59:59.000Z

190

Uranium occurrence in igneous rocks of the central Davis Mountains, west Texas  

E-Print Network (OSTI)

is local? sv ized in fewer sites with higher concentrations than in fine-grained rocks. In glasses, uranium is homogeneously dis tributed. Crystalline rocks are uranium-depleted by as much as 30 percent in comparison to glasses of similar composition.... This suggests that uranium is lost during alteration because it is concentrated at grain boundaries in crystalline rocks, where it is accessible to altering solutions. Uranium depletion also occurs in air-fall tuffs because of their permeability. Alteration...

Schaftenaar, Wendy Elizabeth

2012-06-07T23:59:59.000Z

191

Estimates of Radioxenon Released from Southern Hemisphere Medical isotope Production Facilities Using Measured Air Concentrations and Atmospheric Transport Modeling  

SciTech Connect

Abstract The International Monitoring System (IMS) of the Comprehensive-Nuclear-Test-Ban-Treaty monitors the atmosphere for radioactive xenon leaking from underground nuclear explosions. Emissions from medical isotope production represent a challenging background signal when determining whether measured radioxenon in the atmosphere is associated with a nuclear explosion prohibited by the treaty. The Australian Nuclear Science and Technology Organisation (ANSTO) operates a reactor and medical isotope production facility in Lucas Heights, Australia. This study uses two years of release data from the ANSTO medical isotope production facility and Xe-133 data from three IMS sampling locations to estimate the annual releases of Xe-133 from medical isotope production facilities in Argentina, South Africa, and Indonesia. Atmospheric dilution factors derived from a global atmospheric transport model were used in an optimization scheme to estimate annual release values by facility. The annual releases of about 6.81014 Bq from the ANSTO medical isotope production facility are in good agreement with the sampled concentrations at these three IMS sampling locations. Annual release estimates for the facility in South Africa vary from 1.21016 to 2.51016 Bq and estimates for the facility in Indonesia vary from 6.11013 to 3.61014 Bq. Although some releases from the facility in Argentina may reach these IMS sampling locations, the solution to the objective function is insensitive to the magnitude of those releases.

Eslinger, Paul W.; Friese, Judah I.; Lowrey, Justin D.; McIntyre, Justin I.; Miley, Harry S.; Schrom, Brian T.

2014-04-06T23:59:59.000Z

192

Uranium isotopes in ground water as a prospecting technique  

SciTech Connect

The isotopic concentrations of dissolved uranium were determined for 300 ground water samples near eight known uranium accumulations to see if new approaches to prospecting could be developed. It is concluded that a plot of /sup 234/U//sup 238/U activity ratio (A.R.) versus uranium concentration (C) can be used to identify redox fronts, to locate uranium accumulations, and to determine whether such accumulations are being augmented or depleted by contemporary aquifer/ground water conditions. In aquifers exhibiting flow-through hydrologic systems, up-dip ground water samples are characterized by high uranium concentration values (> 1 to 4 ppB) and down-dip samples by low uranium concentration values (less than 1 ppB). The boundary between these two regimes can usually be identified as a redox front on the basis of regional water chemistry and known uranium accumulations. Close proximity to uranium accumulations is usually indicated either by very high uranium concentrations in the ground water or by a combination of high concentration and high activity ratio values. Ground waters down-dip from such accumulations often exhibit low uranium concentration values but retain their high A.R. values. This serves as a regional indicator of possible uranium accumulations where conditions favor the continued augmentation of the deposit by precipitation from ground water. Where the accumulation is being dispersed and depleted by the ground water system, low A.R. values are observed. Results from the Gulf Coast District of Texas and the Wyoming districts are presented.

Cowart, J.B.; Osmond, J.K.

1980-02-01T23:59:59.000Z

193

Uranium contamination of the Aral Sea  

Science Journals Connector (OSTI)

Located in an endorrheic basin, the Aral Sea is mainly fed by water from two large rivers, the Syrdarya and the Amudarya. As a result, contaminants in dissolved and suspended form discharged by the rivers are accumulating in the lake. The northern Small Aral water contained 37g l?1uranium and water in the western basin of the Large Aral up to 141g l?1uranium in 2002, 2004 and 2006. The present day uranium concentrations in Aral Sea water mainly originate from the Syrdarya River due to uranium mining and tailings in the river watershed, and have been elevated up to 5 times compared to the pre-desiccation times by the ongoing desiccation in the western basin of the Large Aral. Current data indicate that groundwater does not seem to contribute much to the uranium budget. The uranium concentration in the lake is controlled by internal lake processes. Due to the high ionic strength of the Aral Sea water uranium is kept soluble. 238U/Cl?mass ratios range from 5.88 to 6.15g g?1in the Small Aral and from 3.00 to 3.32g g?1in the Large Aral. Based on the238U/Cl?mass ratios, a removal rate of 8% uranium from the water column inventory to the sediments has been estimated for anoxic waters, and it ranges between 2% and 5% in oxic waters, over periods of time without mixing. Most of the uranium removal seems to occur by co-precipitation with calcite and gypsum both in anoxic and oxic waters. According to simulations with PHREEQC, uraninite precipitation contributes little to the removal from anoxic Aral Sea water. In most of the sampled locations, water column removal of uranium matches the sediment inventory. Based on budget calculations, the future development of uranium load in the Aral Sea has been estimated for different scenarios. If the Syrdarya River discharge is below or in balance with the loss by evaporation, the uranium concentration in the Small Aral will increase from 37 g l1to 55g l?1in 20years time. When the river discharge is larger than loss by evaporation, present-day uranium concentration in the lake may be kept at the current level or even decrease slightly. From the ecotoxicological point of view, an increase in Syrdarya River discharge as the major water source will be crucial for the water quality of the Small Aral, despite its high uranium load. However, as it is intended to restore fishery in the Small Aral, accumulation of uranium in fish has to be monitored. Since the western basin of the Large Aral received no Syrdarya River water since 2005, and may become disconnected from the eastern basin, the slightly higher observed uranium removal from anoxic waters may result in a decrease in uranium concentrations in the western basin by 20% in 20years time.

Jana Friedrich

2009-01-01T23:59:59.000Z

194

Uranium: Prices, rise, then fall  

SciTech Connect

Uranium prices hit eight-year highs in both market tiers, $16.60/lb U{sub 3}O{sub 8} for non-former Soviet Union (FSU) origin and $15.50 for FSU origin during mid 1996. However, they declined to $14.70 and $13.90, respectively, by the end of the year. Increased uranium prices continue to encourage new production and restarts of production facilities presently on standby. Australia scrapped its {open_quotes}three-mine{close_quotes} policy following the ouster of the Labor party in a March election. The move opens the way for increasing competition with Canada`s low-cost producers. Other events in the industry during 1996 that have current or potential impacts on the market include: approval of legislation outlining the ground rules for privatization of the US Enrichment Corp. (USEC) and the subsequent sales of converted Russian highly enriched uranium (HEU) from its nuclear weapons program, announcement of sales plans for converted US HEU and other surplus material through either the Department of Energy or USEC, and continuation of quotas for uranium from the FSU in the United States and Europe. In Canada, permitting activities continued on the Cigar Lake and McArthur River projects; and construction commenced on the McClean Lake mill.

Pool, T.C.

1997-03-01T23:59:59.000Z

195

Statistical data of the uranium industry  

SciTech Connect

This report is a compendium of information relating to US uranium reserves and potential resources and to exploration, mining, milling, and other activities of the uranium industry through 1982. The statistics are based primarily on data provided voluntarily by the uranium exploration, mining and milling companies. The compendium has been published annually since 1968 and reflects the basic programs of the Grand Junction Area Office of the US Department of Energy. Statistical data obtained from surveys conducted by the Energy Information Administration are included in Section IX. The production, reserves, and drilling data are reported in a manner which avoids disclosure of proprietary information.

none,

1983-01-01T23:59:59.000Z

196

Uranium Processing Facility | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

About / Transforming Y-12 / Uranium Processing Facility About / Transforming Y-12 / Uranium Processing Facility Uranium Processing Facility UPF will be a state-of-the-art, consolidated facility for enriched uranium operations including assembly, disassembly, dismantlement, quality evaluation, and product certification. An integral part of Y-12's transformation efforts and a key component of the National Nuclear Security Administration's Uranium Center of Excellence, the Uranium Processing Facility is one of two facilities at Y-12 whose joint mission will be to accomplish the storage and processing of all enriched uranium in one much smaller, centralized area. Safety, security and flexibility are key design attributes of the facility, which is in the preliminary design phase of work. UPF will be built to modern standards and engage new technologies through a responsive and agile

197

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

SciTech Connect

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.

NONE

1995-07-05T23:59:59.000Z

198

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and 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 low-enriched uranium hexafluoride (LEUF6) at the DOE Paducah site in western Kentucky (DOE Paducah) and the DOE Portsmouth site near Piketon in south-central Ohio (DOE Portsmouth)1. This inventory exceeds DOE's current and projected energy and defense program needs. On March 11, 2008, the Secretary of Energy issued a policy statement (the

199

The ultimate disposition of depleted uranium  

SciTech Connect

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.

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

1991-12-31T23:59:59.000Z

200

Depleted Uranium Technical Brief  

E-Print Network (OSTI)

and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological healthDepleted Uranium Technical Brief United States Environmental Protection Agency Office of Air

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Geological conditions of safe long-term storage and disposal of depleted uranium hexafluoride  

Science Journals Connector (OSTI)

The production of enriched uranium used in nuclear weapons and fuel for ... power plants is accompanied by the formation of depleted uranium (DU), the amount of which annually ... DU mass is stored as environ-men...

N. P. Laverov; V. I. Velichkin; B. I. Omelyanenko

2010-08-01T23:59:59.000Z

202

Effects of Depleted Uranium on Oxidative Stress, Detoxification, and Defence Parameters of Zebrafish Danio rerio  

Science Journals Connector (OSTI)

In this study, we investigated the effects of depleted uranium (DU), the by-product of nuclear enrichment of uranium, on several parameters related to oxidative stress...Danio rerio. Several parameters were recor...

Beatrice Gagnaire; Isabelle Cavalie

2013-01-01T23:59:59.000Z

203

The New Generation of Uranium In Situ Recovery Facilities: Design Improvements Should Reduce Radiological Impacts Relative to First Generation Uranium Solution Mining Plants  

SciTech Connect

In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium In Situ Leaching / In Situ Recovery (ISL / ISR - also referred to as 'solution mining'), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and are expected to make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since the mid 1970's. However, current designs are expected to result in less radiological wastes and emissions relative to these 'first' generation plants (which were designed, constructed and operated through the 1980's). These early designs typically used alkaline leach chemistries in situ including use of ammonium carbonate which resulted in groundwater restoration challenges, open to air recovery vessels and high temperature calcining systems for final product drying vs the 'zero emissions' vacuum dryers as typically used today. Improved containment, automation and instrumentation control and use of vacuum dryers in the design of current generation plants are expected to reduce production of secondary waste byproduct material, reduce Radon emissions and reduce potential for employee exposure to uranium concentrate aerosols at the back end of the milling process. In Situ Recovery in the U.S. typically involves the circulation of groundwater, fortified with oxidizing (gaseous oxygen e.g) and complexing agents (carbon dioxide, e.g) into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant ( mill). Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facilities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid byproduct materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which radon gas is evolved in the process and the unique aspects of controlling solution flow patterns underground. The radiological character of these processes are described using empirical data collected from many operating facilities. Additionally, the major aspects of the health physics and radiation protection programs that were developed at these first generation facilities are discussed and contrasted to circumstances of the current generation and state of the art of uranium ISR technologies and facilities. In summary: This paper has presented an overview of in situ Uranium recovery processes and associated major radiological aspects and monitoring considerations. Admittedly, the purpose was to present an overview of those special health physics considerations dictated by the in situ Uranium recovery technology, to point out similarities and differences to conventional mill programs and to contrast these alkaline leach facilities to modern day ISR designs. As evidenced by the large number of ISR projects currently under development in the U.S. and worldwide, non conventional Uranium recovery techniques

Brown, S.H. [CHP, SHB INC., Centennial, Colorado (United States)

2008-07-01T23:59:59.000Z

204

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

SciTech Connect

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

NONE

1995-07-05T23:59:59.000Z

205

Estimation of uranium GI absorption fractions for children and adults  

Science Journals Connector (OSTI)

......the ratios of energy expenditures...microg l1. This average concentration...percentage of homes on private well...percentage of homes changed from...the daily water consumption and the uranium...determined from the average value of uranium...Canada. Tap water consumption in Canada......

J. Chen; D. Lariviere; R. Timmins; K. Verdecchia

2011-03-01T23:59:59.000Z

206

Polyethylene Encapsulated Depleted Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

Poly DU Poly DU Polyethylene Encapsulated Depleted Uranium Technology Description: Brookhaven National Laboratory (BNL) has completed preliminary work to investigate the feasibility of encapsulating DU in low density polyethylene to form a stable, dense product. DU loadings as high as 90 wt% were achieved. A maximum product density of 4.2 g/cm3 was achieved using UO3, but increased product density using UO2 is estimated at 6.1 g/cm3. Additional product density improvements up to about 7.2 g/cm3 were projected using DU aggregate in a hybrid technique known as micro/macroencapsulation.[1] A U.S. patent for this process has been received.[2] Figure 1 Figure 1: DU Encapsulated in polyethylene samples produced at BNL containing 80 wt % depleted UO3 A recent DU market study by Kapline Enterprises, Inc. for DOE thoroughly identified and rated potential applications and markets for DU metal and oxide materials.[3] Because of its workability and high DU loading capability, the polyethylene encapsulated DU could readily be fabricated as counterweights/ballast (for use in airplanes, helicopters, ships and missiles), flywheels, armor, and projectiles. Also, polyethylene encapsulated DU is an effective shielding material for both gamma and neutron radiation, with potential application for shielding high activity waste (e.g., ion exchange resins, glass gems), spent fuel dry storage casks, and high energy experimental facilities (e.g., accelerator targets) to reduce radiation exposures to workers and the public.

207

Uranium content variations in thermal waters from the West Rhodope cristalline massif during earthquakes in the Chepino Valley (South Bulgaria)  

Science Journals Connector (OSTI)

The uranium content of the thermal waters in the Chepino valley was determined in a period of increased seismic activity. Significant changes in the uranium concentration, much above the normal background valu...

I. Kuleff; P. Petrov; K. Kostadinov

1980-01-01T23:59:59.000Z

208

Nuclear & Uranium - U.S. Energy Information Administration (EIA) - U.S.  

Gasoline and Diesel Fuel Update (EIA)

Nuclear & Uranium Nuclear & Uranium Glossary › FAQS › Overview Data Summary Uranium & Nuclear Fuel Nuclear Power Plants Radioactive Waste International All Nuclear Data Reports Analysis & Projections Most Requested Nuclear Plants and Reactors Projections Uranium All Reports Uranium Mill Sites Under the UMTRA Project Remediation of UMTRCA Title I Uranium Mill Sites Under the UMTRA Project Summary Table: Uranium Ore Processed, Disposal Cell Material, and Cost for Remediation as of December 31, 1999 Uranium Ore Processed Remediation Project Cost Remediation Project (Mill Site Name, State) Ore (Million Short Tons) Uranium Production (Million Pounds U3O8) Disposal Cell Remediated Material Volume (Million Cubic Yards) Total Cost A (Thousand U.S. Dollars)02/09 Per Pound Produced (Dollars per Pound U3O8) Per Unit of Remediated Material

209

Properties, use and health effects of depleted uranium (DU): a general overview  

Science Journals Connector (OSTI)

Depleted uranium (DU), a waste product of uranium enrichment, has several civilian and military applications. It was used as armor-piercing ammunition in international military conflicts and was claimed to contribute to health problems, known as the Gulf War Syndrome and recently as the Balkan Syndrome. This led to renewed efforts to assess the environmental consequences and the health impact of the use of DU. The radiological and chemical properties of DU can be compared to those of natural uranium, which is ubiquitously present in soil at a typical concentration of 3 mg/kg. Natural uranium has the same chemotoxicity, but its radiotoxicity is 60% higher. Due to the low specific radioactivity and the dominance of alpha-radiation no acute risk is attributed to external exposure to DU. The major risk is DU dust, generated when DU ammunition hits hard targets. Depending on aerosol speciation, inhalation may lead to a protracted exposure of the lung and other organs. After deposition on the ground, resuspension can take place if the DU containing particle size is sufficiently small. However, transfer to drinking water or locally produced food has little potential to lead to significant exposures to DU. Since poor solubility of uranium compounds and lack of information on speciation precludes the use of radioecological models for exposure assessment, biomonitoring has to be used for assessing exposed persons. Urine, feces, hair and nails record recent exposures to DU. With the exception of crews of military vehicles having been hit by DU penetrators, no body burdens above the range of values for natural uranium have been found. Therefore, observable health effects are not expected and residual cancer risk estimates have to be based on theoretical considerations. They appear to be very minor for all post-conflict situations, i.e. a fraction of those expected from natural radiation.

A Bleise; P.R Danesi; W Burkart

2003-01-01T23:59:59.000Z

210

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

59: Uranium Hexafluoride Conversion Facility at the Paducah, 59: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site EIS-0359: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site Summary 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. This EIS also considers a no action alternative that assumes continued storage of DUF6 at the Paducah site. A

211

Uranium Marketing Annual Report  

Gasoline and Diesel Fuel Update (EIA)

4. Uranium sellers to owners and operators of U.S. civilian nuclear power reactors, 2010-2012 2010 2011 2012 4. Uranium sellers to owners and operators of U.S. civilian nuclear power reactors, 2010-2012 2010 2011 2012 American Fuel Resources, LLC Advance Uranium Asset Management Ltd. (was Uranium Asset Management) Advance Uranium Asset Management Ltd. (was Uranium Asset Management) AREVA NC, Inc. (was COGEMA, Inc.) American Fuel Resources, LLC American Fuel Resources, LLC BHP Billiton Olympic Dam Corporation Pty Ltd AREVA NC, Inc. AREVA NC, Inc. CAMECO BHP Billiton Olympic Dam Corporation Pty Ltd BHP Billiton Olympic Dam Corporation Pty Ltd ConverDyn CAMECO CAMECO Denison Mines Corp. ConverDyn ConverDyn Energy Resources of Australia Ltd. Denison Mines Corp. Energy Fuels Resources Energy USA, Inc. Effective Energy N.V. Energy Resources of Australia Ltd.

212

Uranium purchases report 1992  

SciTech Connect

Data reported by domestic nuclear utility companies in their responses to the 1991 and 1992 ``Uranium Industry Annual Survey,`` Form EIA-858, Schedule B ``Uranium Marketing Activities,are provided in response to the requirements in the Energy Policy Act 1992. Data on utility uranium purchases and imports are shown on Table 1. Utility enrichment feed deliveries and secondary market acquisitions of uranium equivalent of US DOE separative work units are shown on Table 2. Appendix A contains a listing of firms that sold uranium to US utilities during 1992 under new domestic purchase contracts. Appendix B contains a similar listing of firms that sold uranium to US utilities during 1992 under new import purchase contracts. Appendix C contains an explanation of Form EIA-858 survey methodologies with emphasis on the processing of Schedule B data.

Not Available

1993-08-19T23:59:59.000Z

213

:- : 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 - 886 Metals, Ceramics and Materials (TID-4500, 22nd Ed.) DRILLING URANIUM BILLETS ON A LEBLOND-CARLSTEDT RAPID BORER By R. J. Jansen* TECHNICAL DIVISION NATIONAL LEAD COMPANY OF OHIO Date of Issuance: September 13, 1963 Approved By: Approved By: Technical Director Head, Metallurgical Department *Mr. Jansen is presently

214

Appendix IV. Risks Associated with Conventional Uranium Milling Introduction  

E-Print Network (OSTI)

by the addition of water/lixiviant is generally collected by air pollution control mechanisms, which return as in situ leaching (ISL) mining operations, to provide a more complete picture of uranium production. While this report focuses on the impacts associated with conventional surface and underground uranium mines

215

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

SciTech Connect

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.

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

2011-11-01T23:59:59.000Z

216

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

DOE Patents (OSTI)

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.

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

1982-06-29T23:59:59.000Z

217

BLENDING LOW ENRICHED URANIUM WITH DEPLETED URANIUM TO CREATE A SOURCE MATERIAL ORE THAT CAN BE PROCESSED FOR THE RECOVERY OF YELLOWCAKE AT A CONVENTIONAL URANIUM MILL  

SciTech Connect

Throughout the United States Department of Energy (DOE) complex, there are a number of streams of low enriched uranium (LEU) that contain various trace contaminants. These surplus nuclear materials require processing in order to meet commercial fuel cycle specifications. To date, they have not been designated as waste for disposal at the DOE's Nevada Test Site (NTS). Currently, with no commercial outlet available, the DOE is evaluating treatment and disposal as the ultimate disposition path for these materials. This paper will describe an innovative program that will provide a solution to DOE that will allow disposition of these materials at a cost that will be competitive with treatment and disposal at the NTS, while at the same time recycling the material to recover a valuable energy resource (yellowcake) for reintroduction into the commercial nuclear fuel cycle. International Uranium (USA) Corporation (IUSA) and Nuclear Fuel Services, Inc. (NFS) have entered into a commercial relationship to pursue the development of this program. The program involves the design of a process and construction of a plant at NFS' site in Erwin, Tennessee, for the blending of contaminated LEU with depleted uranium (DU) to produce a uranium source material ore (USM Ore{trademark}). The USM Ore{trademark} will then be further processed at IUC's White Mesa Mill, located near Blanding, Utah, to produce conventional yellowcake, which can be delivered to conversion facilities, in the same manner as yellowcake that is produced from natural ores or other alternate feed materials. The primary source of feed for the business will be the significant sources of trace contaminated materials within the DOE complex. NFS has developed a dry blending process (DRYSM Process) to blend the surplus LEU material with DU at its Part 70 licensed facility, to produce USM Ore{trademark} with a U235 content within the range of U235 concentrations for source material. By reducing the U235 content to source material levels in this manner, the material will be suitable for processing at a conventional uranium mill under its existing Part 40 license to remove contaminants and enable the product to re-enter the commercial fuel cycle. The tailings from processing the USM Ore{trademark} at the mill will be permanently disposed of in the mill's tailings impoundment as 11e.(2) byproduct material. Blending LEU with DU to make a uranium source material ore that can be returned to the nuclear fuel cycle for processing to produce yellowcake, has never been accomplished before. This program will allow DOE to disposition its surplus LEU and DU in a cost effective manner, and at the same time provide for the recovery of valuable energy resources that would be lost through processing and disposal of the materials. This paper will discuss the nature of the surplus LEU and DU materials, the manner in which the LEU will be blended with DU to form a uranium source material ore, and the legal means by which this blending can be accomplished at a facility licensed under 10 CFR Part 70 to produce ore that can be processed at a conventional uranium mill licensed under 10 CFR Part 40.

Schutt, Stephen M.; Hochstein, Ron F.; Frydenlund, David C.; Thompson, Anthony J.

2003-02-27T23:59:59.000Z

218

2013 Uranium Marketing Annual Survey  

NLE Websites -- All DOE Office Websites (Extended Search)

for inflation. Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual Survey" (2013). UF 6 is uranium hexafluoride. The natural UF 6 and enriched...

219

Manhattan Project: More Uranium Research, 1942  

Office of Scientific and Technical Information (OSTI)

Cubes of uranium metal, Los Alamos, 1945 MORE URANIUM RESEARCH Cubes of uranium metal, Los Alamos, 1945 MORE URANIUM RESEARCH (1942) Events > Difficult Choices, 1942 More Uranium Research, 1942 More Piles and Plutonium, 1942 Enter the Army, 1942 Groves and the MED, 1942 Picking Horses, November 1942 Final Approval to Build the Bomb, December 1942 During the first half of 1942, several routes to a bomb via uranium continued to be explored. At Columbia University, Harold Urey worked on the gaseous diffusion and centrifuge systems for isotope separation in the codenamed SAM (Substitute or Special Alloy Metals) Laboratory. At Berkeley, Ernest Lawrence continued his investigations on electromagnetic separation using the "calutron" he had converted from his thirty-seven-inch cyclotron. Phillip Abelson, who had moved from the Carnegie Institution and the National Bureau of Standards to the Naval Research Laboratory, continued his work on liquid thermal diffusion but with few positive results, and he had lost all contact with the S-1 Section of the Office of Scientific Research and Development. Meanwhile Eger Murphree's group hurriedly studied ways to move from laboratory experiments to production facilities.

