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1

Uranium Lease Tracts Location Map | Department of Energy  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Uranium Lease Tracts Location Map Uranium Lease Tracts Location Map Uranium Lease Tracts...

2

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

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

Administration Other Agencies You are here Home Mined Land Reclamation on DOE's Uranium Lease Tracts, Southwestern Colorado Mined Land Reclamation on DOE's Uranium Lease...

3

DOE Uranium Leasing Program - Lease Tract Metrics  

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

Uranium Leasing Program -- Lease Tract Metrics Uranium Leasing Program -- Lease Tract Metrics Lease Tract Lessee Lease Date Bid (%) Reclamation Bond a Total Acres Acres Excluded b Comment C-JD-5 Gold Eagle Mining, Inc. 04/30/08 12.00 37,000 150.71 C-JD-5A Golden Eagle Uranium, LLC 06/27/08 20.10 5,000 24.54 C-JD-6 Cotter Corporation 04/30/08 14.20 19,000 530.08 C-JD-7 c Cotter Corporation 04/30/08 27.30 1,206,000 493.01 C-JD-8 Cotter Corporation 04/30/08 36.20 4,000 954.62 C-JD-8A No bids received - remains inactive N/A N/A N/A 77.91 C-JD-9 Cotter Corporation 04/30/08 24.30 72,000 1,036.50 C-SR-10 Golden Eagle Uranium, LLC 06/27/08 13.10 5,000 637.64 C-SR-11 Cotter Corporation 04/30/08 11.67 43,000 1,303.22 200.25 Summit Canyon area excluded from lease tract C-SR-11A Golden Eagle Uranium, LLC 06/27/08 14.30 5,000 1,296.81 C-SR-12 Colorado Plateau Partners 06/27/08

4

Uranium Lease Tracts Location Map  

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

16. 16. W. R.17 W. R.18 W. R.17 W. OUTLAW MESA MAVERICK CANYON CALAMITY MESA D O LO R E S MESA COUN TY MONT ROSE COUN TY SINBAD VALLEY SAN JUAN COUN TY MONT ROSE COUN TY PARADOX P A R A D O X V A L L E Y R I V E R ATKINSON MESA URAVAN CLUB MESA BEDROCK DOLORES RIVER S A N M I G U E L R I V E R COLO RAD O UTAH R.26 W. R.19 W. R. 26 E. R. 20 W. R. 19 W. R. 18 W. SAN MIGU EL COUN TY SAN JUAN COUN TY 141 SLICK ROCK D IS A P P O IN T M E N T V A L L E Y BIG GYPSUM VALLEY DRY CREEK BASIN MONT ROSE COUN TY SAN MIGU EL COUN TY WILD STEER MESA R.17 W. DOLORES RIVER T. 25 S. T. 26 S. T. 27 S. T. 28 S. T. 29 S. T. 30 S. T. 31 S. T. 32 S. T. 48 N. T. 47 N. T. 46 N. T. 45 N. T. 44 N. T. 50 N. T. 49 N. COLO RAD O UTAH T. 43 N. 141 MONOGRAM MESA 14 1 GRAN D COUN TY R.16 W. NATURITA TO GATEWAY TO La SAL TO DOVE CREEK 141 90 NUCLA EGNAR 97 P A R A D O X V A L L E Y R.20 W. T. 51 N. 9 16 8 11 13 18 14(1) 11A 19A 19 7 20 25 21 16A 12 23(1) 6 26 10 15 13A 17(1) 24 27 22 5 22A 15A 23(3) 8A 17(2)

5

Uranium Enrichment  

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

Enrichment Depleted Uranium line line Uranium Enrichment Depleted Uranium Health Effects Uranium Enrichment A description of the uranium enrichment process, including gaseous...

6

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

7

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

8

Uranium Leasing Program | Department of Energy  

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

» Uranium Leasing Program » Uranium Leasing Program Uranium Leasing Program Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado LM currently manages the Uranium Leasing Program and continues to administer 31 lease tracts, all located within the Uravan