220

THE ENERGY SPECTRA OF URANIUM ATOMS SPUTTERED FROM URANIUM METAL AND URANIUM DIOXIDE TARGETS  

E-Print Network (OSTI)

THE ENERGY SPECTRA OF URANIUM ATOMS SPUTTERED FROM URANIUM METAL AND URANIUM DIOXIDE TARGETS Thesis. I have benefitted from conversations with many persons w~ile engaged in this project. I would like

Winfree, Erik

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Environmental and health consequences of depleted uranium use in the 1991 Gulf War  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a by-product of the 235U radionuclide enrichment processes for nuclear reactors or nuclear weapons. DU in the metallic form has high density and hardness as well as pyrophoric properties, which makes it superior to the classical tungsten armour-piercing munitions. Military use of DU has been recently a subject of considerable concern, not only to radioecologists but also public opinion in terms of possible health hazards arising from its radioactivity and chemical toxicity. In this review, the results of uranium content measurements in different environmental samples performed by authors in Kuwait after Gulf War are presented with discussion concerning possible environmental and health effects for the local population. It was found that uranium concentration in the surface soil samples ranged from 0.3 to 2.5 ?g g?1 with an average value of 1.1 ?g g?1, much lower than world average value of 2.8 ?g g?1. The solid fallout samples showed similar concentrations varied from 0.3 to 1.7 ?g g?1 (average 1.47 ?g g?1). Only the average concentration of U in solid particulate matter in surface air equal to 0.24 ng g?1 was higher than the usually observed values of ?0.1 ng g?1 but it was caused by the high dust concentration in the air in that region. Calculated on the basis of these measurements, the exposure to uranium for the Kuwait and southern Iraq population does not differ from the world average estimation. Therefore, the widely spread information in newspapers and Internet (see for example: [CADU NEWS, 2003. http://www.cadu.org.uk/news/index.htm (313)]) concerning dramatic health deterioration for Iraqi citizens should not be linked directly with their exposure to DU after the Gulf War.

Henryk Bem; Firyal Bou-Rabee

2004-01-01T23:59:59.000Z

222

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

SciTech Connect

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)

Camper, Larry W.; Michalak, Paul; Cohen, Stephen; Carter, Ted [Nuclear Regulatory Commission (United States)

2012-07-01T23:59:59.000Z

223

Uranium Marketing Annual Report  

Gasoline and Diesel Fuel Update (EIA)

Uranium Marketing Uranium Marketing Annual Report May 2011 www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. U.S. Energy Information Administration | 2010 Uranium Marketing Annual Report ii Contacts This report was prepared by the staff of the Renewables and Uranium Statistics Team, Office of Electricity, Renewables, and Uranium Statistics. Questions about the preparation and content of this report may be directed to Michele Simmons, Team Leader,

224

Removal of residual uranium in simulated radwaste solution by TBP extraction  

SciTech Connect

The extraction behavior of uranium in a multicomponent system simulated on the basis of high-level liquid waste was examined in order to find effective conditions for the removal of residual uranium in a simulated radwaste solution by the TBP solvent extraction method. While the conventional semiempirical equation for the distribution coefficient of uranium could be used in a system composed of only uranium and nitric acid, it was found to be unsuitable for a multicomponent system where the concentration of uranium is not dominant. Uranium extractability by TBP was found to be limited in multicomponents systems regardless of high TBP concentration, phase ratio, and extraction times because of the presence of neodymium and iron together with uranium in the systems.

Kim, Kwang-Wook; Lee, Eil-Hee; Shin, Young-Joon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)] [and others

1995-10-01T23:59:59.000Z

225

Development of Novel Sorbents for Uranium Extraction from Seawater  

SciTech Connect

As the uranium resource in terrestrial ores is limited, it is difficult to ensure a long-term sustainable nuclear energy technology. The oceans contain approximately 4.5 billion tons of uranium, which is one thousand times the amount of uranium in terrestrial ores. Development of technologies to recover the uranium from seawater would greatly improve the uranium resource availability, sustaining the fuel supply for nuclear energy. Several methods have been previously evaluated including solvent extraction, ion exchange, flotation, biomass collection, and adsorption; however, none have been found to be suitable for reasons such as cost effectiveness, long term stability, and selectivity. Recent research has focused on the amidoxime functional group as a promising candidate for uranium sorption. Polymer beads and fibers have been functionalized with amidoxime functional groups, and uranium adsorption capacities as high as 1.5 g U/kg adsorbent have recently been reported with these types of materials. As uranium concentration in seawater is only ~3 ppb, great improvements to uranium collection systems must be made in order to make uranium extraction from seawater economically feasible. This proposed research intends to develop transformative technologies for economic uranium extraction from seawater. The Lin group will design advanced porous supports by taking advantage of recent breakthroughs in nanoscience and nanotechnology and incorporate high densities of well-designed chelators into such nanoporous supports to allow selective and efficient binding of uranyl ions from seawater. Several classes of nanoporous materials, including mesoporous silica nanoparticles (MSNs), mesoporous carbon nanoparticles (MCNs), meta-organic frameworks (MOFs), and covalent-organic frameworks (COFs), will be synthesized. Selective uranium-binding liagnds such as amidoxime will be incorporated into the nanoporous materials to afford a new generation of sorbent materials that will be evaluated for their uranium extraction efficiency. The initial testing of these materials for uranium binding will be carried out in the Lin group, but more detailed sorption studies will be carried out by Dr. Taylor-Pashow of Savannah River National Laboratory in order to obtain quantitative uranyl sorption selectivity and kinetics data for the proposed materials. The proposed nanostructured sorbent materials are expected to have higher binding capacities, enhanced extraction kinetics, optimal stripping efficiency for uranyl ions, and enhanced mechanical and chemical stabilities. This transformative research will significantly impact uranium extraction from seawater as well as benefit DOEs efforts on environmental remediation by developing new materials and providing knowledge for enriching and sequestering ultralow concentrations of other metals.

Lin, Wenbin; Taylor-Pashow, Kathryn

2014-01-08T23:59:59.000Z

226

Uranium Leasing Program: Program Summary | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

which called for the continued leasing of DOE-managed lands for the exploration and production of uranium and vanadium ores. In 1996, DOE reoffered respective leases to the...

227

Purification de l'hexafluorure d'uranium.  

E-Print Network (OSTI)

??Lhexafluorure duranium (UF6), est le seul compos utilis ltat gazeux dans les procds denrichissement pour la production du combustible nuclaire. Pour le bon droulement (more)

Benzouaa, Rachid

2014-01-01T23:59:59.000Z

228

Uranium in prehistoric Indian pottery  

E-Print Network (OSTI)

present in the sample, and the cross l section of the process (the measure of the probability of a neutron interacting with an uranium atom), In general, a daughter product 235 of U fission is analyzed on a detector which counts either gamma rays... for quantitative analysis of various elements on archaeological artifacts, Manganese has been determined in Mesoamerican pot sherds (Bennyhoff and Heizer 1965). A Pu-Be radioisotope neutron source with a flux of 4 x 10 4 -2 -1 neutrons cm sec was used...

Filberth, Ernest William

2012-06-07T23:59:59.000Z

229

Petrography and genetic history of coffinite and uraninite from the Liueryiqi granite-hosted uranium deposit, SE China  

E-Print Network (OSTI)

-hosted uranium deposit, SE China Maozhong Mina,b,*, Changquan Fanga , Mostafa Fayekc a Department of Earth-hosted uranium deposit, SE China, form a unique bbull's-eyeQ texture. These aggregates consist of concentric% at temperatures between 126 and 178 8C and a lithostatic pressure of 500 to 800 bars. Uranium was likely

Fayek, Mostafa

230

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

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.

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

2000-06-01T23:59:59.000Z

231

300 Area Uranium Stabilization Through Polyphosphate Injection: Final Report  

SciTech Connect

The objective of the treatability test was to evaluate the efficacy of using polyphosphate injections to treat uranium-contaminated groundwater in situ. A test site consisting of an injection well and 15 monitoring wells was installed in the 300 Area near the process trenches that had previously received uranium-bearing effluents. This report summarizes the work on the polyphosphate injection project, including bench-scale laboratory studies, a field injection test, and the subsequent analysis and interpretation of the results. Previous laboratory tests have demonstrated that when a soluble form of polyphosphate is injected into uranium-bearing saturated porous media, immobilization of uranium occurs due to formation of an insoluble uranyl phosphate, autunite [Ca(UO2)2(PO4)2nH2O]. These tests were conducted at conditions expected for the aquifer and used Hanford soils and groundwater containing very low concentrations of uranium (10-6 M). Because autunite sequesters uranium in the oxidized form U(VI) rather than forcing reduction to U(IV), the possibility of re-oxidation and subsequent re-mobilization is negated. Extensive testing demonstrated the very low solubility and slow dissolution kinetics of autunite. In addition to autunite, excess phosphorous may result in apatite mineral formation, which provides a long-term source of treatment capacity. Phosphate arrival response data indicate that, under site conditions, the polyphosphate amendment could be effectively distributed over a relatively large lateral extent, with wells located at a radial distance of 23 m (75 ft) reaching from between 40% and 60% of the injection concentration. Given these phosphate transport characteristics, direct treatment of uranium through the formation of uranyl-phosphate mineral phases (i.e., autunite) could likely be effectively implemented at full field scale. However, formation of calcium-phosphate mineral phases using the selected three-phase approach was problematic. Although amendment arrival response data indicate some degree of overlap between the reactive species and thus potential for the formation of calcium-phosphate mineral phases (i.e., apatite formation), the efficiency of this treatment approach was relatively poor. In general, uranium performance monitoring results support the hypothesis that limited long-term treatment capacity (i.e., apatite formation) was established during the injection test. Two separate overarching issues affect the efficacy of apatite remediation for uranium sequestration within the 300 Area: 1) the efficacy of apatite for sequestering uranium under the present geochemical and hydrodynamic conditions, and 2) the formation and emplacement of apatite via polyphosphate technology. In addition, the long-term stability of uranium sequestered via apatite is dependent on the chemical speciation of uranium, surface speciation of apatite, and the mechanism of retention, which is highly susceptible to dynamic geochemical conditions. It was expected that uranium sequestration in the presence of hydroxyapatite would occur by sorption and/or surface complexation until all surface sites have been depleted, but that the high carbonate concentrations in the 300 Area would act to inhibit the transformation of sorbed uranium to chernikovite and/or autunite. Adsorption of uranium by apatite was never considered a viable approach for in situ uranium sequestration in and of itself, because by definition, this is a reversible reaction. The efficacy of uranium sequestration by apatite assumes that the adsorbed uranium would subsequently convert to autunite, or other stable uranium phases. Because this appears to not be the case in the 300 Area aquifer, even in locations near the river, apatite may have limited efficacy for the retention and long-term immobilization of uranium at the 300 Area site..

Vermeul, Vincent R.; Bjornstad, Bruce N.; Fritz, Brad G.; Fruchter, Jonathan S.; Mackley, Rob D.; Newcomer, Darrell R.; Mendoza, Donaldo P.; Rockhold, Mark L.; Wellman, Dawn M.; Williams, Mark D.

2009-06-30T23:59:59.000Z

232

Uranium Marketing Annual Report -  

NLE Websites -- All DOE Office Websites (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, 2009-13 thousands pounds U3O8...

233

Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

a. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors, 1994-2013 million pounds U3O8 equivalent Delivery year Total purchased Purchased from U.S....

234

Uranium Marketing Annual Report -  

NLE Websites -- All DOE Office Websites (Extended Search)

9. Contracted purchases of uranium by owners and operators of U.S. civilian nuclear power reactors, signed in 2013, by delivery year, 2014-23 thousand pounds U3O8 equivalent Year...

235

Uranium purchases report 1993  

SciTech Connect

Data reported by domestic nuclear utility companies in their responses to the 1991 through 1993 ``Uranium Industry Annual Survey,`` Form EIA-858, Schedule B,`` Uranium Marketing Activities,`` are provided in response to the requirements in the Energy Policy Act 1992. Appendix A contains an explanation of Form EIA-858 survey methodologies with emphasis on the processing of Schedule B data. Additional information published in this report not included in Uranium Purchases Report 1992, includes a new data table. Presented in Table 1 are US utility purchases of uranium and enrichment services by origin country. Also, this report contains additional purchase information covering average price and contract duration. Table 2 is an update of Table 1 and Table 3 is an update of Table 2 from the previous year`s report. The report contains a glossary of terms.

Not Available

1994-08-10T23:59:59.000Z

236

Identification and quantification of the source terms for uranium in surface waters collected at the Rocky Flats facility  

Science Journals Connector (OSTI)

The intent of this study was to determine the fraction of soluble uranium attributable to the Rocky Flats Plant (RFP) operations which is recoverable from waters and suspended sediments drawn from ponds on site at RFP. Samples were collected from late 1992 through 1993. Thermal ionization mass spectrometry (TIMS) measurement techniques indicate that the water samples contain both naturally occurring uranium and depleted uranium. The uranium concentrations in the waters collected from the terminal ponds contained 0.5% or less of the interim standard calculated derived concentration guide for uranium in waters available to the public.

D.W. Efurd; D.J. Rokop; R.D. Aguilar; F.R. Roensch; J.C. Banar; R.E. Perrin

1995-01-01T23:59:59.000Z

237

Uranium purchases report 1994  

SciTech Connect

US utilities are required to report to the Secretary of Energy annually the country of origin and the seller of any uranium or enriched uranium purchased or imported into the US, as well as the country of origin and seller of any enrichment services purchased by the utility. This report compiles these data and also contains a glossary of terms and additional purchase information covering average price and contract duration. 3 tabs.

NONE

1995-07-01T23:59:59.000Z

238

Uranium speciation in glass corrosion layers: An XAFS study  

SciTech Connect

Uranium L{sub 3} X-ray absorption data were obtained from two borosilicate glasses, which are considered as models for radioactive wasteforms, both before and after leaching. Surface sensitivity to uranium speciation was attained by a novel application of simultaneous fluorescence and electron-yield detection. Changes in speciation are clearly discernible, from U(VI) in the bulk to (UO{sub 2}){sup 2+}-uranyl in the corrosion layer. The uranium concentrations within the corrosion layer also show variations with leaching times that can be determined from the data.

Biwer, B.M.; Soderholm, L. [Argonne National Lab., IL (United States); Greegor, R.B. [Boeing Co., Seattle, WA (United States); Lytle, F.W. [EXAFS Co., Pioche, NV (United States)

1997-12-31T23:59:59.000Z

239

Remediation of a uranium-contamination in ground water  

SciTech Connect

The former production site of NUKEM where nuclear fuel-elements were developed and handled from 1958 to 1988 was situated in the centre of an industrial park for various activities of the chemical and metallurgical industry. The size of the industrially used part is about 300.000 m{sup 2}. Regulatory routine controls showed elevated CHC (Chlorinated Hydro-Carbons) values of the ground water at the beginning of the 1990's in an area which represented about 80.000 m{sup 2} down-gradient of locations where CHC compounds were stored and handled. Further investigations until 1998 proved that former activities on the NUKEM site, like the UF{sub 6} conversion process, were of certain relevance. The fact that several measured values were above the threshold values made the remediation of the ground water mandatory. This was addressed in the permission given by the Ministry for Nuclear Installations and Environment of Hesse according to chap. 7 of the German atomic law in October 2000. Ground water samples taken in an area of about 5.000 m{sup 2} showed elevated values of total Uranium activity up to between 50 and 75 Bq/l in 2002. Furthermore in an area of another 20.000 m{sup 2} the samples were above threshold value. In this paper results of the remediation are presented. The actual alpha-activities of the ground waters of the remediation wells show values of 3 to 9 Bq/l which are dominated by 80 to 90 % U-234 activity. The mass-share of total Uranium for this nuclide amounts to 0,05% on average. The authority responsible for conventional water utilisation defined target values for remediation: 20 {mu}g/l for dissolved Uranium and 10 {mu}g/l for CHC. Both values have not yet been reached for an area of about 10.000 m{sup 2}. The remediation process by extracting water from four remediation wells has proved its efficiency by reduction of the starting concentrations by a factor of 3 to 6. Further pumping will be necessary especially in that area of the site where the contaminations were found later during soil remediation activities. Only two wells have been in operation since July 2002 when the remediation technique was installed and an apparatus for direct gamma-spectroscopic measurement of the accumulated activities on the adsorbers was qualified. Two further remediation wells have been in operation since August 2006, when the installed remediation technique was about to be doubled from a throughput of 5 m{sup 3}/h to 10 m{sup 3}/h. About 20.000 m{sup 3} of ground water have been extracted since from these two wells and the decrease of their Uranium concentrations behaves similar to that of the two other wells being extracted since the beginning of remediation. Both, total Uranium-concentrations and the weight-share of the nuclides U-234, U-235 and U-238 are measured by ICP-MS (Inductively Coupled Plasma - Mass Spectrometry) besides measurements of Uranium-Alpha-Activities in addition to the measurement of CHC components of which PCE (Per-chlor-Ethene) is dominant in the contaminated area. CHC compounds are measured by GC (Gas Chromatography). Down-gradient naturally attenuated products are detected in various compositions. Overall 183.000 m{sup 3} of ground water have been extracted. Using a pump and treat method 11 kg Uranium have been collected on an ion-exchange material based on cellulose, containing almost 100 MBq U-235 activity, and almost 15 kg of CHC, essentially PCE, were collected on GAC (Granules of Activated Carbon). Less than 3% of the extracted Uranium have passed the adsorber-system of the remediation plant and were adsorbed by the sewage sludge of the industrial site's waste water treatment. The monthly monitoring of 19 monitoring wells shows that an efficient artificial barrier was built up by the water extraction. The Uranium contamination of two ground water plumes has drastically been reduced by the used technique dependent on the amounts of extracted water. The concentration of the CHC contamination has changed depending on the location of temporal pumping. Thereby maximum availability of this contaminan

Woerner, Joerg; Margraf, Sonja; Hackel, Walter [RD Hanau GmbH (Germany)

2007-07-01T23:59:59.000Z

240

Introduction Uranium is a common element in nature, and has been used for centuries as a coloring agent in  

E-Print Network (OSTI)

(U.S. DOE/EIA 2003a, 2003b, 2006). Another legacy of uranium exploration, mining, and ore processing in a full-blown exploration and mining boom, starting immediately after World War II and making uranium the most important commodity in the mining industry. The greatest period of uranium production spanned from

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

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

E-Print Network (OSTI)

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

Cai, Long

242

A pilot study of the dependence of radon concentration on the tectonic structures, using simple geophysical methods  

Science Journals Connector (OSTI)

......concentration of 40K and uranium is more or less stable. The low radon and uranium concentrations measured...supported by the research plan MSM6840770040 of...McMurry P. H. A review of atmospheric aerosol...Plastino W. , et al. Uranium groundwater anomalies...main unit with standard accessories, multi-electrode......

L. Thinova; A. Fronka; K. Rovenska

2011-05-01T23:59:59.000Z

243

Statistical data of the uranium industry  

SciTech Connect

This document is a compilation of historical facts and figures through 1979. These statistics are based primarily on information provided voluntarily by the uranium exploration, mining, and milling companies. The production, reserves, drilling, and production capability information has been reported in a manner which avoids disclosure of proprietary information. Only the totals for the $1.5 reserves are reported. Because of increased interest in higher cost resources for long range planning purposes, a section covering the distribution of $100 per pound reserves statistics has been newly included. A table of mill recovery ranges for the January 1, 1980 reserves has also been added to this year's edition. The section on domestic uranium production capability has been deleted this year but will be included next year. The January 1, 1980 potential resource estimates are unchanged from the January 1, 1979 estimates.

none,

1980-01-01T23:59:59.000Z

244

Development of Integrated Online Monitoring Systems for Detection of Diversion at Natural Uranium Conversion Facilities  

SciTech Connect

Recent work at Oak Ridge National Laboratory (ORNL) has focused on some source term modeling of uranyl nitrate (UN) as part of a comprehensive validation effort employing gamma-ray detector instrumentation for the detection of diversion from declared conversion activities. Conversion, the process by which natural uranium ore (yellowcake) is purified and converted through a series of chemical processes into uranium hexafluoride gas (UF6), has historically been excluded from the nuclear safeguards requirements of the 235U-based nuclear fuel cycle. The undeclared diversion of this product material could potentially provide feedstock for a clandestine weapons program for state or non-state entities. Given the changing global political environment and the increased availability of dual-use nuclear technology, the International Atomic Energy Agency has evolved its policies to emphasize safeguarding this potential feedstock material in response to dynamic and evolving potential diversion pathways. To meet the demand for instrumentation testing at conversion facilities, ORNL developed the Uranyl Nitrate Calibration Loop Equipment (UNCLE) facility to simulate the full-scale operating conditions of a purified uranium-bearing aqueous stream exiting the solvent extraction process in a natural uranium conversion plant. This work investigates gamma-ray signatures of UN circulating in the UNCLE facility and evaluates detector instrumentation sensitivity to UN for safeguards applications. These detector validation activities include assessing detector responses to the UN gamma-ray signatures for spectrometers based on sodium iodide, lanthanum bromide, and germanium detectors. The results of measurements under static and dynamic operating conditions at concentrations ranging from 10-90g U/L of naturally enriched UN will be presented. A range of gamma-ray lines was examined and self-attenuation factors were calculated, in addition to attenuation for transmission measurement of density, concentration and enrichment. A detailed uncertainty analysis will be presented providing insights into instrumentation limitations to spoofing.

Dewji, Shaheen A [ORNL] [ORNL; Lee, Denise L [ORNL] [ORNL; Croft, Stephen [ORNL] [ORNL; McElroy, Robert Dennis [ORNL] [ORNL; Hertel, Nolan [Georgia Institute of Technology] [Georgia Institute of Technology; Chapman, Jeffrey Allen [ORNL] [ORNL; Cleveland, Steven L [ORNL] [ORNL

2013-01-01T23:59:59.000Z

245

Net primary production of terrestrial ecosystems in China and its equilibrium response to changes in climate and atmospheric CO? concentration  

E-Print Network (OSTI)

The Terrestrial Ecosystem Model (TEM, version 4.0) was used to estimate net primary production (NPP) in China for contemporary climate and NPP responses to elevated CO? and climate changes projected by three atmospheric ...

Xiao, Xiangming.; Melillo, Jerry M.; Kicklighter, David W.; Pan, Yude.; McGuire, A. David.; Helfrich III, J.V.K.

246

Controlling uranium reactivity March 18, 2008  

E-Print Network (OSTI)

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

Meyer, Karsten

247

Influence of uranium hydride oxidation on uranium metal behaviour  

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

248

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection  

SciTech Connect

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 ug/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area.

Vermeul, Vincent R.; Williams, Mark D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-06-01T23:59:59.000Z

249

The distribution of copper, manganese, zinc, and iron in antarctic waters and the relation of the concentrations of these metals to biological primary productivity  

E-Print Network (OSTI)

THE DISTRIBUTION OF COPPER, MANGANESE, ZINC, AND IRON IN ANTARCTIC WATERS AND THE RELATION OF THE CONCENTRATIONS OF THESE METALS TO BIOLOGICAL PRIMARY PRODUCTIVITY A Thesis By MARTIN EDWARD ARHELGER Submitted to the Graduate College... of the Texas A& 1 University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August I967 Major Subj ect: CHEMICAL OCEANOGRAPHY THE DISTRIBUTION OF COPPER, MANGANESE, ZINC, AND IRON IN ANTARCTIC WATERS AND THE RELATION...

Arhelger, Martin Edward

1967-01-01T23:59:59.000Z

250

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

year, 2009-13 Source: U.S. Energy Information Administration: Form EIA-858 "Uranium Marketing Annual Survey" (2009-13). Table 19. Foreign purchases of uranium by U.S. suppliers...

251

Radiological aspects of in situ uranium recovery  

SciTech Connect

In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium in situ leaching in situ recovery (ISL / ISR), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and may make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since 1975. Solution mining involves the pumping of groundwater, fortified with oxidizing and complexing agents into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant. Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facilities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid byproduct materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which Radon gas is evolved in the process and the unique aspects of controlling solution flow patterns underground. An overview of the major aspects of the health physics and radiation protection programs that were developed at these facilities are discussed and contrasted to circumstances of the current generation and state of the art of Uranium ISR technologies and facilities. (authors)

BROWN, STEVEN H. [SHB INC., 7505 S. Xanthia Place, Centennial, Colorado (United States)

2007-07-01T23:59:59.000Z

252

Uranium and other heavy metals in the plant-animal-human food chain near abandoned mining sites and structures in an American Indian community in northwestern New Mexico  

E-Print Network (OSTI)

Uranium and thorium isotopic conference on high levels of natural radiation sector inductively coupled mass spectrometry. Chemical Geology,Uranium industry in New Mexico--history, production and present status. New Mexico Geology,

Samuel-Nakamura, Christine

2013-01-01T23:59:59.000Z

253

Depleted uranium instead of lead in munitions: the lesser evil  

Science Journals Connector (OSTI)

Uranium has many similarities to lead in its exposure mechanisms, metabolism and target organs. However, lead is more toxic, which is reflected in the threshold limit values. The main potential hazard associated with depleted uranium is inhalation of the aerosols created when a projectile hits an armoured target. A person can be exposed to lead in similar ways. Accidental dangerous exposures can result from contact with both substances. Encountering uranium fragments is of minor significance because of the low penetration depth of alpha particles emitted by uranium: they are unable to penetrate even the superficial keratin layer of human skin. An additional cancer risk attributable to the uranium exposure might be significant only in case of prolonged contact of the contaminant with susceptible tissues. Lead intoxication can be observed in the wounded, in workers manufacturing munitions etc; moreover, lead has been documented to have a negative impact on the intellectual function of children at very low blood concentrations. It is concluded on the basis of the literature overview that replacement of lead by depleted uranium in munitions would be environmentally beneficial or largely insignificant because both lead and uranium are present in the environment.

Sergei V Jargin

2014-01-01T23:59:59.000Z

254

Progress in alkaline peroxide dissolution of low-enriched uranium metal and silicide targets  

SciTech Connect

This paper reports recent progress on two alkaline peroxide dissolution processes: the dissolution of low-enriched uranium metal and silicide (U{sub 3}Si{sub 2}) targets. These processes are being developed to substitute low-enriched for high-enriched uranium in targets used for production of fission-product {sup 99}Mo. Issues that are addressed include (1) dissolution kinetics of silicide targets, (2) {sup 99}Mo lost during aluminum dissolution, (3) modeling of hydrogen peroxide consumption, (4) optimization of the uranium foil dissolution process, and (5) selection of uranium foil barrier materials. Future work associated with these two processes is also briefly discussed.

Chen, L.; Dong, D.; Buchholz, B.A.; Vandegrift, G.F. [Argonne National Lab., IL (United States). Chemical Technology Div.; Wu, D. [Univ. of Illinois, Urbana, IL (United States)

1996-12-31T23:59:59.000Z

255

The analysis of the factors effect on coalbed methane pool concentration and high-production -- The North China coalbed methane districts as an example  

SciTech Connect

The factors which affect coalbed methane (CBM) pool concentration and high-production based upon the exploration and research of the North China CBM districts are coal facies, coal rank and metamorphic types, structural features, the surrounding rocks and their thickness, and hydrogeological conditions. Coal facies, coal rank and their metamorphic types mainly affect the CBM forming characteristic, while the other factors effect the trap of CBM pool. The interaction of the above factors determines the petrophysics of coal reservoirs and extractability of CBM. The high-production areas where CBM pools develop well in North China CBM districts are sites which have a favorable coordination of the five factors. The poor-production areas where CBM pools are undeveloped in North China are caused by action of one or more unfavorable factors. Therefore the favorable factors coordination is the prerequisite in selecting sites for coalbed methane recovery.

Wang Shengwei; Zhang Ming; Zhuang Xiaoli

1997-12-31T23:59:59.000Z

256

Corrosion-resistant uranium  

DOE Patents (OSTI)

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.

Hovis, Jr., Victor M. (Kingston, TN); Pullen, William C. (Knoxville, TN); Kollie, Thomas G. (Oak Ridge, TN); Bell, Richard T. (Knoxville, TN)

1983-01-01T23:59:59.000Z

257

Corrosion-resistant uranium  

DOE Patents (OSTI)

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.

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

1981-10-21T23:59:59.000Z

258

Disposition of Uranium -233 (sup 233U) in Plutonium Metal and Oxide at the Rocky Flats Environmental Technology Site  

SciTech Connect

This report documents the position that the concentration of Uranium-233 ({sup 233}U) in plutonium metal and oxide currently stored at the DOE Rocky Flats Environmental Technology Site (RFETS) is well below the maximum permissible stabilization, packaging, shipping and storage limits. The {sup 233}U stabilization, packaging and storage limit is 0.5 weight percent (wt%), which is also the shipping limit maximum. These two plutonium products (metal and oxide) are scheduled for processing through the Building 371 Plutonium Stabilization and Packaging System (PuSPS). This justification is supported by written technical reports, personnel interviews, and nuclear material inventories, as compiled in the ''History of Uranium-233 ({sup 233}U) Processing at the Rocky Flats Plant In Support of the RFETS Acceptable Knowledge Program'' RS-090-056, April 1, 1999. Relevant data from this report is summarized for application to the PuSPS metal and oxide processing campaigns.

Freiboth, Cameron J.; Gibbs, Frank E.

2000-03-01T23:59:59.000Z

259

Process for the production of aqueous hydrochloric acid having a concentration of at least 35. 5% by weight  

SciTech Connect

The present invention is directed to a process for continuously producing aqueous hydrochloric acid having a concentration of at least 3.5% by weight comprising: continuously introducing water to the top of an absorption unit, continuously introducing a gas stream containing anhydrous hydrogen chloride to the bottom of said absorption unit, removing an overhead gaseous stream from said unit, said gaseous stream containing no more than 3% by weight, and preferably no more than 1% by weight hydrogen chloride, and removing a bottom liquid stream from said unit, said bottom stream containing at least 35.5% by weight hydrogen chloride, and returning a portion of said bottom stream to said unit.

Parigi, J.V.

1984-12-18T23:59:59.000Z

260

DOE - Office of Legacy Management -- Colonial Uranium Co - CO 10  

NLE Websites -- All DOE Office Websites (Extended Search)

Colonial Uranium Co - CO 10 Colonial Uranium Co - CO 10 FUSRAP Considered Sites Site: Colonial Uranium Co. (CO.10 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Grand Junction , Colorado CO.10-1 Evaluation Year: 1987 CO.10-2 Site Operations: Processed thorium concentrates for commercial market at another site. AEC purchased small quantity (100 lbs) for testing. CO.10-1 Site Disposition: Eliminated - No Authority - Commercial operation CO.10-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Thorium CO.10-1 Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to Colonial Uranium Co. CO.10-1 - AEC Memorandum; Faulkner to Sapirie; Subject: Testing of

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

RESPONSES OF PRIMARY PRODUCTION AND TOTAL CARBON STORAGE TO CHANGES IN CLIMATE AND ATMOSPHERIC CO2 CONCENTRATION  

E-Print Network (OSTI)

Model (TEM, version 4.0) to estimate global responses of annual net primary production (NPP) and total. For contemporary climate with 315 ppmv CO2, TEM estimated that global NPP is 47.9 PgC/yr and global total carbon-q climate and +20.6% (9.9 PgC/yr) for the GISS climate. The responses of global total carbon storage are +17

262

Observations of Oxygen Ion Behavior in the Lithium-Based Electrolytic Reduction of Uranium Oxide  

SciTech Connect

Parametric studies were performed on a lithium-based electrolytic reduction process at bench-scale to investigate the behavior of oxygen ions in the reduction of uranium oxide for various electrochemical cell configurations. Specifically, a series of eight electrolytic reduction runs was performed in a common salt bath of LiCl 1 wt% Li2O. The variable parameters included fuel basket containment material (i.e., stainless steel wire mesh and sintered stainless steel) and applied electrical charge (i.e., 75 150% of the theoretical charge for complete reduction of uranium oxide in a basket to uranium metal). Samples of the molten salt electrolyte were taken at regular intervals throughout each run and analyzed to produce a time plot of Li2O concentrations in the bulk salt over the course of the runs. Following each run, the fuel basket was sectioned and the fuel was removed. Samples of the fuel were analyzed for the extent of uranium oxide reduction to metal and for the concentration of salt constituents, i.e., LiCl and Li2O. Extents of uranium oxide reduction ranged from 43 70% in stainless steel wire mesh baskets and 8 33 % in sintered stainless steel baskets. The concentrations of Li2O in the salt phase of the fuel product from the stainless steel wire mesh baskets ranged from 6.2 9.2 wt%, while those for the sintered stainless steel baskets ranged from 26 46 wt%. Another series of tests was performed to investigate the dissolution of Li2O in LiCl at 650 C across various cathode containment materials (i.e., stainless steel wire mesh, sintered stainless steel and porous magnesia) and configurations (i.e., stationary and rotating cylindrical baskets). Dissolution of identical loadings of Li2O particulate reached equilibrium within one hour for stationary stainless steel wire mesh baskets, while the same took several hours for sintered stainless steel and porous magnesia baskets. Rotation of an annular cylindrical basket of stainless steel wire mesh accelerated the Li2O dissolution rate by more than a factor of six.

Steven D. Herrmann; Shelly X. Li; Brenda E. Serrano-Rodriguez

2009-09-01T23:59:59.000Z

263

Numerical analysis of hydrogen production via methane steam reforming in porous media solar thermochemical reactor using concentrated solar irradiation as heat source  

Science Journals Connector (OSTI)

Abstract The calorific value of syngas can be greatly upgraded during the methane steam reforming process by using concentrated solar energy as heat source. In this study, the Monte Carlo Ray Tracing (MCRT) and Finite Volume Method (FVM) coupling method is developed to investigate the hydrogen production performance via methane steam reforming in porous media solar thermochemical reactor which includes the mass, momentum, energy and irradiative transfer equations as well as chemical reaction kinetics. The local thermal non-equilibrium (LTNE) model is used to provide more temperature information. The modified P1 approximation is adopted for solving the irradiative heat transfer equation. The MCRT method is used to calculate the sunlight concentration and transmission problems. The fluid phase energy equation and transport equations are solved by Fluent software. The solid phase energy equation, irradiative transfer equation and chemical reaction kinetics are programmed by user defined functions (UDFs). The numerical results indicate that concentrated solar irradiation on the fluid entrance surface of solar chemical reactor is highly uneven, and temperature distribution has significant influence on hydrogen production.

Fuqiang Wang; Jianyu Tan; Yong Shuai; Liang Gong; Heping Tan

2014-01-01T23:59:59.000Z

264

Tris(bis(trimethylsilyl)amido)uranium: Compounds with tri-, tetra-, and penta-valent uranium  

SciTech Connect

This trivalent uranium compound, serves as a precursor to new tri-, tetra-, and penta-valent uranium species. The geometry about the U atom is pyramidal. Lewis-base coordination compounds of U(N(SiMe/sub 3/)/sub 2/)/sub 3/ with a one-to-one- ratio of Lewis base to uranium were isolated with pyridine, 4-dimethylamino-pyridine, 2,6-Me/sub 2/-C/sub 6/H/sub 3/NC, and TPO. Two-to-one coordination compounds were obtained with t-butylnitrile and t-butylisocyanide. Compounds with more sterically demanding bases could not be isolated. The expected decrease in U-N(SiMe/sub 3/)/sub 2/ bond length with increase in oxidation state is not observed. Reaction of ClU(N(SiMe/sub 3/)/sub 2/)/sub 3/and Li(NH(p-tolyl)) yields the uranium (IV) dimer, U/sub 2/(N(SiMe/sub 3/)/sub 2/)/sub 4/(..mu..-N(p-tolyl))/sub 2/. Reaction with 2,4,6-triemethylaniline produces a dimer. Analogous substitution products could not be obtained with aniline or p-toluidine. t-Bu/sub 3/CO/sup /minus//, t-Bu/sub 2/CHO/sup /minus//, and t-Bu/sub 3/SiO/sup /minus// are used to synthesize new tetravalent, mononuclear uranium compounds. Reaction of ClU(tritox)/sub 3/ with alkyllithium reagents leads to isolation of RU(tritox)/sub 3/. The reaction of U(ditox)/sub 4/ with MeLi affords the addition product U(ditox)/sub 4/(Me)Li, whose crystal structure is described. Preparation of uranium silox compounds is reported. 97 refs., 26 figs., 39 tabs.

Stewart, J.L.

1988-04-01T23:59:59.000Z

265

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)

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.

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

1995-05-30T23:59:59.000Z

266

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)

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.

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

1995-01-01T23:59:59.000Z

267

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

SciTech Connect

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.

Andrews, Lester

2014-10-17T23:59:59.000Z

268

Accumulation and Distribution of Uranium in Rats after Implantation with Depleted Uranium Fragments  

Science Journals Connector (OSTI)

......Rats after Implantation with Depleted Uranium Fragments Guoying Zhu 1 * Mingguang...and distribution of uranium in depleted uranium (DU) implanted rats. Materials...of chronic exposure to DU. Depleted uranium|Bone|Kidney|Distribution......

Guoying Zhu; Mingguang Tan; Yulan Li; Xiqiao Xiang; Heping Hu; Shuquan Zhao

2009-05-01T23:59:59.000Z

269

Dissolution rates of uranium compounds in simulated lung fluid  

SciTech Connect

Maximum dissolution rates of uranium into simulated lung fluid from a variety of materials were measured at 37/sup 0/in the where f/sub i/ is in order to estimate clearance rates from the deep lung. A batch procedure was utilized in which samples containing as little as 10 ..mu..g of natural uranium could be tested. The materials included: products of uranium mining, milling and refining operations, coal fly ash, an environmental sample from a site exposed to multiple uranium sources, and purified samples of (NH/sub 4/)/sub 2/U/sub 2/O/sub 7/ U/sub 3/O/sub 8/, UO/sub 2/, and UF/sub 4/. Dissolution of uranium from several materials indicated the presence of more than one type of uranium compound; but in all cases, the fraction F of uranium remaining undissolved at any time t could be represented by the sum of up to three terms in the series: F = ..sigma../sub i/f/sub i/ exp (-0.693t/UPSILON/sub i/), where f/sub i/ is the initial fraction of component i with dissolution half-time epsilon/sub i/. Values of epsilon/sub i/ varied from 0.01 day to several thousand days depending on the physical and chemical form of the uranium. Dissolution occurred predominantly by formation of the (UO/sub 2/(CO/sub 3/)/sub 3/)/sup 4 -/ ion; and as a result, tetravalent uranium compounds dissolved slowly. Dissolution rates of size-separated yellow-cake aerosols were found to be more closely correlated with specific surface area than with aerodynamic diameter.

Kalkwarf, D.R.

1981-01-01T23:59:59.000Z

270

GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM GC GUIDANCE ON BARTER TRANSACTIONS INVOLVING DOE-OWNED URANIUM The Department of Energy has on a variety of occasions engaged in transactions under which it bartered uranium to which it has title for goods or services . This guidance memorializes the results of analyses previously directed to individual proposed transactions . For the reasons discussed below, we conclude that the Atomic Energy Act of 1954' , as amended, (AEA), authorizes such barter transactions. Background : DOE Barter Transactions In a number of instances, DOE has engaged in transactions involving the barter of DOE-owned uranium2 in exchange for various products or services. For example, DOE entered into a transaction with the United States Enrichment Corporation (USEC), under which USEC would

271

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

SciTech Connect

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.

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

1993-02-01T23:59:59.000Z

272

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

SciTech Connect

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.

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

1993-02-01T23:59:59.000Z

273

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

Annual Energy Outlook 2012 (EIA)

The initial uranium property reserves estimates were based on bore hole radiometric data validated by chemical analysis of samples from cores and drill cuttings. The...

274

Method for fabricating uranium foils and uranium alloy foils  

DOE Patents (OSTI)

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.

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

2006-09-05T23:59:59.000Z

275

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

SciTech Connect

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)

Schneider, Erich; Scopatza, Anthony [The University of Texas at Austin, 1 University Station C2200, Austin TX 78712 (United States); Deinert, Mark [The University of Texas at Austin, 1 University Station C2200, Austin TX 78712 (United States); Cornell University, Ithaca NY 14853 (United States)

2007-07-01T23:59:59.000Z

276

Uranium in Hanford Site 300 Area: Extraction Data on Borehole Sediments  

SciTech Connect

In this study, sediments collected from boreholes drilled in 2010 and 2011 as part of a remedial investigation/feasibility study were characterized. The wells, located within or around two process ponds and one process trench waste site, were characterized in terms of total uranium concentration, mobile fraction of uranium, particle size, and moisture content along the borehole depth. In general, the gravel-dominated sediments of the vadose zone Hanford formation in all investigated boreholes had low moisture contents. Based on total uranium content, a total of 48 vadose zone and periodically rewetted zone sediment samples were selected for more detailed characterization, including measuring the concentration of uranium extracted with 8 M nitric acid, and leached using bicarbonate mixed solutions to determine the liable uranium (U(VI)) contents. In addition, water extraction was conducted on 17 selected sediments. Results from the sediment acid and bicarbonate extractions indicated the total concentrations of anthropogenic labile uranium in the sediments varied among the investigated boreholes. The peak uranium concentration (114.84 g/g, acid extract) in <2-mm size fractions was found in borehole 399 1-55, which was drilled directly in the southwest corner of the North Process Pond. Lower uranium concentrations (~0.32.5 g/g, acid extract) in <2-mm size fractions were found in boreholes 399-1-57, 399-1-58, and 399-1-59, which were drilled either near the Columbia River or inland and upgradient of any waste process ponds or trenches. A general trend of total uranium concentrations was observed that increased as the particle size decreased when relating the sediment particle size and acid extractable uranium concentrations in two selected sediment samples. The labile uranium bicarbonate leaching kinetic experiments on three selected sediments indicated a two-step leaching rate: an initial rapid release, followed by a slow continual release of uranium from the sediment. Based on the uranium leaching kinetic results, quasi equilibrium can be assumed after 1000-h batch reaction time in this study.

Wang, Guohui; Serne, R. Jeffrey; Lindberg, Michael J.; Um, Wooyong; Bjornstad, Bruce N.; Williams, Benjamin D.; Kutynakov, I. V.; Wang, Zheming; Qafoku, Nikolla

2012-11-26T23:59:59.000Z

277

Uranium Oxide Aerosol Transport in Porous Graphite  

SciTech Connect

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.

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

2012-01-23T23:59:59.000Z

278

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

......ingestion of natural uranium in food and drink, and...for the measurement of uranium in urine samples, DU...respect to potential health hazards can be detected...Assessment of exposure to depleted uranium. | In most circumstances......

P. Roth; V. Hllriegl; E. Werner; P. Schramel

2003-07-01T23:59:59.000Z

279

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

......Article Assessment of exposure to depleted uranium P. Roth V. Hollriegl E. Werner...for determining the amount of depleted uranium (DU) incorporated. The problems...Assessment of exposure to depleted uranium. | In most circumstances......

P. Roth; V. Hllriegl; E. Werner; P. Schramel

2003-07-01T23:59:59.000Z

280

Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System  

E-Print Network (OSTI)

Uranium present in low concentration in ocean water has the potential to greatly augment the current fuel reserve for nuclear power generation, but the challenge of extracting it economically remains. Two new designs of ...

Wu, You

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

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

Gasoline and Diesel Fuel Update (EIA)

4. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by origin and material type, 2012 deliveries 4. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors by origin and material type, 2012 deliveries thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent Deliveries Uranium Concentrate Natural UF6 Enriched UF6 Natural UF6 and Enriched UF6 Total U.S.-Origin Uranium Purchases W W W W 9,807 Weighted-Average Price W W W W 59.44 Foreign-Origin Uranium Purchases W W W W 47,713 Weighted-Average Price W W W W 54.07 Total Purchases 28,642 W W 28,878 57,520 Weighted-Average Price 54.20 W W 55.80 54.99 W = Data withheld to avoid disclosure of individual company data. Notes: Totals may not equal sum of components because of independent rounding. Weighted-average prices are not adjusted for inflation. Natural UF6 is uranium hexafluoride. The natural UF6 and enriched UF6 quantity represents only the U3O8 equivalent uranium-component quantity specified in the contract for each delivery of natural UF6 and enriched UF6. The natural UF6 and enriched UF6 weighted-average price represent only the U3O8 equivalent uranium-component price specified in the contract for each delivery of natural UF6 and enriched UF6, and does not include the conversion service and enrichment service components.

282

2013 Uranium Marketing Annual Report  

Gasoline and Diesel Fuel Update (EIA)

accounted for 32%. The remaining 16% originated from Brazil, China, Czech Republic, Germany, Hungary, Malawi, Namibia, Niger, Portugal, and South Africa. COOs purchased uranium...

283

U.S.Uranium Reserves  

Annual Energy Outlook 2012 (EIA)

conditions. The uranium property reserves estimates were based on bore hole radiometric data validated by chemical analysis of samples from cores and drill cuttings. The...

284

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (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" (2013)....

285

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Annual, Tables 10, 11 and 16. 2003-2013-Form EIA-858, "Uranium Marketing Annual Survey". million pounds U 3 O 8 equivalent 1 Includes purchases between...

286

Uranium geochemistry in soil and groundwater at the F and H seepage basins  

SciTech Connect

For 33 years, low activity liquid wastes from the chemical separation areas at the U.S. Department of Energy`s Savannah River Site were disposed of in unlined seepage basins. Soil and associated pore water samples of widely varying groundwater chemistries and contaminant concentrations were collected from the region downgradient of these basins using cone penetrometer technology. Analysis of samples using inductively coupled plasma - mass spectrometry has allowed the investigation of uranium partitioning between the aqueous phase and soil surfaces at this site. The distribution of uranium was examined with respect to the solution and soil chemistry (e.g., pH, redox potential, cation and contaminant concentration) and aqueous-phase chemical speciation modeling. The uranium soil source term at the F- and H-Area Seepage Basins (FHSB) is much smaller than has been used in previous modeling efforts. This should result in a much shorter remediation time and a greater effectiveness of a pump-and-treat design than previously predicted. Distribution coefficients at the (FHSB) were found to vary between 1.2 to 34,000 1 kg{sup {minus}1} for uranium. Differences in sorption of these elements can be explained primarily by changes in aqueous pH and the associated change in soil surface charge. Sorption models were fit directly to sorption isotherms from field samples. All models underestimated the fraction of uranium bound at low aqueous uranium concentrations. Linear models overestimated bound uranium at locations where the aqueous concentration was greater than 500 ppb. Mechanistic models provided a much better estimate of the bound uranium concentrations, especially at high aqueous concentrations. Since a large fraction of the uranium at the site is associated with the low-pH portion of the plume, consideration should be given to pumping water from the lowest pH portions of the plume in the F-Area.

Serkiz, S.M.; Johnson, W.H.

1994-09-01T23:59:59.000Z

287

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

Gasoline and Diesel Fuel Update (EIA)

2. Inventories of natural and enriched uranium by material type as of end of year, 2008-2012 thousand pounds U3O8 equivalent 2. Inventories of natural and enriched uranium by material type as of end of year, 2008-2012 thousand pounds U3O8 equivalent Inventories at the End of the Year Type of Uranium Inventory 2008 2009 2010 2011 P2012 Owners and Operators of U.S. Civilian Nuclear Power Reactors Inventories 82,972 84,757 86,527 89,835 97,466 Uranium Concentrate (U3O8) 12,286 15,094 13,076 14,718 13,454 Natural UF6 46,525 38,463 35,767 35,883 30,168 Enriched UF6 13,748 18,195 25,392 19,596 38,903 Fabricated Fuel (not inserted into a reactor) 10,414 13,006 12,292 19,638 14,941 U.S. Supplier Inventories 27,010 26,774 24,732 22,269 23,264 Uranium Concentrate (U3O8) 12,264 12,132 10,153 7,057 W Natural UF6 W W W W W Enriched UF6 W W W W W

288

The distribution of depleted uranium contamination in Colonie, NY, USA  

Science Journals Connector (OSTI)

Uranium oxide particles were dispersed into the environment from a factory in Colonie (NY, USA) by prevailing winds during the 1960s and '70s. Uranium concentrations and isotope ratios from bulk soil samples have been accurately measured using inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) without the need for analyte separation chemistry. The natural range of uranium concentrations in the Colonie soils has been estimated as 0.72.1?gg?1, with a weighted geometric mean of 1.05?gg?1; the contaminated soil samples comprise uranium up to 50040?gg?1. A plot of 236U/238U against 235U/238U isotope ratios describes a mixing line between natural uranium and depleted uranium (DU) in bulk soil samples; scatter from this line can be accounted for by heterogeneity in the DU particulate. The end-member of DU compositions aggregated in these bulk samples comprises (2.050.06)נ10?3 235U/238U, (3.20.1)נ10?5 236U/238U, and (7.10.3)נ10?6 234U/238U. The analytical method is sensitive to as little as 50ngg?1 DU mixed with the natural uranium occurring in these soils. The contamination footprint has been mapped northward from site, and at least one third of the uranium in a soil sample from the surface 5cm, collected 5.1km NNW of the site, is DU. The distribution of contamination within the surface soil horizon follows a trend of exponential decrease with depth, which can be approximated by a simple diffusion model. Bioturbation by earthworms can account for dispersal of contaminant from the soil surface, in the form of primary uranium oxide particulates, and uranyl species that are adsorbed to organic matter. Considering this distribution, the total mass of uranium contamination emitted from the factory is estimated to be c. 4.8tonnes.

N.S. Lloyd; S.R.N. Chenery; R.R. Parrish

2009-01-01T23:59:59.000Z

289

Separation of uranium from technetium in recovery of spent nuclear fuel  

DOE Patents (OSTI)

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.

Friedman, H.A.

1984-06-13T23:59:59.000Z

290

Marathon/Vitro to seek uranium  

Science Journals Connector (OSTI)

Marathon/Vitro to seek uranium ... Last week, Marathon Oil agreed with Vitro Corp. of America to explore jointly for uranium in North America. ...

1967-03-13T23:59:59.000Z

291

Final Uranium Leasing Program Programmatic Environmental Impact...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

292

Conversion of depleted uranium hexafluoride to a solid uranium compound  

DOE Patents (OSTI)

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.

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

2001-01-01T23:59:59.000Z

293

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

E-Print Network (OSTI)

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

Varughese, Joseph Verghese

2012-06-07T23:59:59.000Z

294

Fernald vacuum transfer system for uranium materials repackaging  

SciTech Connect

The Fernald Environmental Management Project (FEMP) is the site of a former Department of Energy (DOE) uranium processing plant. When production was halted, many materials were left in an intermediate state. Some of this product material included enriched uranium compounds that had to be repackaged for shipment of off-site storage. This paper provides an overview, technical description, and status of a new application of existing technology, a vacuum transfer system, to repackage the uranium bearing compounds for shipment. The vacuum transfer system provides a method of transferring compounds from their current storage configuration into packages that meet the Department of Transportation (DOT) shipping requirements for fissile materials. This is a necessary activity, supporting removal of nuclear materials prior to site decontamination and decommissioning, key to the Fernald site's closure process.

Kaushiva, Shirley; Weekley, Clint; Molecke, Martin; Polansky, Gary

2002-02-24T23:59:59.000Z

295

Effect of Grain Size on Uranium(VI) Surface Complexation Kinetics and Adsorption Additivity  

SciTech Connect

Laboratory experiments were performed to investigate the contribution of variable grain sizes to uranium adsorption/desorption in a sediment collected from the US DOE Hanford site. The sediment was wet-sieved into four size fractions: coarse sand (1-2 mm), medium sand (0.2-1 mm), fine sand (0.05-0.2 mm), and clay/silt fraction (< 0.05mm). For each size fraction and their composite (sediment), batch experiments were performed to determine uranium adsorption isotherms, and stirred flow-cell experiments were conducted to derive kinetic data of uranium adsorption and subsequent desorption. The results showed that uranium adsorption isotherms and adsorption/desorption kinetics were size-specific, reflecting the effects of size-specific adsorption site concentration and kinetic rate constants. The larger-size fraction had a larger mass percentage in the sediment, but with a smaller adsorption site concentration and generally a slower uranium adsorption/desorption rate. The same equilibrium surface complexation reaction and reaction constant could describe uranium adsorption isotherms for all size fractions and the composite after accounting for the effect of adsorption site concentration. Mass-weighted, linear additivity was observed for both uranium adsorption isotherms and adsorption/desorption kinetics in the composite. Our analysis also showed that uranium adsorption site concentration estimated from the adsorption isotherms was 3 orders of magnitude less than a site concentration estimated from sediment surface area and generic site density. One important implication of this study is that grain size distribution may be used to estimate uranium adsorption site, and adsorption/desorption kinetic rates in heterogeneous sediments from a common location.

Shang, Jianying; Liu, Chongxuan; Wang, Zheming; Zachara, John M.

2011-07-27T23:59:59.000Z

296

Isotopic Analysis of Uranium in NIST SRM Glass by Femtosecond Laser Ablation  

SciTech Connect

We employed femtosecond Laser Ablation Multicollector Inductively Coupled Mass Spectrometry for the 11 determination of uranium isotope ratios in a series of standard reference material glasses (NIST 610, 612, 614, and 12 616). This uranium concentration in this series of SRM glasses is a combination of isotopically natural uranium in 13 the materials used to make the glass matrix and isotopically depleted uranium added to increase the uranium 14 elemental concentration across the series. Results for NIST 610 are in excellent agreement with literature values. 15 However, other than atom percent 235U, little information is available for the remaining glasses. We present atom 16 percent and isotope ratios for 234U, 235U, 236U, and 238U for all four glasses. Our results show deviations from the 17 certificate values for the atom percent 235U, indicating the need for further examination of the uranium isotopes in 18 NIST 610-616. Our results are fully consistent with a two isotopic component mixing between the depleted 19 uranium spike and natural uranium in the bulk glass.

Duffin, Andrew M.; Hart, Garret L.; Hanlen, Richard C.; Eiden, Gregory C.

2013-05-19T23:59:59.000Z

297

Growth, CO2 Consumption, and H2 Production of Anabaena variabilis ATCC 29413-U under Different Irradiances and CO2 Concentrations  

E-Print Network (OSTI)

Benemann, J. (2000). Hydrogen production by microalgae, JHall, D. (2000). Hydrogen production by Anabaena variabilisand Veziroglu, T. (2001). Hydrogen production by biological

Berberoglu, Halil; Barra, Natasha; Pilon, Laurent; Jay, Jenny

2008-01-01T23:59:59.000Z

298

Uranyl Protoporphyrin: a New Uranium Complex  

Science Journals Connector (OSTI)

...received 3 times the LD50 of uranium as uranyl protoporphyrin...nitrate, had showed livers depleted of glycogen and kidneys...destruc-tion typical of uranium poisoning. The uranium-damaged...T. Godwin et al., Cancer 8, 601 (1954). 5...excretion of hexavalent uranium in man," in Proc...

ROBERT E. BASES

1957-07-26T23:59:59.000Z

299

Uranium Atoms Don't Share the Vibe  

NLE Websites -- All DOE Office Websites (Extended Search)

Uranium Atoms Don't Share the Vibe Uranium Atoms Don't Share the Vibe Suppose you throw a rock into a pond, but instead of circular waves spreading across the surface, only a single bit of the surface at the rock's entry point oscillates up and down continuously. In the 31 March Physical Review Letters, researchers using the XOR 3-ID-C beamline at the APS report a surprising effect in a crystalline solid: a few-atom-wide vibration that refuses to spread through the material. The team probed heated uranium with x rays and neutrons to study the crystal's vibrations. Although predicted twenty years ago, the effect has never been conclusively seen in a three-dimensional crystal. The result seems to demonstrate the surprising ability of a uniform material to concentrate energy spontaneously. - JR Minkel

300

Safe Operating Procedure SAFETY PROTOCOL: URANIUM  

E-Print Network (OSTI)

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

Farritor, Shane

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

RECOVERY OF URANIUM FROM ORE CONCENTRATES | OSTI, US Dept of...  

Office of Scientific and Technical Information (OSTI)

Re-direct Destination: Temp Data Fields Sheft, I.; Hyman, H.H.; Katz, J.J. Temp Data Storage 3: Argonne National Lab., Lemont, Ill' Short URL for this Page http:t.osti.gov3r7...

302

Uranium Mining Life-Cycle Energy Cost vs. Uranium Resources  

Science Journals Connector (OSTI)

The long-term viability of nuclear energy systems depends on the availability of uranium and on the question, whether the overall energy balance of the fuel cycle is positive, taking into account the full life-cy...

W. Eberhard Falck

2012-01-01T23:59:59.000Z

303

Accumulation and Distribution of Uranium in Rats after Implantation with Depleted Uranium Fragments  

Science Journals Connector (OSTI)

......Environmental and health consequences of depleted uranium use in the 1991 Gulf...Properties, use and health effects of depleted uranium (DU): a general...J. (2002). Health effects of embedded depleted uranium. Mil Med. 167......

Guoying Zhu; Mingguang Tan; Yulan Li; Xiqiao Xiang; Heping Hu; Shuquan Zhao

2009-05-01T23:59:59.000Z

304

Uranium-loaded apoferritin with antibodies attached: molecular design for uranium neutron-capture therapy  

Science Journals Connector (OSTI)

...Molecular design for uranium neutron-capture therapy (cancer/immunotherapy...methodology for cancer therapy. Boron...system using uranium, as described...800 to =400 uranium atoms per apoferritin...uranyl ions were depleted, and loading...

J F Hainfeld

1992-01-01T23:59:59.000Z

305

Characterization of uranium isotopic abundances in depleted uranium metal assay standard 115  

Science Journals Connector (OSTI)

Certified reference material (CRM) 115, Uranium (Depleted) Metal (Uranium Assay Standard), was analyzed using a ... TRITON Thermal Ionization Mass Spectrometer to characterize the uranium isotope-amount ratios. T...

K. J. Mathew; G. L. Singleton; R. M. Essex

2013-04-01T23:59:59.000Z

306

Production  

Science Journals Connector (OSTI)

Production is obtained from proved reserves but the determinants of the scale of production in the industry and country components of the world total are many and complex with some unique to the individual com...

D. C. Ion

1980-01-01T23:59:59.000Z

307

Uranium chloride extraction of transuranium elements from LWR fuel  

DOE Patents (OSTI)

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.

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

1992-08-25T23:59:59.000Z

308

Depleted Uranium Hexafluoride Management  

NLE Websites -- All DOE Office Websites (Extended Search)

for for DUF 6 Conversion Project Environmental Impact Statement Scoping Meetings November/December 2001 Overview Depleted Uranium Hexafluoride (DUF 6 ) Management Program DUF 6 EIS Scoping Briefing 2 DUF 6 Management Program Organizational Chart DUF 6 Management Program Organizational Chart EM-10 Policy EM-40 Project Completion EM-20 Integration EM-50 Science and Technology EM-31 Ohio DUF6 Management Program EM-32 Oak Ridge EM-33 Rocky Flats EM-34 Small Sites EM-30 Office of Site Closure Office of Environmental Management EM-1 DUF 6 EIS Scoping Briefing 3 DUF 6 Management Program DUF 6 Management Program * Mission: Safely and efficiently manage the DOE inventory of DUF 6 in a way that protects the health and safety of workers and the public, and protects the environment DUF 6 EIS Scoping Briefing 4 DUF 6 Inventory Distribution

309

Disposition of uranium-233  

SciTech Connect

The US is developing a strategy for the disposition of surplus weapons-usable uranium-233 ({sup 233}U). The strategy (1) identifies the requirements for the disposition of surplus {sup 233}U; (2) identifies potential disposition options, including key issues to be resolved with each option; and (3) defines a road map that identifies future key decisions and actions. The disposition of weapons-usable fissile materials is part of a US international arms-control program for reduction of the number of nuclear weapons and the quantities of nuclear-weapons-usable materials worldwide. The disposition options ultimately lead to waste forms requiring some type of geological disposal. Major options are described herein.

Tousley, D.R. [Dept. of Energy, Washington, DC (United States). Office of Fissile Materials Disposition; Forsberg, C.W.; Krichinsky, A.M. [Oak Ridge National Lab., TN (United States)

1997-10-16T23:59:59.000Z

310

Competing retention pathways of uranium upon reaction with Fe(II)  

SciTech Connect

Biogeochemical retention processes, including adsorption, reductive precipitation, and incorporation into host minerals, are important in contaminant transport, remediation, and geologic deposition of uranium. Recent work has shown that U can become incorporated into iron (hydr)oxide minerals, with a key pathway arising from Fe(II)-induced transformation of ferrihydrite, (Fe(OH)3nH2O) to goethite (?-FeO(OH)); this is a possible U retention mechanism in soils and sediments. Several key questions, however, remain unanswered regarding U incorporation into iron (hydr)oxides and this pathways contribution to U retention, including: (i) the competitiveness of U incorporation versus reduction to U(IV) and subsequent precipitation of UO2; (ii) the oxidation state of incorporated U; (iii) the effects of uranyl aqueous speciation on U incorporation; and, (iv) the mechanism of U incorporation. Here we use a series of batch reactions conducted at pH ~7, [U(VI)] from 1 to 170 ?M, [Fe(II)] from 0 to 3 mM, and [Ca] at 0 or 4 mM) coupled with spectroscopic examination of reaction products of Fe(II)-induced ferrihydrite transformation to address these outstanding questions. Uranium retention pathways were identified and quantified using extended x-ray absorption fine structure (EXAFS) spectroscopy, x-ray powder diffraction, x-ray photoelectron spectroscopy, and transmission electron microscopy. Analysis of EXAFS spectra showed that 14 to 89% of total U was incorporated into goethite, upon reaction with Fe(II) and ferrihydrite. Uranium incorporation was a particularly dominant retention pathway at U concentrations ? 50 ?M when either uranyl-carbonato or calcium-uranyl-carbonato complexes were dominant, accounting for 64 to 89% of total U. With increasing U(VI) and Fe(II) concentrations, U(VI) reduction to U(IV) became more prevalent, but U incorporation remained a functioning retention pathway. These findings highlight the potential importance of U(V) incorporation within iron oxides as a retention process of U across a wide range of biogeochemical environments and the sensitivity of uranium retention processes to operative (bio)geochemical conditions.

Massey, Michael S.; Lezama Pacheco, Juan S.; Jones, Morris; Ilton, Eugene S.; Cerrato, Jose M.; Bargar, John R.; Fendorf, Scott

2014-10-01T23:59:59.000Z

311

Micro-Scale Heterogeneity in Biogeochemical Uranium Cycling  

SciTech Connect

One method for the in situ remediation of uranium contaminated subsurface environments is the removal of highly soluble U(VI) from groundwater by microbial reduction to the sparingly soluble U(IV) mineral uraninite. Success of this remediation strategy will, in part, be determined by the extent and products of microbial reduction. In heterogeneous subsurface environments, microbial processes will likely yield a combination of U(IV) and U(VI) phases distributed throughout the soil matrix. Here, we use a combination of bulk X-ray absorption spectroscopy (XAS) and micro-focused XAS and X-ray diffraction to determine uranium speciation and distribution with sediment from a pilot-scale uranium remediation project located in Oak Ridge, TN.

Ginder-Vogel, M.; Wu, W.-M.; Kelly, S.; Criddle, C.S.; Carley, J.; Jardine, P.; Kemner, K.M.; Fendorf, S.

2009-06-04T23:59:59.000Z

312

2012 Uranium Marketing Annual Report  

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

Uranium Marketing Annual Uranium Marketing Annual Report May 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 May 2013 U.S. Energy Information Administration | 2012 Uranium Marketing Annual Report i This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. May 2013 U.S. Energy Information Administration | 2012 Uranium Marketing Annual Report ii

313

Uranium Enrichment's $7-Billion Uncertainty  

Science Journals Connector (OSTI)

...229 : 1407 ( 1985 ). Uranium...claims John R. Longenecker, who heads...because it be-John Longenecker '"ou have...based on gas centrifuges Finally...research on the centrifuge technology...21 June 1985, p. 1407...

COLIN NORMAN

1986-04-18T23:59:59.000Z

314

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Annual, Tables 28, 29, 30 and 31. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". Notes: Totals may not equal sum of components because of independent...

315

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Annual, Tables 10, 11 and 16. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". dollars per pound U 3 O 8 equivalent dollars per pound U 3 O 8...

316

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Annual, Tables 28, 29, 30 and 31. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". million pounds U 3 O 8 equivalent million pounds U 3 O 8 equivalent...

317

2013 Uranium Marketing Annual Report  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Annual, Tables 22, 23, 25, and 27. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". - No data reported. 0 10 20 30 40 50 60 70 1994 1995 1996 1997...

318

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

SciTech Connect

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)

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

2013-07-01T23:59:59.000Z

319

Microbial transformations of uranium in wastes and implication on its mobility  

SciTech Connect

Uranium exists in several chemical forms in mining and mill tailings and in nuclear and weapons production wastes. Under appropriate conditions, microorganisms can affect the stability and mobility of U in wastes by altering the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of U in solution and the bioavailability. Dissolution or immobilization of U is brought about by direct enzymatic action or indirect nonenzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of U have been extensively investigated, we have only limited information on the mechanisms of microbial transformations of various chemical forms of U in the presence of electron donors and acceptors.

Suzuki,Y.; Nankawa, T.; Ozaki, T.; Ohnuki, T.; Francis, A.J.; Enokida, Y.; Yamamoto, I.

2008-09-14T23:59:59.000Z

320

The development of uranium foil farication technology utilizing twin roll method for Mo-99 irradiation target  

E-Print Network (OSTI)

MDS Nordion in Canada, occupying about 75% of global supply of Mo-99 isotope, has provided the irradiation target of Mo-99 using the rod-type UAl sub x alloys with HEU(High Enrichment Uranium). ANL (Argonne National Laboratory) through co-operation with BATAN in Indonesia, leading RERTR (Reduced Enrichment for Research and Test Reactors) program substantially for nuclear non-proliferation, has designed and fabricated the annular cylinder of uranium targets, and successfully performed irradiation test, in order to develop the fabrication technology of fission Mo-99 using LEU(Low Enrichment Uranium). As the uranium foils could be fabricated in laboratory scale, not in commercialized scale by hot rolling method due to significant problems in foil quality, productivity and economic efficiency, attention has shifted to the development of new technology. Under these circumstances, the invention of uranium foil fabrication technology utilizing twin-roll casting method in KAERI is found to be able to fabricate LEU or...

Kim, C K; Park, H D

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Long-term criticality control in radioactive waste disposal facilities using depleted uranium  

SciTech Connect

Plant photosynthesis has created a unique planetary-wide geochemistry - an oxidizing atmosphere with oxidizing surface waters on a planetary body with chemically reducing conditions near or at some distance below the surface. Uranium is four orders of magnitude more soluble under chemically oxidizing conditions than it is under chemically reducing conditions. Thus, uranium tends to leach from surface rock and disposal sites, move with groundwater, and concentrate where chemically reducing conditions appear. Earth`s geochemistry concentrates uranium and can separate uranium from all other elements except oxygen, hydrogen (in water), and silicon (silicates, etc). Fissile isotopes include {sup 235}U, {sup 233}U, and many higher actinides that eventually decay to one of these two uranium isotopes. The potential for nuclear criticality exists if the precipitated uranium from disposal sites has a significant fissile enrichment, mass, and volume. The earth`s geochemistry suggests that isotopic dilution of fissile materials in waste with {sup 238}U is a preferred strategy to prevent long-term nuclear criticality in and beyond the boundaries of waste disposal facilities because the {sup 238}U does not separate from the fissile uranium isotopes. Geological, laboratory, and theoretical data indicate that the potential for nuclear criticality can be minimized by diluting fissile materials with-{sup 238}U to 1 wt % {sup 235}U equivalent.

Forsberg, C.W.

1997-02-19T23:59:59.000Z

322

Concentrating Information  

E-Print Network (OSTI)

We introduce the concentrated information of tripartite quantum states. For three parties Alice, Bob and Charlie, it is defined as the maximal mutual information achievable between Alice and Charlie via local operations and classical communication performed by Charlie and Bob. The gap between classical and quantum concentrated information is shown to be an operational figure of merit for a state merging protocol involving shared mixed states and no distributed entanglement. We derive upper and lower bounds on the concentrated information, and obtain a closed expression for arbitrary pure tripartite states in the asymptotic setting. In this situation, one-way classical communication is shown to be sufficient for optimal information concentration.

Alexander Streltsov; Soojoon Lee; Gerardo Adesso

2014-10-23T23:59:59.000Z

323

Response Surface Models To Describe the Effects of Temperature, pH, and Ethanol Concentration on Growth Kinetics and Fermentation End Products of a Pectinatus sp.  

Science Journals Connector (OSTI)

...temperature, pH, and ethanol concentration. The activation energy of this microorganism...different activation energy (E(infa...vol/vol) ethanol for the growth...temperature, pH, and ethanol concentration. The activation energy of this microorganism...

D Watier; H C Dubourguier; I Leguerinel; J P Hornez

1996-04-01T23:59:59.000Z

324

Production  

Energy.gov (U.S. Department of Energy (DOE))

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

325

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

DOE Patents (OSTI)

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.

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

1995-05-02T23:59:59.000Z

326

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

DOE Patents (OSTI)

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.

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

1995-01-01T23:59:59.000Z

327

Study of the distribution of 226Ra in ground water near the uranium industry of Jharkhand, India  

Science Journals Connector (OSTI)

......levels of 226Ra observed in the ground water. Being a mineralised area, variation...226Ra activity concentration in ground water that is used for drinking purpose...Cretescu I. Characterisation and remediation of soils contaminated with uranium......

R. M. Tripathi; V. N. Jha; S. K. Sahoo; N. K. Sethy; A. K. Shukla; V. D. Puranik; H. S. Kushwaha

2012-01-01T23:59:59.000Z

328

Arontis Solar Concentrator AB | Open Energy Information  

Open Energy Info (EERE)

Harnosand, Sweden Zip: SE-871 31 Product: Developer of a medium-concentrating, one axis sun tracking PV system that also produces hot water. References: Arontis Solar Concentrator...

329

Regulation of New Depleted Uranium Uses  

NLE Websites -- All DOE Office Websites (Extended Search)

2-5 2-5 Regulation of New Depleted Uranium Uses Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor The University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark,

330

Advective Desorption of Uranium (VI) from Contaminated Hanford Vadose Zone Sediments under Saturated and Unsaturated Conditions  

SciTech Connect

Sedimentary, hydrologic, and geochemical variations in the Hanford subsurface environment, as well as compositional differences in contaminating waste streams, have created vast differences in the migration and mobility of uranium within the subsurface environment. A series of hydraulically-saturated and -unsaturated column experiments were performed to i.) assess the effect of water content on the advective desorption and migration of uranium from contaminated sediments, and ii.) evaluate the uranium concentration that can develop in porewater and/or groundwater as a result of desorption/dissolution reactions. Flow rate and moisture content were varied to evaluate the influence of contact time, pore water velocity, and macropore desaturation on aqueous uranium concentrations. Sediments were collected from the T-TX-TY tank farm complex and the 300 Area Process Ponds located on the Hanford Site, southeastern Washington State. The sediments vary in depth, mineralogy, and in contamination events. Experiments were conducted under mildly alkaline/calcareous conditions representative of conditions commonly encountered at repository sites across the arid western United States and, in particular, the Hanford site. Results illustrate the release of uranium from these sediments is kinetically controlled and low water contents encountered within the Hanford vadose zone result in the formation of mobile-immobile water regimes, which isolate a fraction of the reactive sites within the sediments, effectively reducing the concentration of uranium released into migrating porewaters.

Wellman, Dawn M.; Zachara, John M.; Liu, Chongxuan; Qafoku, Nikolla; Smith, Steven C.; Forrester, Steven W.

2008-11-03T23:59:59.000Z

331

Variations of the Isotopic Ratios of Uranium in Environmental Samples Containing Traces of Depleted Uranium: Theoretical and Experimental Aspects  

Science Journals Connector (OSTI)

......Samples Containing Traces of Depleted Uranium: Theoretical and Experimental...for the detection of traces of depleted uranium (DU) in environmental samples...percentage composition is about 20% depleted uranium and 80% natural uranium, for......

M. Magnoni; S. Bertino; B. Bellotto; M. Campi

2001-12-01T23:59:59.000Z

332

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......after parenteral injections of depleted uranium S. Fukuda 1 * M. Ikeda 1 M...intramuscular (i.m.) injections of depleted uranium (DU) was examined and the...with uranium. INTRODUCTION Depleted uranium (DU) can affect human health......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

333

Operating and life-cycle costs for uranium-contaminated soil treatment technologies  

SciTech Connect

The development of a nuclear industry in the US required mining, milling, and fabricating a large variety of uranium products. One of these products was purified uranium metal which was used in the Savannah River and Hanford Site reactors. Most of this feed material was produced at the US Department of Energy (DOE) facility formerly called the Feed Materials Production Center at Fernald, Ohio. During operation of this facility, soils became contaminated with uranium from a variety of sources. To avoid disposal of these soils in low-level radioactive waste burial sites, increasing emphasis has been placed on the remediating soils contaminated with uranium and other radionuclides. To address remediation and management of uranium-contaminated soils at sites owned by DOE, the DOE Office of Technology Development (OTD) evaluates and compares the versatility, efficiency, and economics of various technologies that may be combined into systems designed to characterize and remediate uranium-contaminated soils. Each technology must be able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from soil, (3) treat or dispose of resulting waste streams, (4) meet necessary state and federal regulations, and (5) meet performance assessment objectives. The role of the performance assessment objectives is to provide the information necessary to conduct evaluations of the technologies. These performance assessments provide the basis for selecting the optimum system for remediation of large areas contaminated with uranium. One of the performance assessment tasks is to address the economics of full-scale implementation of soil treatment technologies. The cost of treating contaminated soil is one of the criteria used in the decision-making process for selecting remedial alternatives.

Douthat, D.M.; Armstrong, A.Q. [Oak Ridge National Lab., TN (United States). Health Sciences Research Div.; Stewart, R.N. [Univ. of Tennessee, Knoxville, TN (United States)

1995-09-01T23:59:59.000Z

334

Manhattan Project: The Uranium Path to the Bomb, 1942-1944  

Office of Scientific and Technical Information (OSTI)

Alpha Racetrack, Y-12 Electromagnetic Plant, Oak Ridge THE URANIUM PATH TO THE BOMB Alpha Racetrack, Y-12 Electromagnetic Plant, Oak Ridge THE URANIUM PATH TO THE BOMB (1942-1944) Events > The Uranium Path to the Bomb, 1942-1944 Y-12: Design, 1942-1943 Y-12: Construction, 1943 Y-12: Operation, 1943-1944 Working K-25 into the Mix, 1943-1944 The Navy and Thermal Diffusion, 1944 The uranium path to the atomic bomb ran through Oak Ridge, Tennessee. Only if the new plants built at Oak Ridge produced enough enriched uranium-235 would a uranium bomb be possible. General Groves placed two methods into production: 1) electromagnetic, based on the principle that charged particles of the lighter isotope would be deflected more when passing through a magnetic field; and 2) gaseous diffusion, based on the principle that molecules of the lighter isotope, uranium-235, would pass more readily through a porous barrier. Full-scale electromagnetic and gaseous diffusion production plants were built at Oak Ridge at sites designated as "Y-12" and "K-25", respectively.

335

Uranium redistribution under oxidizing conditions in Oklo natural reactor zone 2, Gabon  

SciTech Connect

This mineralogical study was completed to elucidate the relationships between uranium distribution and alteration products of the host rock of natural reactor zone clays just below the reactor core. Uraninite is preserved without any alteration in the reactor core. Uranium minerals are found to be present in the fractures in the reactor zone clays associated with iron-mineral veins, galena and Ti-bearing minerals. Uranium, for which the phases could not be identified, occurs in iron-mineral veins and the iron-mineral rim of pyrite grains in the reactor zone clays. Uranium is not associated with granular iron minerals occurring in the illite matrix of the reactor zone clays. The degree of crystallinity and uranium content of the three iron-bearing alteration products suggest that they formed under different conditions; the granular iron minerals, under alteration conditions where uranium was not mobilized while the iron-mineral veins and the iron-mineral rim of pyrite, under conditions in which uranium is mobilized after the formation of the granular iron minerals.

Isobe, H.; Ohnuki, T. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan); Murakami, T. [Ehime Univ., Matsuyama, Ehime (Japan); Gauthier-Lafaye, F. [CNRS, Strasbourg (France). Centre de Geochemie de la Surface

1995-12-31T23:59:59.000Z

336

An investigation on recycling the recovered uranium from electro-refining process in a CANDU reactor  

Science Journals Connector (OSTI)

Feasibility studies for recycling the recovered uranium from electro-refining process of pyroprocessing into a Canada Deuterium Uranium (CANDU) reactor have been carried out with a source term analysis code ORIGEN-S, a reactor lattice analysis code WIMS-AECL, and a Monte Carlo analysis code MCNPX. The uranium metal can be recovered in a solid cathode during an electro-refining process and has a form of a dendrite phase with about 99.99% expecting recovery purity. Considering some impurities of transuranic (TRU) elements and fission products in the recovered uranium, sensitivity calculations were also performed for the compositions of impurities. For a typical spent PWR fuel of 3.0wt.% of uranium enrichment, 30GWD/tU burnup and 10years cooling, the recovered uranium exhibited an extended burnup up to 14GWD/tU. And among the several safety parameters, the void reactivity at the equilibrium state was estimated 15mk. Additionally, a simple sphere model was constructed to analyze surface dose rates with the Monte Carlo calculations. It was found that the recovered uranium from the spent PWR fuel by electro-refining process has a significant radioactivity depending on the impurities such as fission products.

Chang Je Park; Kweon Ho Kang; Jung Won Lee; Ki Seog Seo

2011-01-01T23:59:59.000Z

337

Spectrophotometric determination of tantalum in boron, uranium, zirconium, and uranium-Zircaloy-2 alloy with malachite green  

Science Journals Connector (OSTI)

Spectrophotometric determination of tantalum in boron, uranium, zirconium, and uranium-Zircaloy-2 alloy with malachite green ...

Allan R. Eberle; Morris W. Lerner

1967-01-01T23:59:59.000Z

338

Evidence of uranium biomineralization in sandstone-hosted roll-front uranium deposits, northwestern China  

E-Print Network (OSTI)

Evidence of uranium biomineralization in sandstone-hosted roll-front uranium deposits, northwestern Available online 25 January 2005 Abstract We show evidence that the primary uranium minerals, uraninite-front uranium deposits, Xinjiang, northwestern China were biogenically precipitated and psuedomorphically

Fayek, Mostafa

339

Production  

Energy.gov (U.S. Department of Energy (DOE))

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

340

Polyethylene Encapsulation of Depleted Uranium Trioxide  

Science Journals Connector (OSTI)

Depleted uranium, in the form of uranium trioxide (UO3) powder, was encapsulated in molten polyethylene forming a stable, dense composite henceforth known as DUPoly (patent pending). Materials were fed by calibra...

J. W. Adams; P. R. Lageraaen; P. D. Kalb

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

2013 IREP Symposium-Bulk Power System Dynamics and Control IX (IREP), August 25-30, 2013, Rethymnon, Greece A Production Simulation Tool for Systems with an Integrated Concentrated Solar  

E-Print Network (OSTI)

, Rethymnon, Greece A Production Simulation Tool for Systems with an Integrated Concentrated Solar Plant2013 IREP Symposium-Bulk Power System Dynamics and Control ­IX (IREP), August 25-30, 2013 with Thermal Energy Storage Ti Xu George Gross University of Illinois at Urbana-Champaign University

Gross, George

342

Studies in the Respiratory and Carbohydrate Metabolism of Plant Tissues. IV. The Relation between the Rate of Carbon Dioxide Production in Potato Tubers in Air Following Anaerobic Conditions, and the Accompanying Changes in Lactic Acid Content and Sugar Concentration  

Science Journals Connector (OSTI)

...Following Anaerobic Conditions, and the Accompanying Changes in Lactic Acid Content and Sugar Concentration J. Barker A. F. El Saifi In part III of this series data were presented for the changes in air following periods of anaerobiosis in the rate of production...

1953-01-01T23:59:59.000Z

343

Standard test method for analysis of urine for uranium-235 and uranium-238 isotopes by inductively coupled plasma-mass spectrometry  

E-Print Network (OSTI)

1.1 This test method covers the determination of the concentration of uranium-235 and uranium-238 in urine using Inductively Coupled Plasma-Mass Spectrometry. This test method can be used to support uranium facility bioassay programs. 1.2 This method detection limits for 235U and 238U are 6 ng/L. To meet the requirements of ANSI N13.30, the minimum detectable activity (MDA) of each radionuclide measured must be at least 0.1 pCi/L (0.0037 Bq/L). The MDA translates to 47 ng/L for 235U and 300 ng/L for 238U. Uranium 234 cannot be determined at the MDA with this test method because of its low mass concentration level equivalent to 0.1 pCi/L. 1.3 The digestion and anion separation of urine may not be necessary when uranium concentrations of more than 100 ng/L are present. 1.4 UnitsThe values stated in picoCurie per liter units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1....

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

344

Supercritical Fluid Extraction and Separation of Uranium from Other Actinides  

SciTech Connect

This paper investigates the feasibility of separating uranium from other actinides by using supercritical fluid carbon dioxide (sc-CO2) as a solvent modified with tri-n-butylphosphate (TBP) for the development of an extraction and counter current stripping technique, which would be a more efficient and environmentally benign technology for used nuclear fuel reprocessing compared to traditional solvent extraction. Several actinides (U(VI), Np(VI), Pu(IV), and Am(III)) were extracted in sc-CO2 modified with TBP over a range of nitric acid concentrations and then the actinides were exposed to reducing and complexing agents to suppress their extractability. According to this study, the separation of uranium from plutonium in sc-CO2 modified with TBP was successful at nitric acid concentrations of less than 3 M in the presence of acetohydroxamic acid or oxalic acid, and the separation of uranium from neptunium was successful at nitric acid concentrations of less than 1 M in the presence of acetohydroxamic acid, oxalic acid, or sodium nitrite.

Donna L. Quach; Bruce J. Mincher; Chien M. Wai

2014-06-01T23:59:59.000Z

345

Updated Conceptual Model for the 300 Area Uranium Groundwater Plume  

SciTech Connect

The 300 Area uranium groundwater plume in the 300-FF-5 Operable Unit is residual from past discharge of nuclear fuel fabrication wastes to a number of liquid (and solid) disposal sites. The source zones in the disposal sites were remediated by excavation and backfilled to grade, but sorbed uranium remains in deeper, unexcavated vadose zone sediments. In spite of source term removal, the groundwater plume has shown remarkable persistence, with concentrations exceeding the drinking water standard over an area of approximately 1 km2. The plume resides within a coupled vadose zone, groundwater, river zone system of immense complexity and scale. Interactions between geologic structure, the hydrologic system driven by the Columbia River, groundwater-river exchange points, and the geochemistry of uranium contribute to persistence of the plume. The U.S. Department of Energy (DOE) recently completed a Remedial Investigation/Feasibility Study (RI/FS) to document characterization of the 300 Area uranium plume and plan for beginning to implement proposed remedial actions. As part of the RI/FS document, a conceptual model was developed that integrates knowledge of the hydrogeologic and geochemical properties of the 300 Area and controlling processes to yield an understanding of how the system behaves and the variables that control it. Recent results from the Hanford Integrated Field Research Challenge site and the Subsurface Biogeochemistry Scientific Focus Area Project funded by the DOE Office of Science were used to update the conceptual model and provide an assessment of key factors controlling plume persistence.

Zachara, John M.; Freshley, Mark D.; Last, George V.; Peterson, Robert E.; Bjornstad, Bruce N.

2012-11-01T23:59:59.000Z

346

Y-12 Uranium Exposure Study  

SciTech Connect

Following the recent restart of operations at the Y-12 Plant, the Radiological Control Organization (RCO) observed that the enriched uranium exposures appeared to involve insoluble rather than soluble uranium that presumably characterized most earlier Y-12 operations. These observations necessitated changes in the bioassay program, particularly the need for routine fecal sampling. In addition, it was not reasonable to interpret the bioassay data using metabolic parameter values established during earlier Y-12 operations. Thus, the recent urinary and fecal bioassay data were interpreted using the default guidance in Publication 54 of the International Commission on Radiological Protection (ICRP); that is, inhalation of Class Y uranium with an activity median aerodynamic diameter (AMAD) of 1 {micro}m. Faced with apparently new workplace conditions, these actions were appropriate and ensured a cautionary approach to worker protection. As additional bioassay data were accumulated, it became apparent that the data were not consistent with Publication 54. Therefore, this study was undertaken to examine the situation.

Eckerman, K.F.; Kerr, G.D.

1999-08-05T23:59:59.000Z

347

The Uranium Institute 24th Annual Symposium  

E-Print Network (OSTI)

the waste U-238 into Pu-239 for burning. By this means 100 times as much energy can be obtained from it to extract the uranium, enriching the natural uranium in the fissile isotope U-235, burning the U-235 than the uranium fuel it burns, leading to a breeder reactor. In addition, if the reactor is a fast

Laughlin, Robert B.

348

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

...least some of the uranium had been irradiated...not represent a health threat, says Danesi...VISAR KRYEZIU/AP Depleted uranium is what's left...not represent a health threat, says...VISAR KRYEZIU/AP Depleted uranium is what's left...

Richard Stone

2002-09-13T23:59:59.000Z

349

D Riso-R-429 Automated Uranium  

E-Print Network (OSTI)

routinely used analytical techniques for uranium determina- tions in geological samples, fissionCM i D Riso-R-429 Automated Uranium Analysis by Delayed-Neutron Counting H. Kunzendorf, L. Løvborg AUTOMATED URANIUM ANALYSIS BY DELAYED-NEUTRON COUNTING H. Kunzendorf, L. Løvborg and E.M. Christiansen

350

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

SciTech Connect

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.

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

2000-01-01T23:59:59.000Z

351

NUCLEAR ISOTOPIC DILUTION OF HIGHLY ENRICHED URANIUM BY DRY BLENDING VIA THE RM-2 MILL TECHNOLOGY  

SciTech Connect

DOE has initiated numerous activities to focus on identifying material management strategies to disposition various excess fissile materials. In particular the INEEL has stored 1,700 Kg of offspec HEU at INTEC in CPP-651 vault facility. Currently, the proposed strategies for dispositioning are (a) aqueous dissolution and down blending to LEU via facilities at SRS followed by shipment of the liquid LEU to NFS for fabrication into LWR fuel for the TVA reactors and (b) dilution of the HEU to 0.9% for discard as a waste stream that would no longer have a criticality or proliferation risk without being processed through some type of enrichment system. Dispositioning this inventory as a waste stream via aqueous processing at SRS has been determined to be too costly. Thus, dry blending is the only proposed disposal process for the uranium oxide materials in the CPP-651 vault. Isotopic dilution of HEU to typically less than 20% by dry blending is the key to solving the dispositioning issue (i.e., proliferation) posed by HEU stored at INEEL. RM-2 mill is a technology developed and successfully tested for producing ultra-fine particles by dry grinding. Grinding action in RM-2 mill produces a two million-fold increase in the number of particles being blended in a centrifugal field. In a previous study, the concept of achieving complete and adequate blending and mixing (i.e., no methods were identified to easily separate and concentrate one titanium compound from the other) in remarkably short processing times was successfully tested with surrogate materials (titanium dioxide and titanium mono-oxide) with different particle sizes, hardness and densities. In the current project, the RM-2 milling technology was thoroughly tested with mixtures of natural uranium oxide (NU) and depleted uranium oxide (DU) stock to prove its performance. The effects of mill operating and design variables on the blending of NU/DU oxides were evaluated. First, NU and DU both made of the same oxide, UO{sub 3}, was used in the testing. Next, NU made up of UO{sub 3} and DU made up of UO{sub 2} was used in the test work. In every test, the blend achieved was characterized by spatial sampling of the ground product and analyzing for {sup 235}U concentration. The test work proved that these uranium oxide materials can be blended successfully. The spatial concentration was found to be uniform. Next, sintered thorium oxide pellets were used as surrogate for light water breeder reactor pellets (LWBR). To simulate LWBR pellet dispositioning, the thorium oxide pellets were first ground to a powder form and then the powder was blended with NU. In these tests also the concentration of {sup 235}U and {sup 232}Th in blended products fell within established limits proving the success of RM-2 milling technology. RM-2 milling technology is applicable to any dry radioactive waste, especially brittle solids that can be ground up and mixed with the non-radioactive stock.

Raj K. Rajamani; Sanjeeva Latchireddi; Vikas Devrani; Harappan Sethi; Roger Henry; Nate Chipman

2003-08-01T23:59:59.000Z

352

Kr ion irradiation study of the depleted-uranium alloys.  

SciTech Connect

Fuel development for the reduced enrichment research and test reactor (RERTR) program is tasked with the development of new low enrichment uranium nuclear fuels that can be employed to replace existing high enrichment 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(Al, Si){sub 3}, (U, Mo)(Al, Si){sub 3}, UMo{sub 2}Al{sub 20}, U{sub 6}Mo{sub 4}Al{sub 43} and UAl{sub 4}. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200 C to ion doses up to 2.5 x 10{sup 19} ions/m{sup 2} ({approx}10 dpa) with an Kr ion flux of 10{sup 16} ions/m{sup 2}/s ({approx}4.0 x 10{sup -3} dpa/s). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

Gan, J.; Keiser, D. D.; Miller, B. D.; Kirk, M. A.; Rest, J.; Allen, T. R.; Wachs, D. M. (Materials Science Division); (INL); (Univ. of Wisconsin)

2010-12-01T23:59:59.000Z

353

Kr Ion Irradiation Study of the Depleted-Uranium Alloys  

SciTech Connect

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.

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

2010-12-01T23:59:59.000Z

354

Acute and chronic toxicity of uranium compounds to Ceriodaphnia-Daphnia dubia  

SciTech Connect

A study to determine the acute and chronic toxicity of uranyl nitrate, hydrogen uranyl phosphate, and uranium dioxide to the organism Ceriodaphnia dubia was conducted. The toxicity tests were conducted by two independent environmental consulting laboratories. Part of the emphasis for this determination was based on concerns expressed by SCDHEC, which was concerned that a safety factor of 100 must be applied to the previous 1986 acute toxicity result of 0.22 mg/L for Daphnia pulex, This would have resulted in the LETF release limits being based on an instream concentration of 0.0022 mg/L uranium. The NPDES Permit renewal application to SCDHEC utilized the results of this study and recommended that the LETF release limit for uranium be based an instream concentration of 0.004 mg/L uranium. This is based on the fact that the uranium releases from the M-Area LETF will be in the hydrogen uranyl phosphate form, or a uranyl phosphate complex at the pH (6--10) of the Liquid Effluent Treatment Facility effluent stream, and at the pH of the receiving stream (5.5 to 7.0). Based on the chronic toxicity of hydrogen uranyl phosphate, a lower uranium concentration limit for the Liquid Effluent Treatment Facility outfall vs. the existing NPDES permit was recommended: The current NPDES permit ``Guideline`` for uranium at outfall M-004 is 0.500 mg/L average and 1.0 mg/L maximum, at a design flowrate of 60 gpm. It was recommended that the uranium concentration at the M-004 outfall be reduced to 0.28 mg/L average, and 0.56 mg/L, maximum, and to reduce the design flowrate to 30 gpm. The 0.28 mg/L concentration will provide an instream concentration of 0.004 mg/L uranium. The 0.28 mg/L concentration at M-004 is based on the combined flows from A-014, A-015, and A-011 outfalls (since 1985) of 1840 gpm (2.65 MGD) and was the flow rate which was utilized in the 1988 NPDES permit renewal application.

Pickett, J.B.; Specht, W.L.; Keyes, J.L.

1993-03-31T23:59:59.000Z

355

Uranium bioaccumulation and biological disorders induced in zebrafish (Danio rerio) after a depleted uranium waterborne exposure  

Science Journals Connector (OSTI)

Because of its toxicity and its ubiquity within aquatic compartments, uranium (U) represents a significant hazard to aquatic species such as fish. In a previous study, we investigated some biological responses in zebrafish either exposed to depleted or to enriched U (i.e., to different radiological activities). However, results required further experiments to better understand biological responses. Moreover, we failed to clearly demonstrate a significant relationship between biological effects and U radiological activity. We therefore chose to herein examine U bioaccumulation and induced effects in zebrafish according to a chemical doseresponse approach. Results showed that U is highly bioconcentrated in fish, according to a time- and concentration-dependent model. Additionally, hepatic antioxidant defenses, red blood cells DNA integrity and brain acetylcholinesterase activity were found to be significantly altered. Generally, the higher the U concentration, the sooner and/or the greater the effect, suggesting a close relationship between accumulation and effect.

Sabrina Barillet; Christelle Adam-Guillermin; Olivier Palluel; Jean-Marc Porcher; Alain Devaux

2011-01-01T23:59:59.000Z

356

Niowave Develops Production Route for Medical Radioisotopes with...  

Office of Science (SC) Website

lack of a domestic supply and current use of techniques requiring weapons grade uranium led Congress to pass the American Medical Isotope Production Act in 2013. The Act...

357

SASSE MODELING OF A URANIUM MOLYBDENUM SEPARATION FLOWSHEET  

SciTech Connect

H-Canyon Engineering (HCE) is evaluating the feasibility of processing material from the Super Kukla Prompt Burst Reactor, which operated at the Nevada Test Site from 1964 to 1978. This material is comprised of 90 wt % uranium (U) (at approximately 20% 235U enrichment) alloyed with 10 wt % molybdenum (Mo). The objective is to dissolve the material in nitric acid (HNO{sub 3}) in the H-Canyon dissolvers and then to process the dissolved material through H-Canyon First and Second Cycle solvent extraction. The U product from Second Cycle will be sent to the highly enriched uranium (HEU) blend down program. In the blend down program, enriched U from the 1EU product stream will be blended with natural U at a ratio of 1 part enriched U per 3.5 parts natural U to meet a reactor fuel specification of 4.95% 235U before being shipped for use by the Tennessee Valley Authority (TVA) in its nuclear plants. The TVA specification calls for <200 mg Mo/g U (200 ppm). Since natural U has about 10 mg Mo/g U, the required purity of the 1EU product prior to blending is about 800 mg Mo/g U, allowing for uncertainties. HCE requested that the Savannah River National Laboratory (SRNL) define a flowsheet for the safe and efficient processing of the U-10Mo material. This report presents a computational model of the solvent extraction portion of the proposed flowsheet. The two main objectives of the computational model are to demonstrate that the Mo impurity requirement can be met and to show that the solvent feed rates in the proposed flowsheet, in particular to 1A and 1D Banks, are adequate to prevent refluxing of U and thereby ensure nuclear criticality safety. SASSE (Spreadsheet Algorithm for Stagewise Solvent Extraction), a Microsoft Excel spreadsheet that supports Argonne National Laboratory's proprietary AMUSE (Argonne Model for Universal Solvent Extraction) code, was selected to model the U/Mo separation flowsheet. SASSE spreadsheet models of H-Canyon First and Second Cycle solvent extraction show that a standard unirradiated fuel flowsheet is capable of separating U from Mo in dissolved solutions of a U/Mo alloy. The standard unirradiated fuel flowsheet is used, except for increases in solvent feed rates to prevent U refluxing and thereby ensure nuclear criticality safety and substitution of higher HNO{sub 3} concentrations for aluminum nitrate (Al(NO{sub 3})){sub 3} in the feed to 1A Bank. (Unlike Savanah River Site (SRS) fuels, the U/Mo material contains no aluminum (Al). As a result, higher HNO3 concentrations are required in the 1AF to provide the necessary salting.) The TVA limit for the final blended product is 200 {micro}g Mo/g U, which translates to approximately 800 mg Mo/g U for the Second Cycle product solution. SASSE calculations give a Mo impurity level of 4 {micro}g Mo/g U in the Second Cycle product solution, conservatively based on Mo organic-to-aqueous distributions measured during minibank testing for previous processing of Piqua reactor fuel. The calculated impurity level is slightly more than two orders of magnitude lower than the required level. The Piqua feed solution contained a significant concentration of Al(NO{sub 3}){sub 3}, which is not present in the feed solution for the proposed flowsheet. Measured distribution data indicate that, without Al(NO{sub 3}){sub 3} or other salting agents present, Mo extracts into the organic phase to a much lesser extent, so that the overall U/Mo separation is better and the Mo impurities in the Second Cycle product drop to negligible concentrations. The 1DF U concentration of 20 g/L specified by the proposed flowsheet requires an increased 1DX organic feed rate to satisfy H-Canyon Double Contingency Analysis (DCA) guidelines for the prevention of U refluxing. The ranges for the 1AX, 1BS, and 1DX organic flow rates in the proposed flowsheet are set so that the limiting ratios of organic/aqueous flow rates exactly meet the minimum values specified by the DCA.

Laurinat, J

2007-05-31T23:59:59.000Z

358

D0 Decomissioning : Storage of Depleted Uranium Modules Inside D0 Calorimeters after the Termination of D0 Experiment  

SciTech Connect

Dzero liquid Argon calorimeters contain hadronic modules made of depleted uranium plates. After the termination of DO detector's operation, liquid Argon will be transferred back to Argon storage Dewar, and all three calorimeters will be warmed up. At this point, there is no intention to disassemble the calorimeters. The depleted uranium modules will stay inside the cryostats. Depleted uranium is a by-product of the uranium enrichment process. It is slightly radioactive, emits alpha, beta and gamma radiation. External radiation hazards are minimal. Alpha radiation has no external exposure hazards, as dead layers of skin stop it; beta radiation might have effects only when there is a direct contact with skin; and gamma rays are negligible - levels are extremely low. Depleted uranium is a pyrophoric material. Small particles (such as shavings, powder etc.) may ignite with presence of Oxygen (air). Also, in presence of air and moisture it can oxidize. Depleted uranium can absorb moisture and keep oxidizing later, even after air and moisture are excluded. Uranium oxide can powder and flake off. This powder is also pyrographic. Uranium oxide may create health problems if inhaled. Since uranium oxide is water soluble, it may enter the bloodstream and cause toxic effects.

Sarychev, Michael; /Fermilab

2011-09-21T23:59:59.000Z

359

Criticality safety concerns of uranium deposits in cascade equipment  

SciTech Connect

The Paducah and Portsmouth Gaseous Diffusion Plants enrich uranium in the {sup 235}U isotope by diffusing gaseous uranium hexafluoride (UF{sub 6}) through a porous barrier. The UF{sub 6} gaseous diffusion cascade utilized several thousand {open_quotes}stages{close_quotes} of barrier to produce highly enriched uranium (HEU). Historically, Portsmouth has enriched the Paducah Gaseous Diffusion Plant`s product (typically 1.8 wt% {sup 235}U) as well as natural enrichment feed stock up to 97 wt%. Due to the chemical reactivity of UF{sub 6}, particularly with water, the formation of solid uranium deposits occur at a gaseous diffusion plant. Much of the equipment operates below atmospheric pressure, and deposits are formed when atmospheric air enters the cascade. Deposits may also be formed from UF{sub 6} reactions with oil, UF{sub 6} reactions with the metallic surfaces of equipment, and desublimation of UF{sub 6}. The major deposits form as a result of moist air in leakage due to failure of compressor casing flanges, blow-off plates, seals, expansion joint convolutions, and instrument lines. This report describes criticality concerns and deposit disposition.

Plaster, M.J. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States)

1996-12-31T23:59:59.000Z

360

US developments in technology for uranium enrichment  

SciTech Connect

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.

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

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Deep liquid-chromatographic purification of uranium extract from technetium  

SciTech Connect

The recycling of uranium in the nuclear fuel cycle requires the removal of a number of radioactive and stable impurities like {sup 99}Tc from spent fuels. In order to improve the grade of uranium extract purification from technetium the method of liquid chromatography and the apparatus for its performance have been developed. Process of technetium extraction and concentrating in aqueous solution containing reducing agent has been studied on simulated solutions (U-Tc-HNO{sub 3}-30% TBP-isoparM). The dynamic tests of the method have been carried out on the laboratory unit. Solution of diformyl-hydrazine in nitric acid was used as a stationary phase. Silica gel with specific surface of 186 m{sup 2}/g was used as a carrier of the stationary phase. It is shown that the volume of purified extract increases as the solution temperature increases, concentration of reducing agent increases and extract flow rate decreases. It is established that the technetium content in uranium by this method could achieve a value below 0.3 ppm. Some variants of overload and composition of the stationary phase containing the extracted technetium have been offered and tested. It is defined that the method provides reduction of processing medium-active wastes by more than 10 times during finish refining process. (authors)

Volk, V.; Dvoeglazov, K; Podrezova, L.; Vidanov, V.; Pavlyukevich, E. [OAO State Research Center - VNIINM, Rogov str., bld. 5, Moscow (Russian Federation)

2013-07-01T23:59:59.000Z

362

Investigation of Uranium Polymorphs  

SciTech Connect

The UO3-water system is complex and has not been fully characterized, even though these species are common throughout the nuclear fuel cycle. As an example, most production schemes for UO3 result in a mixture of up to six or more different polymorphic phases, and small differences in these conditions will affect phase genesis that ultimately result in measureable changes to the end product. As a result, this feature of the UO3-water system may be useful as a means for determining process history. This research effort attempts to better characterize the UO3-water system with a variety of optical techniques for the purpose of developing some predictive capability for estimating process history in polymorphic phases of unknown origin. Three commercially relevant preparation methods for the production of UO3 were explored. Previously unreported low temperature routes to ?- and ?-UO3 were discovered. Raman and fluorescence spectroscopic libraries were established for pure and mixed polymorphic forms of UO3 in addition to the common hydrolysis products of UO3. An advantage of the sensitivity of optical fluorescence microscopy over XRD has been demonstrated. Preliminary aging studies of the ? and ? forms of UO3 have been conducted. In addition, development of a 3-D phase field model used to predict phase genesis of the system was initiated. Thermodynamic and structural constants that will feed the model have been gathered from the literature for most of the UO3 polymorphic phases.

Sweet, Lucas E.; Henager, Charles H.; Hu, Shenyang Y.; Johnson, Timothy J.; Meier, David E.; Peper, Shane M.; Schwantes, Jon M.

2011-08-01T23:59:59.000Z

363

Relationships between soil CO2 concentration and CO2 production, temperature, water content, and gas diffusivity: implications for field studies through sensitivity analyses  

Science Journals Connector (OSTI)

Soil CO2 levels reflect CO2 production and transport in soil and provide valuable information about soil CO2 dynamics. However, extracting information from soil CO2 profiles is often difficult because of the comp...

Shoji Hashimoto; Hikaru Komatsu

2006-02-01T23:59:59.000Z

364

Activity concentrations of 224Ra, 226Ra, 228Ra and 40K radionuclides in refinery products and the additional radiation dose originated from oil residues in Turkey  

Science Journals Connector (OSTI)

......radioactive materials (TENORM). Oil and gas production, coal mining and combustion, drinking or waste water treatments...Sources from the point of view of radiation protection, taking economic and social factors into account, the common goal is to keep......

A. Parmaksiz; Y. Agus; F. Bulgurlu; E. Bulur; . Yildiz; T. nc

2013-10-01T23:59:59.000Z

365

Ion exchange technology in the remediation of uranium contaminated groundwater at Fernald  

SciTech Connect

Using pump and treat methodology, uranium contaminated groundwater is being removed from the Great Miami Aquifer at the Fernald Environmental Management Project (FEMP) per the FEMP Record of Decision (ROD) that defines groundwater cleanup. Standard extraction wells pump about 3900 gallons-per-minute (gpm) from the aquifer through five ion exchange treatment systems. The largest treatment system k the Advanced Wastewater Treatment (AWWT) Expansion System with a capacity of 1800 gpm, which consists of three trains of two vessels. The trains operate in parallel treating 600 gpm each, The two vessels in each train operate in series, one in lead and one in lag. Treated groundwater is either reinfected back into the aquifer to speed up the aquifer cleanup processor discharged to the Great Miami River. The uranium regulatory ROD limit for discharge to the river is 20 parts per billion (ppb), and the FEMP uranium administrative action level for reinfection is 10 ppb. Spent (i.e., a resin that no longer adsorbs uranium) ion exchange resins must either be replaced or regenerated. The regeneration of spent ion exchange resins is considerably more cost effective than their replacement. Therefore, a project was undertaken to learn how best to regenerate the resins in the groundwater vessels. At the outset of this project, considerable uncertainty existed as to whether a spent resin could be regenerated successfully enough so that it performed as well as new resin relative to achieving very low uranium concentrations in the effluent. A second major uncertain y was whether the operational lifetime of a regenerated resin would be similar to that of a new resin with respect to uranium loading capacity and effluent concentration behavior. The project was successful in that a method for regenerating resins has been developed that is operationally efficient, that results in regenerated resins yielding uranium concentrations much lower than regulatory limits, and that results in regenerated resins with operational lifetimes comparable to new resins.

Chris Sutton; Cathy Glassmeyer; Steve Bozich

2000-09-29T23:59:59.000Z

366

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel  

NLE Websites -- All DOE Office Websites (Extended Search)

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel ... Fact Sheet Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel

367

Uranium at Y-12: Rolling and Forming | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

Rolling ... Rolling ... Uranium at Y-12: Rolling and Forming Posted: July 22, 2013 - 3:40pm | Y-12 Report | Volume 10, Issue 1 | 2013 Rolling involves preheating a uranium or uranium alloy workpiece and passing it through a mill to reduce its thickness. This is useful in creating reactor fuel element foils and other products. Rolling mill operators possess a strong grasp of thickness-reduction limits, reheating intervals and temperatures, metallurgical phases, rolling speed and force, impurity influences and other techniques. Forming of enriched uranium is done through a process called hydroforming, a way of shaping malleable metals. Y-12 hydroform operators are highly skilled and trained machinists. Forming requires knowledge of friction on the workpiece, high-pressure application, tooling temperature and other

368

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

SciTech Connect

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.

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

2013-02-01T23:59:59.000Z

369

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel  

National Nuclear Security Administration (NNSA)

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel ... Fact Sheet Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel

370

Recovery of uranium from phosphoric acid medium by polymeric composite beads encapsulating organophosphorus extractants  

SciTech Connect

The present study deals with the preparation and evaluation of the poly-ethersulfone (PES) based composite beads encapsulating synergistic mixture of D2EHPA and Cyanex 923 (at 4:1 mole ratio) for the separation of uranium from phosphoric acid medium. SEM was used for the characterization of the composite materials. Addition of 1% PVA (polyvinyl alcohol) improved the internal morphology and porosity of the beads. Additionally, microscopic examination of the composite bead confirmed central coconut type cavity surrounded by porous polymer layer of the beads through which exchange of metal ions take place. Effect of various experimental variables including aqueous acidity, metal ion concentration in aqueous feed, concentration of organic extractant inside the beads, extractant to polymer ratio, liquid to solid (L/S) ratio and temperature on the extraction of uranium was studied. Increase in acidity (1-6 M), L/S ratio (1- 10), metal ion concentration (0.2-3 g/L U{sub 3}O{sub 8}) and polymer to extractant ratio (1:4 -1:10) led to decrease in extraction of uranium. At 5.5 M (comparable to wet process phosphoric acid concentration) the extraction of uranium was about 85% at L/S ratio 5. Increase in extractant concentration inside the bead resulted in enhanced extraction of metal ion. Increase in temperature in the range of 30 to 50 Celsius degrees increased the extraction, whereas further increase to 70 C degrees led to the decrease in extraction of uranium. Amongst various reagents tested, stripping of uranium was quantitative by 12% Na{sub 2}CO{sub 3} solution. Polymeric beads were found to be stable and reusable up-to 10 cycles of extraction/stripping. (authors)

Singh, D.K.; Yadav, K.K.; Varshney, L.; Singh, H. [Bhabha Atomic Research Centre, Mumbai 400 085 (India)

2013-07-01T23:59:59.000Z

371

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

SciTech Connect

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.

PLYS, M.G.

2000-10-10T23:59:59.000Z

372

Advancing Performance Assessment for Disposal of Depleted Uranium at Clive Utah - 12493  

SciTech Connect

A Performance Assessment (PA) for disposal of depleted uranium (DU) waste has recently been completed for a potential disposal facility at Clive in northwestern Utah. For the purposes of this PA, 'DU waste' includes uranium oxides of all naturally-occurring isotopes, though depleted in U-235, varying quantities of other radionuclides introduced to the uranium enrichment process in the form of used nuclear reactor fuel (reactor returns), and decay products of all of these radionuclides. The PA will be used by the State of Utah to inform an approval decision for disposal of DU waste at the facility, and will be available to federal regulators as they revisit rulemaking for the disposal of DU. The specific performance objectives of the Clive DU PA relate to annual individual radiation dose within a 10,000-year performance period, groundwater concentrations of specific radionuclides within a 500-year compliance period, and site stability in the longer term. Fate and transport processes that underlie the PA model include radioactive decay and ingrowth, diffusion in gaseous and water phases, water advection in unsaturated and saturated zones, transport caused by plant and animal activity, cover naturalization, natural and anthropogenic erosion, and air dispersion. Fate and transport models were used to support the dose assessment and the evaluation of groundwater concentrations. Exposure assessment was based on site-specific scenarios, since the traditional human exposure scenarios suggested by DOE and NRC guidance are unrealistic for this site. Because the U-238 in DU waste reaches peak radioactivity (secular equilibrium) after 2 million years (My) following its separation, the PA must also evaluate the impact of climate change cycles, including the return of pluvial lakes such as Lake Bonneville. The first draft of the PA has been submitted to the State of Utah for review. The results of this preliminary analysis indicate that doses are very low for the site-specific receptors for the 10,000-year compliance period. This is primarily because DU waste is not highly radioactive within this time frame, the DU waste is assumed to be buried beneath zones exposed by erosion, groundwater concentrations of DU waste constituents do not exceed groundwater protection limits with in the 500-year compliance period, and the first deep lake occurrence will disperse DU waste across a large area, and will ultimately be covered by lake-derived sediment. A probabilistic PA model was constructed that considered DU waste and decay product doses to site-specific receptors for a 10,000-yr performance period, as well as deep-time effects. The quantitative results are summarized in Table VII. Doses (as TEDE) are always less than 5 mSv in a year, and doses to the offsite receptors are always much less than 0.25 mSv in a year. Groundwater concentrations of Tc-99 are always less than its GWPL except when the Tc-99 contaminated waste is disposed below grade. Even in this case, the median groundwater concentration is only 4.18 Bq/L (113 pCi/L), which is more than one order of magnitude less than the GWPL for Tc-99. The results overall suggest that there are disposal configurations that can be used to dispose of the proposed quantities of DU waste that are adequately protective of human health. (authors)

Black, Paul; Tauxe, John; Perona, Ralph; Lee, Robert; Catlett, Kate; Balshi, Mike; Fitzgerald, Mark; McDermott, Greg [Neptune and Company, Inc., Los Alamos, New Mexico 87544 (United States); Shrum, Dan; McCandless, Sean; Sobocinski, Robert; Rogers, Vern [EnergySolutions, LLC, Salt Lake City, Utah 84101 (United States)

2012-07-01T23:59:59.000Z

373

US uranium mining industry: background information on economics and emissions  

SciTech Connect

A review of the US uranium mining industry has revealed a generally depressed industry situation. The 1982 U/sub 3/O/sub 8/ production from both open-pit and underground mines declined to 3800 and 6300 tons respectively with the underground portion representing 46% of total production. US exploration and development has continued downward in 1982. Employment in the mining and milling sectors has dropped 31% and 17% respectively in 1982. Representative forecasts were developed for reactor fuel demand and U/sub 3/O/sub 8/ production for the years 1983 and 1990. Reactor fuel demand is estimated to increase from 15,900 tons to 21,300 tons U/sub 3/O/sub 8/ respectively. U/sub 3/O/sub 8/ production, however, is estimated to decrease from 10,600 tons to 9600 tons respectively. A field examination was conducted of 29 selected underground uranium mines that represent 84% of the 1982 underground production. Data was gathered regarding population, land ownership and private property valuation. An analysis of the increased cost to production resulting from the installation of 20-meter high exhaust borehole vent stacks was conducted. An assessment was made of the current and future /sup 222/Rn emission levels for a group of 27 uranium mines. It is shown that /sup 222/Rn emission rates are increasing from 10 individual operating mines through 1990 by 1.2 to 3.8 times. But for the group of 27 mines as a whole, a reduction of total /sup 222/Rn emissions is predicted due to 17 of the mines being shutdown and sealed. The estimated total /sup 222/Rn emission rate for this group of mines will be 105 Ci/yr by year end 1983 or 70% of the 1978-79 measured rate and 124 Ci/yr by year end 1990 or 83% of the 1978-79 measured rate.

Bruno, G.A.; Dirks, J.A.; Jackson, P.O.; Young, J.K.

1984-03-01T23:59:59.000Z

374

Global terrestrial uranium supply and its policy implications : a probabilistic projection of future uranium costs  

E-Print Network (OSTI)

An accurate outlook on long-term uranium resources is critical in forecasting uranium costresource relationships, and for energy policy planning as regards the development and deployment of nuclear fuel cycle alternatives. ...

Matthews, Isaac A

2010-01-01T23:59:59.000Z

375

TRIMOLECULAR REACTIONS OF URANIUM HEXAFLUORIDE WITH WATER  

SciTech Connect

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.

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

2010-02-25T23:59:59.000Z

376

Process Flow Chart for Immobilizing of Radioactive High Concentration Sodium Hydroxide Product from the Sodium Processing Facility at the BN-350 Nuclear power plant in Aktau, Kazakhstan  

SciTech Connect

This paper describes the results of a joint research investigations carried out by the group of Kazakhstan, British and American specialists in development of a new material for immobilization of radioactive 35% sodium hydroxide solutions from the sodium coolant processing facility of the BN-350 nuclear power plant. The resulting solid matrix product, termed geo-cement stone, is capable of isolating long lived radionuclides from the environment. The physico-mechanical properties of geo-cement stone have been investigated and the flow chart for its production verified in a full scale experiments. (author)

Burkitbayev, M.; Omarova, K.; Tolebayev, T. [Ai-Farabi Kazakh National University, Chemical Faculty, Republic of Kazakhstan (Kazakhstan); Galkin, A. [KATEP Ltd., Republic of Kazakhstan (Kazakhstan); Bachilova, N. [NIISTROMPROEKT Ltd., Republic of Kazakhstan (Kazakhstan); Blynskiy, A. [Nuclear Technology Safety Centre, Republic of Kazakhstan (Kazakhstan); Maev, V. [MAEK-Kazatomprom Ltd., Republic of Kazakhstan (Kazakhstan); Wells, D. [NUKEM Limited- a member of the Freyssinet Group, Winfrith Technology Centre, Dorchester, Dorset (United Kingdom); Herrick, A. [NUKEM Limited- a member of the Freyssinet Group, Caithness (United Kingdom); Michelbacher, J. [Idaho National Laboratory, Idaho Falls (United States)

2008-07-01T23:59:59.000Z

377

Potential Uses of Depleted Uranium  

NLE Websites -- All DOE Office Websites (Extended Search)

POTENTIAL USES OF DEPLETED URANIUM POTENTIAL USES OF DEPLETED URANIUM Robert R. Price U.S. Department of Energy Germantown, Maryland 20874 M. Jonathan Haire and Allen G. Croff Chemical Technology Division Oak Ridge National Laboratory * Oak Ridge, Tennessee 37831-6180 June 2000 For American Nuclear Society 2000 International Winter and Embedded Topical Meetings Washington, D.C. November 12B16, 2000 The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. _________________________

378

Semiconductive Properties of Uranium Oxides  

NLE Websites -- All DOE Office Websites (Extended Search)

SEMICONDUCTIVE PROPERTIES OF URANIUM OXIDES SEMICONDUCTIVE PROPERTIES OF URANIUM OXIDES Thomas Meek Materials Science Engineering Department University of Tennessee Knoxville, TN 37931 Michael Hu and M. Jonathan Haire Chemical Technology Division Oak Ridge National Laboratory * Oak Ridge, Tennessee 37831-6179 August 2000 For the Waste Management 2001 Symposium Tucson, Arizona February 25-March 1, 2001 The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. _________________________ * Oak Ridge National Laboratory, managed by UT-Battelle, LLC, for the U.S. Department of Energy

379

Standard specification for uranium hexafluoride enriched to less than 5 % 235U  

E-Print Network (OSTI)

1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any 235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the pro...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

380

Depleted Uranium (DU) Cermet Waste Package  

NLE Websites -- All DOE Office Websites (Extended Search)

Package Package Depleted Uranium (DU) Cermet Waste Package The steel components of the waste package could be replaced with a uranium cermet. The cermet contains uranium dioxide particulates, which are embedded in steel. Cermets are made with outer layers of clean steel; thus, there is no radiation-contamination hazard in handling the waste packages. Because cermets are made of the same materials that would normally be found in the YM repository (uranium dioxide and steel), there are no chemical compatibility issues. From half to all of the DU inventory in the United States could be used for this application. Depleted Uranium Dioxide Steel Cermet Cross Section of a Depleted Uranium Dioxide Steel Cermet Follow the link below for more information on Cermets:

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Depleted Uranium Uses Research and Development  

NLE Websites -- All DOE Office Websites (Extended Search)

DU Uses DU Uses Depleted Uranium Uses Research & Development A Depleted Uranium Uses Research and Development Program was initiated to explore beneficial uses of depleted uranium (DU) and other materials resulting from conversion of depleted UF6. A Depleted Uranium Uses Research and Development Program was initiated to explore the safe, beneficial use of depleted uranium and other materials resulting from conversion of depleted UF6 (e.g., fluorine and empty carbon steel cylinders) for the purposes of resource conservation and cost savings compared with disposal. This program explored the risks and benefits of several depleted uranium uses, including uses as a radiation shielding material, a catalyst, and a semi-conductor material in electronic devices.

382

Bayesian Prediction of Mean Indoor Radon Concentrations for Minnesota Counties  

E-Print Network (OSTI)

from the National Uranium Resource Evaluation (NURE). Thatpart of the National Uranium Resource Evaluation (NURE). The

Price, P.N.

2011-01-01T23:59:59.000Z

383

Review of uranium bioassay techniques  

SciTech Connect

A variety of analytical techniques is available for evaluating uranium in excreta and tissues at levels appropriate for occupational exposure control and evaluation. A few (fluorometry, kinetic phosphorescence analysis, {alpha}-particle spectrometry, neutron irradiation techniques, and inductively-coupled plasma mass spectrometry) have also been demonstrated as capable of determining uranium in these materials at levels comparable to those which occur naturally. Sample preparation requirements and isotopic sensitivities vary widely among these techniques and should be considered carefully when choosing a method. This report discusses analytical techniques used for evaluating uranium in biological matrices (primarily urine) and limits of detection reported in the literature. No cost comparison is attempted, although references are cited which address cost. Techniques discussed include: {alpha}-particle spectrometry; liquid scintillation spectrometry, fluorometry, phosphorometry, neutron activation analysis, fission-track counting, UV-visible absorption spectrophotometry, resonance ionization mass spectrometry, and inductively-coupled plasma mass spectrometry. A summary table of reported limits of detection and of the more important experimental conditions associated with these reported limits is also provided.

Bogard, J.S.

1996-04-01T23:59:59.000Z

384

Video: Part of the 'Hole' Story (of Uranium Hexafluoride Cylinders)  

NLE Websites -- All DOE Office Websites (Extended Search)

Hole Story Hole Story Part of the "Hole" Story (of Uranium Hexafluoride Cylinders) Holes in the depleted Uranium Hexafluoride storage cylinders are investigated. It is shown that corrosion products cause the openings to be self-healing. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:00 Part of the 'Hole' Story Video 00:05 One of the depleted UF6 cylinder storage lots at Portsmouth Video 00:28 48G cylinders, each containing 14 tons of depleted UF6, in storage Video 00:52 Stacked 48G cylinders Video 01:35 UF6 sealed in glass tube Video 02:01 A lifting lug of one cylinder damaging a neighboring cylinder Video 02:37 Damage to small hole cylinder from impact with a lifting lub of an adjoining cylinder

385

Shock induced multi-mode damage in depleted uranium  

SciTech Connect

Recent dynamic damage studies on depleted uranium samples have revealed mixed mode failure mechanisms leading to incipient cracking as well as ductile failure processes. Results show that delamination of inclusions upon compression may provide nucleation sites for damage initiation in the form of crack tip production. However, under tension the material propagates cracks in a mixed shear localization and mode-I ductile tearing and cracking. Cracks tips appear to link up through regions of severe, shear dominated plastic flow. Shock recovery experiments were conducted on a 50 mm single stage light gas gun. Serial metallographic sectioning was conducted on the recovered samples to characterize the bulk response of the sample. Experiments show delaminated inclusions due to uniaxial compression without damage propagation. Further results show the propagation of the damage through tensile loading to the incipient state, illustrating ductile processes coupled with mixed mode-I tensile ductile tearing, shear localization, and mode-I cracking in depleted uranium.

Koller, Darcie D [Los Alamos National Laboratory; Cerreta, Ellen K [Los Alamos National Laboratory; Gray, Ill, George T [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

386

DOE/EA-1155 Uranium Mill Tailing Remedial Action Project  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

55 55 Uranium Mill Tailing Remedial Action Project Environmental Assessment of Ground- Water Compliance Activities At the Uranium Mill Tailings Site Spook, Wyoming February 1997 Prepared by U.S. Department of Energy Albuquerque Operations Office Grand Junction Office This page intentionally blank : illegible Portions of tbis DISCLAIMER document may be in electronic image products. Images are produced fiom the best available original dOClMXlf?IlL DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, make any warranty, express or implied, or assumes any legal liabili- ty or responsibility for the accuracy, completeness,

387

SHEEP MOUNTAIN URANIUM PROJECT CROOKS GAP, WYOMING  

E-Print Network (OSTI)

;PROJECT OVERVIEW ·Site Location·Site Location ·Fremont , Wyoming ·Existing Uranium Mine Permit 381C·Existing Uranium Mine Permit 381C ·Historical Operation ·Western Nuclear Crooks Gap Project ·Mined 1956 ­ 1988 and Open Pit Mining ·Current Mine Permit (381C) ·Updating POO, Reclamation Plan & Bond ·Uranium Recovery

388

Depleted uranium exposure and health effects in Gulf War veterans  

Science Journals Connector (OSTI)

...2006 research-article Depleted uranium exposure and health effects in Gulf War...Medicine) Gulf War and health. In Depleted uranium, pyridostigmine bromide...McDiarmid, M.A , Health effects of depleted uranium on exposed Gulf War...

2006-01-01T23:59:59.000Z

389

Excretion of depleted uranium by Gulf war veterans  

Science Journals Connector (OSTI)

......Dosimetry Article Excretion of depleted uranium by Gulf war veterans R. E...personnel had potential intakes of depleted uranium (DU), including shrapnel...excretion rate. Excretion of depleted uranium by Gulf War veterans. | During......

R. E. Toohey

2003-07-01T23:59:59.000Z

390

Depleted uranium - induced malignant transformation in human lung epithelial cells.  

Science Journals Connector (OSTI)

...Washington, DC Abstract 3590: Depleted uranium-induced leukemia: Epigenetic...with leukemia development. Depleted uranium is used in military missions...Karvelisse Miller, Max Costa. Depleted uranium-induced leukemia: Epigenetic...

Aldona A. Karaczyn; Hong Xie; and John P. Wise

2006-04-15T23:59:59.000Z

391

Structural Sequestration of Uranium in Bacteriogenic Manganese...  

NLE Websites -- All DOE Office Websites (Extended Search)

of metal-contaminated waters (in engineered remediation technologies, for example)?" Uranium is a key contaminant of concern at US DOE sites and shuttered mining and ore...

392

Uranium Weapons Components Successfully Dismantled | National...  

National Nuclear Security Administration (NNSA)

Successfully Dismantled March 20, 2007 Uranium Weapons Components Successfully Dismantled Oak Ridge, TN Continuing its efforts to reduce the size of the U.S. nuclear weapons...

393

U.S. Uranium Reserves Estimates  

Gasoline and Diesel Fuel Update (EIA)

The initial uranium property reserves estimates were based on bore hole radiometric data validated by chemical analysis of samples from cores and drill cuttings. The...

394

Adsorptive Stripping Voltammetric Measurements of Trace Uranium...  

NLE Websites -- All DOE Office Websites (Extended Search)

Measurements of Trace Uranium at the Bismuth Film Electrode. Abstract: Bismuth-coated carbon-fiber electrodes have been successfully applied for adsorptive-stripping...

395

Biogeochemical Processes In Ethanol Stimulated Uranium Contaminated...  

NLE Websites -- All DOE Office Websites (Extended Search)

A laboratory incubation experiment was conducted with uranium contaminated subsurface sediment to assess the geochemical and microbial community response to ethanol amendment. A...

396

Comparison of actinide production in traveling wave and pressurized water reactors  

SciTech Connect

The geopolitical problems associated with civilian nuclear energy production arise in part from the accumulation of transuranics in spent nuclear fuel. A traveling wave reactor is a type of breed-burn reactor that could, if feasible, reduce the overall production of transuranics. In one possible configuration, a cylinder of natural or depleted uranium would be subjected to a fast neutron flux at one end. The neutrons would transmute the uranium, producing plutonium and higher actinides. Under the right conditions, the reactor could become critical, at which point a self-stabilizing fission wave would form and propagate down the length of the reactor cylinder. The neutrons from the fission wave would burn the fissile nuclides and transmute uranium ahead of the wave to produce additional fuel. Fission waves in uranium are driven largely by the production and fission of {sup 239}Pu. Simulations have shown that the fuel burnup can reach values greater than 400 MWd/kgIHM, before fission products poison the reaction. In this work we compare the production of plutonium and minor actinides produced in a fission wave to that of a UOX fueled light water reactor, both on an energy normalized basis. The nuclide concentrations in the spent traveling wave reactor fuel are computed using a one-group diffusion model and are verified using Monte Carlo simulations. In the case of the pressurized water reactor, a multi-group collision probability model is used to generate the nuclide quantities. We find that the traveling wave reactor produces about 0.187 g/MWd/kgIHM of transuranics compared to 0.413 g/MWd/kgIHM for a pressurized water reactor running fuel enriched to 4.95 % and burned to 50 MWd/kgIHM. (authors)

Osborne, A.G.; Smith, T.A.; Deinert, M.R. [Department of Mechanical Engineering, University of Texas at Austin, Austin, TX (United States)

2013-07-01T23:59:59.000Z

397

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......chemical forms of the uranium in the body after intake...REFERENCES 1 Mould R. F. Depleted uranium and radiation-induced lung cancer and leukaemia. Br. J...Abou-Donia M. B. Depleted and natural uranium: chemistry and toxicological......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

398

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......contaminated accidentally with uranium. INTRODUCTION Depleted uranium (DU) can affect human health via chemical and radiation...B. Teratogenicity of depleted uranium aerosols: a review from...perspective. Environ. Health (2005) 4:17-35......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

399

SRP Scientific Meeting: Depleted Uranium  

Science Journals Connector (OSTI)

London, January 2002 The meeting was organised by the SRP to review current research and discuss the use, dispersion into the environment and radiological impact of depleted uranium (DU) by the UK and US in recent military conflicts. Brian Spratt chaired the morning session of the meeting and stressed the need to gauge the actual risks involved in using DU and to balance professional opinions with public mistrust of scientists and government bodies. He asked whether more could be done by the radiation protection profession to improve communication with the media, pressure groups and the public in general. Ron Brown, of the MOD Dstl Radiological Protection Services, gave a thorough overview of the origins and properties of DU, focusing on munitions, in the UK and abroad and public concerns arising from its use in the 1991 Gulf War. He gave a brief overview of past DU munitions studies by the UK and US governments and contrasted this with the lack of hard data used to back up claims made by pressure groups. He compared the known risks of DU with other battlefield risks, e.g. biological agents, chemical attacks and vaccines, and questioned whether peacetime dose limits should apply to soldiers on the battlefield. Barry Smith, of the British Geological Survey, spoke on DU transport, pathways and exposure routes focusing on groundwater as an important example in the Former Yugoslav Republic of Kosovo. He discussed the large amount of work that has already been done on natural uranium in groundwater, with particular emphasis on its mobility within the soil and rock profile being strongly dependent on precipitation and the local geochemical conditions. Therefore, generic risk assessments will not be sufficient in gauging risks to local populations after the introduction of DU into their environment; local geochemical conditions must be taken into account. However, experiments are required to fully appreciate the extent to which DU, particularly DU:Ti alloys used in munitions, disperses into the environment in a variety of soil types. Barry outlined recent computer modelling work investigating the time taken for DU to migrate from a buried munition to a borehole in three different scenarios. The modelling revealed times from 30 years to 5 ? 109 years depending on the local geochemical environment and the depth of the DU penetrator in the soil profile. This suggests the real possibility of borehole contamination within a human lifetime in wet conditions similar to those found in Kosovo. Nick Priest, of Middlesex University, discussed methods of biological monitoring for natural and depleted uranium. The preferred method of detection is by 24 h urine sampling, with measurement of the total mass or isotopic ratios of uranium using mass spectroscopy (ICPMS). This is because uranium is only deposited in new areas of bone growth, a slow process in healthy adults, the remainder is filtered by the kidneys and excreted in urine, giving a non-invasive and rapid sample collection method. Nick also described a rapid assessment technique to look for total uranium and DU in a sample, using a multi-collector ICPMS, specifically looking at the 235U:238U ratio with 236U as a tracer to determine the total mass of uranium present and its source. The MC-ICPMS method was applied in a BBC Scotland funded study of uptakes of uranium in three populations in the Balkans during March 2001. Variable levels of DU were found in each population. The age of the subject was found to influence the excretion of natural uranium and DU to the same degree, increasing age leading to increased excretion. Overall, the levels of DU were extremely small (tens of g), but DU was found to be present in each population investigated. The MC-ICPMS method is capable of detecting 1% DU in natural uranium and Nick intends to extend the study to include ground and drinking water samples and food in the same populations. Neil Stradling gave a talk on the contribution of the NRPB to the WHO report on DU published in April 2001. It addressed the biokinetics of inhaled uranium

David Kestell

2002-01-01T23:59:59.000Z

400

Surface Decontamination of System Components in Uranium Conversion Plant at KAERI  

SciTech Connect

A chemical decontamination process using nitric acid solution was selected as in-situ technology for recycle or release with authorization of a large amount of metallic waste including process system components such as tanks, piping, etc., which is generated by dismantling a retired uranium conversion plant at Korea Atomic Energy Research Institute (KAERI). The applicability of nitric acid solution for surface decontamination of metallic wastes contaminated with uranium compounds was evaluated through the basic research on the dissolution of UO2 and ammonium uranyl carbonate (AUC) powder. Decontamination performance was verified by using the specimens contaminated with such uranium compounds as UO2 and AUC taken from the uranium conversion plant. Dissolution rate of UO2 powder is notably enhanced by the addition of H2O2 as an oxidant even in the condition of a low concentration of nitric acid and low temperature compared with those in a nitric acid solution without H2O2. AUC powders dissolve easily in nitric acid solutions until the solution pH attains about 2.5 {approx} 3. Above that solution pH, however, the uranium concentration in the solution is lowered drastically by precipitation as a form of U3(NH3)4O9 . 5H2O. Decontamination performance tests for the specimens contaminated with UO2 and AUC were quite successful with the application of decontamination conditions obtained through the basic studies on the dissolution of UO2 and AUC powders.

Choi, W. K.; Kim, K. N.; Won, H. J.; Jung, C. H.; Oh, W. Z.

2003-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Corrosion of Uranium in Desert Soil, with Application to GCD Source Term M  

SciTech Connect

Uranium fragments from the Sandia Sled Track were studied as analogues for weapons components and depleted uranium buried at the Greater Confinement Disposal (GCD) site in Nevada. The Sled Track uranium fragments originated as weapons mockups and counterweights impacted on concrete and soil barriers, and experienced heating and fragmentation similar to processes thought to affect the Nuclear Weapons Accident Residues (NWAR) at GCD. Furthermore, the Sandia uranium was buried in unsaturated desert soils for 10 to 40 years, and has undergone weathering processes expected to affect the GCD wastes. Scanning electron microscopy, X-ray diffraction and microprobe analyses of the fragments show rapid alteration from metals to dominantly VI-valent oxy-hydroxides. Leaching studies of the samples give results consistent with published U-oxide dissolution rates, and suggest longer experimental periods (ca. 1 year) would be required to reach equilibrium solution concentrations. Thermochemical modeling with the EQ3/6 code indicates that the uranium concentrations in solutions saturated with becquerelite could increase as the pore waters evaporate, due to changes in carbonate equilibria and increased ionic strength.

ANDERSON, HOWARD L.; BACA, JULIANNE; KRUMHANSL, JAMES L.; STOCKMAN, HARLAN W.; THOMPSON, MOLLIE E.

1999-09-01T23:59:59.000Z

402

Mined Land Reclamation on DOE's Uranium Lease Tracts, Southwestern...  

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

Mined Land Reclamation on DOE's Uranium Lease Tracts, Southwestern Colorado Mined Land Reclamation on DOE's Uranium Lease Tracts, Southwestern Colorado Mined Land Reclamation on...

403

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Most recently, LM visited 84 defense-related legacy uranium mine sites located within 11 uranium mining districts in 6 western states. At these sites, photographs and global...

404

Secretarial Determination for the Sale or Transfer of Uranium...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Uranium.pdf More Documents & Publications Secretarial Determination Pursuant to USEC Privatization Act for the Sale or Transfer of Low-Enriched Uranium Secretarial...

405

Secretarial Determination of No Adverse Material Impact for Uranium...  

Energy Savers (EERE)

5-15-14.pdf More Documents & Publications Excess Uranium Inventory Management Plan 2008 2014 Review of the Potential Impact of DOE Excess Uranium Inventory On the...

406

Editorial - Depleted Uranium: A Problem of Perception rather than Reality  

Science Journals Connector (OSTI)

......Radiation Protection Dosimetry Editorial Editorial - Depleted Uranium: A Problem of Perception rather than Reality R. L. Kathren Depleted uranium: a problem of perception rather than reality......

R. L. Kathren

2001-05-01T23:59:59.000Z

407

Modeling of Depleted Uranium Transport in Subsurface Systems  

Science Journals Connector (OSTI)

Groundwater and soil contamination with depleted uranium (DU) isan important public concern because ... four extremecases of climate and existing conditions of uranium penetrator fragments. The simulations demons...

J. Paul Chen; Sotira Yiacoumi

2002-10-01T23:59:59.000Z

408

Microbial Reduction of Uranium under Iron- and Sulfate-reducing...  

NLE Websites -- All DOE Office Websites (Extended Search)

Uranium under Iron- and Sulfate-reducing Conditions: Effect of Amended Goethite on Microbial Community Microbial Reduction of Uranium under Iron- and Sulfate-reducing Conditions:...

409

Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex  

SciTech Connect

The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

Veinot, K. G.

2009-07-22T23:59:59.000Z

410

A top-down assessment of energy, water and land use in uranium mining, milling, and refining  

SciTech Connect

Land, water and energy use are key measures of the sustainability of uranium production into the future. As the most attractive, accessible deposits are mined out, future discoveries may prove to be significantly, perhaps unsustainably, more intensive consumers of environmental resources. A number of previous attempts have been made to provide empirical relationships connecting these environmental impact metrics to process variables such as stripping ratio and ore grade. These earlier attempts were often constrained by a lack of real world data and perform poorly when compared against data from modern operations. This paper conditions new empirical models of energy, water and land use in uranium mining, milling, and refining on contemporary data reported by operating mines. It shows that, at present, direct energy use from uranium production represents less than 1% of the electrical energy produced by the once-through fuel cycle. Projections of future energy intensity from uranium production are also possible by coupling the empirical models with estimates of uranium crustal abundance, characteristics of new discoveries, and demand. The projections show that even for the most pessimistic of scenarios considered, by 2100, the direct energy use from uranium production represents less than 3% of the electrical energy produced by the contemporary once-through fuel cycle.

E. Schneider; B. Carlsen; E. Tavrides; C. van der Hoeven; U. Phathanapirom

2013-11-01T23:59:59.000Z

411

Summary - Uranium233 Downblending and Disposition Project  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Product Product EM wa in Buil to extr from 23 downb mitigat concer dispos downb WIPP condu the "ba allowin assess techno The as Techn Techn * An * C (T * Pr * O The Ele Site: O roject: 2 P Report Date: S ited States 233 Ura Why DOE t Packaging Syste as directed to t ding 3019 at O ract 229 Th (an is 33 U. The missi blend the inven te security and rns and prepar sal. The projec blended materia or the Nevada cted to coincid ack-end" of the ng observation sment team to ology maturity p What th ssessment team ology Element ology Readine nalytical Labor oncentration p TRL=4) roduct Packag ffgas Treatmen To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Oak Ridge/OR 233 Uranium Do Project September 20 Departmen anium D E-EM Did This em and Interfaces ake ownership Oak Ridge that sotope used in

412

Hydrogen production by steam-gasification of carbonaceous materials using concentrated solar energy V. Reactor modeling, optimization, and scale-up  

Science Journals Connector (OSTI)

A chemical reactor for the steam-gasification of carbonaceous particles (e.g. coal, coke) is considered for using concentrated solar radiation as the energy source of high-temperature process heat. A two-phase reactor model that couples radiative, convective, and conductive heat transfer to the chemical kinetics is applied to optimize the reactor geometrical configuration and operational parameters (feedstock's initial particle size, feeding rates, and solar power input) for maximum reaction extent and solar-to-chemical energy conversion efficiency of a 5kW prototype reactor and its scale-up to 300kW. For the 300kW reactor, complete reaction extent is predicted for an initial feedstock particle size up to 35?m at residence times of less than 10s and peak temperatures of 1818K, yielding high-quality syngas with a calorific content that has been solar-upgraded by 19% over that of the petcoke gasified.

A. Z'Graggen; A. Steinfeld

2008-01-01T23:59:59.000Z

413

HIGH-DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE  

NLE Websites -- All DOE Office Websites (Extended Search)

DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DENSITY CONCRETE WITH CERAMIC AGGREGATE BASED ON DEPLETED URANIUM DIOXIDE S.G. Ermichev, V.I. Shapovalov, N.V.Sviridov (RFNC-VNIIEF, Sarov, Russia) V.K. Orlov, V.M. Sergeev, A. G. Semyenov, A.M. Visik, A.A. Maslov, A. V. Demin, D.D. Petrov, V.V. Noskov, V. I. Sorokin, O. I. Uferov (VNIINM, Moscow, Russia) L. Dole (ORNL, Oak Ridge, USA) Abstract - Russia is researching the production and testing of concretes with ceramic aggregate based on depleted uranium dioxide (UO 2 ). These DU concretes are to be used as structural and radiation-shielded material for casks for A-plant spent nuclear fuel transportation and storage. This paper presents the results of studies aimed at selection of ceramics and concrete composition, justification of their production technology, investigation of mechanical properties, and chemical stability.

414

MOBILE SYSTEMS FOR DILUTION OF HIGHLY ENRICHED URANIUM AND URANIUM CONTAINING COMPONENTS  

SciTech Connect

A mobile melt-dilute (MMD) module for the treatment of aluminum research reactor spent fuel is being developed. The process utilizes a closed system approach to retain fission products/gases inside a sealed canister after treatment. The MMD process melts and dilutes spent fuel with depleted uranium to obtain a fissile fraction of less than 0.2. The final ingot is solidified inside the sealed canister and can be stored safely either wet or dry until final disposition or reprocessing. The MMD module can be staged at or near the research reactor fuel storage sites to facilitate the melt-dilute treatment of the spent fuel into a stable non-proliferable form.

Adams, T

2007-05-02T23:59:59.000Z

415

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

...poses virtually no cancer risk. Moreover, Danesi's...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...

Richard Stone

2002-09-13T23:59:59.000Z

416

Reoxidation of Bioreduced Uranium under Reducing Conditions  

E-Print Network (OSTI)

concentrations and formation of very stable uranyl carbonatecomplexes in sediments and groundwaters with neutral to alkaline pH, where uranyl carbonates are most stable(IV). Dissolved oxygen, nitrate, and deni- trification products have been shown to oxidize U(IV) (10- 12

Hazen, Terry

417

IPNS enriched uranium booster target  

SciTech Connect

Since startup in 1981, IPNS has operated on a fully depleted /sup 238/U target. With the booster as in the present system, high energy protons accelerated to 450 MeV by the Rapid Cycling Synchrotron are directed at the target and by mechanisms of spallation and fission of the uranium, produce fast neutrons. The neutrons from the target pass into adjacent moderator where they slow down to energies useful for spectroscopy. The target cooling systems and monitoring systems have operated very reliably and safely during this period. To provide higher neutron intensity, we have developed plans for an enriched uranium (booster) target. HETC-VIM calculations indicate that the target will produce approx.90 kW of heat, with a nominal x5 gain (k/sub eff/ = 0.80). The neutron beam intensity gain will be a factor of approx.3. Thermal-hydraulic and heat transport calculations indicate that approx.1/2 in. thick /sup 235/U discs are subject to about the same temperatures as the present /sup 238/U 1 in. thick discs. The coolant will be light demineralized water (H/sub 2/O) and the coolant flow rate must be doubled. The broadening of the fast neutron pulse width should not seriously affect the neutron scattering experiments. Delayed neutrons will appear at a level about 3% of the total (currently approx.0.5%). This may affect backgrounds in some experiments, so that we are assessing measures to control and correct for this (e.g., beam tube choppers). Safety analyses and neutronic calculations are nearing completion. Construction of the /sup 235/U discs at the ORNL Y-12 facility is scheduled to begin late 1985. The completion of the booster target and operation are scheduled for late 1986. No enriched uranium target assembly operating at the projected power level now exists in the world. This effort thus represents an important technological experiment as well as being a ''flux enhancer''.

Schulke, A.W. Jr.

1985-01-01T23:59:59.000Z

418

Review of the NURE Assessment of the U.S. Gulf Coast Uranium Province  

SciTech Connect

Historic exploration and development were used to evaluate the reliability of domestic uranium reserves and potential resources estimated by the U.S. Department of Energy national uranium resource evaluation (NURE) program in the U.S. Gulf Coast Uranium Province. NURE estimated 87 million pounds of reserves in the $30/lb U{sub 3}O{sub 8} cost category in the Coast Plain uranium resource region, most in the Gulf Coast Uranium Province. Since NURE, 40 million pounds of reserves have been mined, and 38 million pounds are estimated to remain in place as of 2012, accounting for all but 9 million pounds of U{sub 3}O{sub 8} in the reserve or production categories in the NURE estimate. Considering the complexities and uncertainties of the analysis, this study indicates that the NURE reserve estimates for the province were accurate. An unconditional potential resource of 1.4 billion pounds of U{sub 3}O{sub 8}, 600 million pounds of U{sub 3}O{sub 8} in the forward cost category of $30/lb U{sub 3}O{sub 8} (1980 prices), was estimated in 106 favorable areas by the NURE program in the province. Removing potential resources from the non-productive Houston embayment, and those reserves estimated below historic and current mining depths reduces the unconditional potential resource 33% to about 930 million pounds of U{sub 3}O{sub 8}, and that in the $30/lb cost category 34% to 399 million pounds of U{sub 3}O{sub 8}. Based on production records and reserve estimates tabulated for the region, most of the production since 1980 is likely from the reserves identified by NURE. The potential resource predicted by NURE has not been developed, likely due to a variety of factors related to the low uranium prices that have prevailed since 1980.

Hall, Susan M., E-mail: SusanHall@usgs.gov [Central Energy Resources Science Center, U.S. Geological Survey (United States)

2013-09-15T23:59:59.000Z

419

Depleted-Uranium Weapons the Whys and Wherefores  

E-Print Network (OSTI)

The only military application in which present-day depleted-uranium (DU) alloys out-perform tungsten alloys is long-rod penetration into a main battle-tank's armor. However, this advantage is only on the order of 10% and disappearing when the comparison is made in terms of actual lethality of complete anti-tank systems instead of laboratory-type steel penetration capability. Therefore, new micro- and nano-engineered tungsten alloys may soon out-perform existing DU alloys, enabling the production of tungsten munition which will be better than uranium munition, and whose overall life-cycle cost will be less due to the absence of the problems related to the radioactivity of uranium. The reasons why DU weapons have been introduced and used are analysed from the perspective that their radioactivity must have played an important role in the decision making process. It is found that DU weapons belong to the diffuse category of low-radiological-impact nuclear weapons to which emerging types of low-yield, i.e., fourth...

Gsponer, A

2003-01-01T23:59:59.000Z

420

Early Breakthrough of Molybdenum and Uranium in a Permeable Reactive Barrier  

Science Journals Connector (OSTI)

S.M. Stoller Corporation, 2597 B 3/4 Road, Grand Junction, Colorado 81503, U.S. Environmental Protection Agency Region 8, Federal Facilities Program, Office of Environmental Protection and Remediation, 999 18th Street, Suite 300, Denver, Colorado 80202, and Cotter Corporation, 7800 East Dorado Place, Englewood, Colorado 80111 ... A permeable reactive barrier (PRB) using zerovalent iron (ZVI) was installed at a site near Caon City, CO, to treat molybdenum (Mo) and uranium (U) in groundwater. ... Uranium (U) mill tailings in northern Saskatchewan, Canada, contain elevated concentrations of molybdenum (Mo). ...

Stan J. Morrison; Paul S. Mushovic; Preston L. Niesen

2006-02-14T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Overview of Depleted Uranium Hexafluoride Management Program  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE's DUF DOE's DUF 6 Cylinder Inventory a Location Number of Cylinders DUF 6 (MT) b Paducah, Kentucky 36,910 450,000 Portsmouth, Ohio 16,041 198,000 Oak Ridge (ETTP), Tennessee 4,683 56,000 Total 57,634 704,000 a The DOE inventory includes DUF 6 generated by the government, as well as DUF 6 transferred from U.S. Enrichment Corporation pursuant to two memoranda of agreement. b A metric ton (MT) is equal to 1,000 kilograms, or 2,200 pounds. Overview of Depleted Uranium Hexafluoride Management Program Over the last four decades, large quantities of uranium were processed by gaseous diffusion to produce enriched uranium for U.S. national defense and civilian purposes. The gaseous diffusion process uses uranium in the form of uranium hexafluoride (UF 6 ), primarily because UF 6 can conveniently be used in

422

National Uranium Resource Evaluation, Tonopah quadrangle, Nevada  

SciTech Connect

The Tonopah Quadrangle, Nevada, was evaluated using National Uranium Resource Evaluation criteria to identify and delineate areas favorable for uranium deposits. Investigations included reconnaissance and detailed surface geologic and radiometric studies, geochemical sampling and evaluation, analysis and ground-truth followup of aerial radiometric and hydrogeochemical and stream-sediment reconnaissance data, and subsurface data evaluation. The results of these investigations indicate environments favorable for hydroallogenic uranium deposits in Miocene lacustrine sediments of the Big Smoky Valley west of Tonopah. The northern portion of the Toquima granitic pluton is favorable for authigenic uranium deposits. Environments considered unfavorable for uranium deposits include Quaternary sediments; intermediate and mafic volcanic and metavolcanic rocks; Mesozoic, Paleozoic, and Precambrian sedimentary and metasedimentary rocks; those plutonic rocks not included within favorable areas; and those felsic volcanic rocks not within the Northumberland and Mount Jefferson calderas.

Hurley, B W; Parker, D P

1982-04-01T23:59:59.000Z

423

Radionuclide Concentrations in Terrestrial Vegetation and Soil Samples On and Around the Hanford Site, 1971 Through 2008  

SciTech Connect

Environmental monitoring is conducted on the U.S. Department of Energy (DOE) Hanford Site to comply with DOE Orders and federal and state regulations. Major objectives of the monitoring are to characterize contaminant levels in the environment and to determine site contributions to the contaminant inventory. This report focuses on surface soil and perennial vegetation samples collected between 1971 and 2008 as part of the Pacific Northwest National Laboratory Surface Environmental Surveillance Project performed under contract to DOE. Areas sampled under this program are located on the Hanford Site but outside facility boundaries and on public lands surrounding the Hanford Site. Additional samples were collected during the past 8 years under DOE projects that evaluated parcels of land for radiological release. These data were included because the same sampling methodology and analytical laboratory were used for the projects. The spatial and temporal trends of six radionuclides collected over a 38-year period were evaluated. The radionuclides----cobalt-60, cesium-137, strontium-90, plutonium-238, plutonium-239/240, and uranium (reported either as uranium-238 or total uranium)----were selected because they persist in the environment and are still being monitored routinely and reported in Hanford Site environmental reports. All these radionuclides were associated with plutonium production and waste management of activities occurring on the site. Other sources include fallout from atmospheric testing of nuclear weapons, which ended in 1980, and the Chernobyl explosion in 1986. Uranium is also a natural component of the soil. This assessment of soil and vegetation data provides important information on the distribution of radionuclides in areas adjacent to industrial areas, established perimeter locations and buffer areas, and more offsite nearby and distant locations. The concentrations reflect a tendency for detection of some radionuclides close to where they were utilized onsite, but as one moves to unindustrialized areas on the site, surrounding buffer areas and perimeter location into the more distant sites, concentrations of these radionuclides approach background and cannot be distinguished from fallout activity. More importantly, concentrations in soil and vegetation samples did not exceed environmental benchmark concentrations, and associated exposure to human and ecological receptors were well below levels that are demonstratively hazardous to human health and the environment.

Simmons, Mary Ann; Poston, Ted M.; Fritz, Brad G.; Bisping, Lynn E.

2011-07-29T23:59:59.000Z

424

Fission product retention in newly discovered organic-rich natural fission reactors at Oklo and Bangombe, Gabon  

SciTech Connect

The discovery of naturally occurring fission reactors in the rock strata of the Paleoproterozoic Francevillian Basin in the Republic of Gabon in equatorial West Africa led to several programs to define migration and/or retention of uranium and fissiogenic isotopes from/in the natural reactor zones. Although much understanding has been gained, new insight is needed regarding the chemical and physical parameters that control movement and retention of fission products over almost two billion years from/in the natural reactors. Seventeen known natural fission reactors sustained criticality for 0.1 to 1 million years in hydrothermally altered sedimentary rocks 1968 +/- 50 million years ago. These natural nuclear reactors attained criticality because of high concentrations of uranium in small pockets in uranium ores, the lack of neutron poisons, and because at the time they reached criticality, the abundance of [sup 235]U was five times greater than it is today. Water acted as a moderator, and temperature in the natural reactors was between 160 and 360[degrees]C. Both the uranium-rich pockets and the uranium ore bodies in which these pockets are located were formed when aqueous solutions moving through highly fractured zones in the Francevillian sedimentary rocks met organic-rich sediments. This resulted in the reduction of U(VI) in the dissolved uranyl ions to U(IV), causing the precipitation of pitchblende and uraninite. It has been proposed that between 2.2 and 1.9 billion years ago, the earth's atmosphere experienced a remarkable temporary rise in O[sub 2] content; this event may account for the uranium-bearing, oxidizing aqueous solutions in the Francevillian rocks.

Nagy, B.; Rigali, M.J. (Univ. of Arizona, Tucson (United States))

1993-01-01T23:59:59.000Z

425

Determination of Depleted Uranium in Environmental Bio-monitor Samples and Soil from Target sites in Western Balkan Region  

SciTech Connect

Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper, we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses, lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP-MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2-755.43 Bq/Kg. We have determined {sup 235}U/{sup 238}U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.002097-0.002380. TIMS measurement confirms presence of DU in some samples. However, we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

Sahoo, Sarata K.; Enomoto, Hiroko; Tokonami, Shinji; Ishikawa, Tetsuo [National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage-ku, Chiba 263-8555 (Japan); Ujic, Predrag; Celikovic, Igor; Zunic, Zora S. [Institute of Nuclear Sciences, Vinca, Mike Petrovica Alasa 12-14, 11000 Belgrade (Serbia)

2008-08-07T23:59:59.000Z

426

Determination of Depleted Uranium in Environmental Bio?monitor Samples and Soil from Target sites in Western Balkan Region  

Science Journals Connector (OSTI)

Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP?MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2755.43 Bq/Kg. We have determined 235 U / 238 U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.0020970.002380. TIMS measurement confirms presence of DU in some samples. However we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

Sarata K. Sahoo; Hiroko Enomoto; Shinji Tokonami; Tetsuo Ishikawa; Predrag Uji?; Igor ?elikovi?; Zora S. uni?

2008-01-01T23:59:59.000Z

427

Uranium(VI) extraction by TBP in the presence of HDBP  

SciTech Connect

The influence of di-n-butyl phosphoric acid (HDBP) upon extraction of uranium(VI) by tri-n-butyl phosphate (TBP) from 0.5--3.0 M nitric acid solutions has been studied. It has been shown that the uranium(VI) distribution coefficient D{sub U} for extraction by 1.1 M TBP in tri-decane or xylene is increased when HDBP is present in the organic phase. For iso-molar solutions of (TBP + HDBP) with a total concentration of 0.36 M, and Uranium(VI) aqueous concentration up to 10--20 g/l, a maximum value of D{sub U} is observed when TBP/HDBP = 1; for higher U(VI) concentration the maximum gradually disappears, with D{sub U} growing monotonically with the HDBP content in the organic phase. Uranium(VI) absorption spectra for 1.1 M TBP in tri-decane or xylene, containing HDBP, provide evidence for the formation of compounds, of which composition is intermediate between uranyl nitrate--TBP disolvate and the U(VI)--HDBP complex. It is proposed that these intermediate compounds are UO{sub 2}(NO{sub 3}){sub 2}HDBP.TBP and UO{sub 2}(NO{sub 3}){sub 2}(HDBP){sub 2}.

Fedorov, Yu.S.; Zilberman, B.Ya.; Kulikov, S.M.; Blazheva, I.V.; Mishin, E.N. [V.G. Khlopin Radium Inst., Saint-Petersburg (Russian Federation); Wallwork, A.L.; Denniss, I.S.; May, I. [British Nuclear Fuels plc, Sellafield (United Kingdom); Hill, N.J. [British Nuclear Fuels plc, Risley (United Kingdom)

1999-03-01T23:59:59.000Z

428

Summary history of domestic uranium procurement under US Atomic Energy Commission contracts. Final report  

SciTech Connect

During the period 1947 through 1970, the Atomic Energy Commission (AEC) fostered the rapid development and expansion of the domestic uranium mining and milling industry by providing a market for uranium. Some thirty-two mills were constructed during that period to produce U/sub 3/O/sub 8/ concentrates for sale to the AEC. In addition, there were various pilot plants, concentrators, upgraders, heap leach, and solution mining facilities that operated during the period. The purpose of this report is to compile a short narrative history of the AEC's uranium concentrate procurement program and to describe briefly each of the operations that produced uranium for sale to the AEC. Contractual arrangements are described and data are given on quantities of U/sub 3/O/sub 8/ purchased and prices paid. Similar data are included for V/sub 2/O/sub 5/, where applicable. Mill and other plant operating data were also compiled from old AEC records. These latter data were provided by the companies, as a contractual requirement, during the period of operation under AEC contracts. Additionally, an effort was made to determine the present status of each facility by reference to other recently published reports. No sites were visited nor were the individual reports reviewed by the companies, many of which no longer exist. The authors relied almost entirely on published information for descriptions of facilities and milling processes utilized.

Albrethsen, H. Jr.; McGinley, F.E.

1982-09-01T23:59:59.000Z

429

Removal of uranium from uranium-contaminated soils -- Phase 1: Bench-scale testing. Uranium in Soils Integrated Demonstration  

SciTech Connect

To address the management of uranium-contaminated soils at Fernald and other DOE sites, the DOE Office of Technology Development formed the Uranium in Soils Integrated Demonstration (USID) program. The USID has five major tasks. These include the development and demonstration of technologies that are able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from the soil, (3) treat the soil and dispose of any waste, (4) establish performance assessments, and (5) meet necessary state and federal regulations. This report deals with soil decontamination or removal of uranium from contaminated soils. The report was compiled by the USID task group that addresses soil decontamination; includes data from projects under the management of four DOE facilities [Argonne National Laboratory (ANL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), and the Savannah River Plant (SRP)]; and consists of four separate reports written by staff at these facilities. The fundamental goal of the soil decontamination task group has been the selective extraction/leaching or removal of uranium from soil faster, cheaper, and safer than current conventional technologies. The objective is to selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics or generating waste forms that are difficult to manage and/or dispose of. Emphasis in research was placed more strongly on chemical extraction techniques than physical extraction techniques.

Francis, C. W.

1993-09-01T23:59:59.000Z

430

Reassessment of individual dosimetry of long-lived alpha radionuclides of uranium miners through experimental determination of urinary excretion of uranium  

Science Journals Connector (OSTI)

......iranium in urine of uranium miners as a tool for...230Th in excreta of uranium mill crushermen. Health Phys. (1983) 45...Measurement of daily urinary uranium excretion in German...potential intakes of depleted uranium(DU). Sci......

I. Maltov; V. Beckov; L. Tomsek; M. Slezkov-Marusiakov; J. Hulka

2013-04-01T23:59:59.000Z

431

FAQ 3-What are the common forms of uranium?  

NLE Websites -- All DOE Office Websites (Extended Search)

are the common forms of uranium? are the common forms of uranium? What are the common forms of uranium? Uranium can take many chemical forms. In nature, uranium is generally found as an oxide, such as in the olive-green-colored mineral pitchblende. Uranium oxide is also the chemical form most often used for nuclear fuel. Uranium-fluorine compounds are also common in uranium processing, with uranium hexafluoride (UF6) and uranium tetrafluoride (UF4) being the two most common. In its pure form, uranium is a silver-colored metal. The most common forms of uranium oxide are U3O8 and UO2. Both oxide forms have low solubility in water and are relatively stable over a wide range of environmental conditions. Triuranium octaoxide (U3O8) is the most stable form of uranium and is the form most commonly found in nature. Uranium dioxide (UO2) is the form in which uranium is most commonly used as a nuclear reactor fuel. At ambient temperatures, UO2 will gradually convert to U3O8. Because of their stability, uranium oxides are generally considered the preferred chemical form for storage or disposal.

432

Estimated dose to man from uranium milling via the terrestrial food-chain pathway  

SciTech Connect

One of the major pathways of radiological exposure to man from uranium milling operations is through the terrestrial food chain. Studies by various investigators have shown the extent of uptake and distribution of U-238, U-234, Th-230, Ra-226, Pb-210, and Po-210 in plants and animals. These long-lived natural radioisotopes, all nuclides of the uranium decay series, are found in concentrated amounts in uranium mill tailings. Data from these investigations are used to estimate the dose to man from consumption of beef and milk contaminated by the tailings. This dose estimate from this technologically enhanced source is compared with that from average normal dietary intake of these radionuclides from natural sources.

Rayno, D.R.

1982-01-01T23:59:59.000Z

433

Measuring Aerosols Generated Inside Armoured Vehicles Perforated by Depleted Uranium Ammunition  

SciTech Connect

In response to questions raised after the Gulf War about the health significance of exposure to depleted uranium (DU), a study was initiated to provide an improved scientific basis for assessment of possible health effects of soldiers in vehicles struck by these munitions. As part of this experimental study, a series of DU penetrators were fired at an Abrams tank and a Bradley fighting vehicle, and the aerosols generated by vehicle perforation were collected and characterized. The aerosol sampling system designed for these tests consisted of filter cassettes, cascade impactors, a five-stage cyclone, and a moving filter. Aerosols collected were analyzed for uranium concentration and particle size distribution as a function of time. The aerosol samples were also analyzed for uranium oxide phases, particle morphology, and in vitro solubility. These data will provide input for use in future prospective and retrospective dose and health risk assessments of DU aerosols.

Parkhurst, MaryAnn

2003-01-01T23:59:59.000Z

434

Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF4)  

NLE Websites -- All DOE Office Websites (Extended Search)

6 6 Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF 4 ) Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering activities, contact: Director, Environmental Assessment Division Argonne National Laboratory Argonne, Illinois 60439-4832

435

Depleted Uranium: Exposure and Possible Health Effects  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a by-product of the enrichment process of 235U used for fission in nuclear reactors and nuclear weapons. It has both civilian and military applications. The military use of DU is of defensive as well as of offensive nature, being mainly employed as armor-piercing ammunition. So far, the usage of ammunitions containing DU has been officially confirmed in four military conflicts: Iraq (1991), Bosnia (1994), Kosovo (1999), and again Iraq (2003). During their deployment in the military actions, most penetrators are thought to have missed their intended targets. Therefore, a substantial amount of DU is still present in the environment and may act as a source of contamination for the environment and the population. The possible effects of this radioactive and chemically toxic material have attracted particular notice. To evaluate these consequences, it is important to have accurate methods to assess the exposure to DU in both environmental and biological samples. This article is therefore intended to point out the problematic nature of the experimental techniques and of the analytical methods so far used to quantify the exposure to DU in the light of possible health effects of DU.

U. Oeh

2011-01-01T23:59:59.000Z

436

Prospects of Using Reprocessed Uranium in CANDU Reactors, in the U.S. GNEP Program  

SciTech Connect

Current Global Nuclear Energy Partnership (GNEP) plans envision reprocessing spent fuel (SF) with view to minimizing high-level waste (HLW) repository use and recovering actinides (U, Np, Pu, Am, and Cm) for transmutation in reactors as fuel and targets. The reprocessed uranium (RU), however, is to be disposed of. This paper presents a limited-scope analysis of possible reuse of RU in CANDU (Canada Deuterium Uranium) Reactors, within the context of the US GNEP program. Other papers on this topic submitted to this conference discuss the possibility of RU reuse in light-water reactors (LWRs) (with enrichment) and offer an independent economic analysis of RU reuse. A representative RU uranium 'vector', from reprocessed spent LWR fuel, comprises 98.538 wt% 238U, 0.46 wt% {sup 236}U, 0.986 wt% {sup 235}U, and 0.006 wt% {sup 234}U. After multiple recyclings, the concentration of {sup 234}U can approach 0.02 wt%. The presence of {sup 234}U and {sup 236}U in RU reduces the reactivity and fuel lifetime (exit burnup), which is particularly an issue in LWRs. While in PWR analyses, the burnup penalty caused by the concentration of {sup 236}U in RU needs to be offset by additional {sup 235}U enrichment in the amount of {approx}25% to 30% of the weight percentage of the {sup 236}U; however, the effect in CANDU is much smaller. Furthermore, since the {sup 235}U content in RU exceeds that of natural uranium, CANDU offers the advantageous option of uranium recycling without reenrichment. The exit burnup of CANDU RU-derived fuel is considerably larger than that for natural uranium-fueled scenario, despite the presence of {sup 234}U and {sup 236}U.

Ellis, Ronald James [ORNL

2007-01-01T23:59:59.000Z

437

Uranium mill tailings neutralization: contaminant complexation and tailings leaching studies  

SciTech Connect

Laboratory experiments were performed to compare the effectiveness of limestone (CaCO/sub 3/) and hydrated lime (Ca(OH)/sub 2/) for improving waste water quality through the neutralization of acidic uranium mill tailings liquor. The experiments were designed to also assess the effects of three proposed mechanisms - carbonate complexation, elevated pH, and colloidal particle adsorption - on the solubility of toxic contaminants found in a typical uranium mill waste solution. Of special interest were the effects each of these possible mechanisms had on the solution concentrations of trace metals such as Cd, Co, Mo, Zn, and U after neutralization. Results indicated that the neutralization of acidic tailings to a pH of 7.3 using hydrated lime provided the highest overall waste water quality. Both the presence of a carbonate source or elevating solution pH beyond pH = 7.3 resulted in a lowering of previously achieved water quality, while adsorption of contaminants onto colloidal particles was not found to affect the solution concentration of any constituent investigated. 24 refs., 8 figs., 19 tabs.

Opitz, B.E.; Dodson, M.E.; Serne, R.J.

1985-05-01T23:59:59.000Z

438

FIREPLUME model for plume dispersion from fires: Application to uranium hexafluoride cylinder fires  

SciTech Connect

This report provides basic documentation of the FIREPLUME model and discusses its application to the prediction of health impacts resulting from releases of uranium hexafluoride (UF{sub 6}) in fires. The model application outlined in this report was conducted for the Draft Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted UF{sub 6}. The FIREPLUME model is an advanced stochastic model for atmospheric plume dispersion that predicts the downwind consequences of a release of toxic materials from an explosion or a fire. The model is based on the nonbuoyant atmospheric dispersion model MCLDM (Monte Carlo Lagrangian Dispersion Model), which has been shown to be consistent with available laboratory and field data. The inclusion of buoyancy and the addition of a postprocessor to evaluate time-varying concentrations lead to the current model. The FIREPLUME model, as applied to fire-related UF{sub 6} cylinder releases, accounts for three phases of release and dispersion. The first phase of release involves the hydraulic rupture of the cylinder due to heating of the UF{sub 6} in the fire. The second phase involves the emission of material into the burning fire, and the third phase involves the emission of material after the fire has died during the cool-down period. The model predicts the downwind concentration of the material as a function of time at any point downwind at or above the ground. All together, five fire-related release scenarios are examined in this report. For each scenario, downwind concentrations of the UF{sub 6} reaction products, uranyl fluoride and hydrogen fluoride, are provided for two meteorological conditions: (1) D stability with a 4-m/s wind speed, and (2) F stability with a 1-m/s wind speed.

Brown, D.F.; Dunn, W.E. [Univ. of Illinois, Champaign-Urbana, IL (United States). Dept. of Mechanical Engineering; Policastro, A.J.; Maloney, D. [Argonne National Lab., IL (United States)

1997-06-01T23:59:59.000Z

439

Bayesian Prediction of Mean Indoor Radon Concentrations for Minnesota Counties  

E-Print Network (OSTI)

Uranium Resource Evaluation (NURE). That analysis, as wellas part of the National Uranium Resource Evaluation (NURE).The NURE survey generated estimates of surficial uranium

Price, P.N.

2011-01-01T23:59:59.000Z

440

Bacterial Community Succession During in situ Uranium Bioremediation: Spatial Similarities Along Controlled Flow Paths  

E-Print Network (OSTI)

problem, and the use of depleted uranium and other heavyenvironmental hazard. Depleted uranium is weakly radioactiveMB. (2004). Depleted and natural uranium: chemistry and

Hwang, Chiachi

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium concentrate production" from the National Library of EnergyBeta (NLEBeta).
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441

Appendix D Surface Water and Ground Water Time-Concentration Plots,  

Office of Legacy Management (LM)

Surface Water and Ground Water Time-Concentration Plots, Surface Water and Ground Water Time-Concentration Plots, Stream Discharge Measurements, Ground Water Level Data, and Ground Water Well Hydrographs This page intentionally left blank Contents Section .................................................................................. Surface Water Time-Concentration Plots D1.O ............................................................................................... Stream Discharge Measurements D2.0 ............................................................. Ground Water Time-Concentration Plots for Uranium D3.0 .......................................................................................................... Ground Water Level Data D4.0 ..............................................................................................

442

Synthesis of uranium nitride and uranium carbide powder by carbothermic reduction  

SciTech Connect

Uranium nitride and uranium carbide are being considered as high burnup fuels in next generation nuclear reactors and accelerated driven systems for the transmutation of nuclear waste. The same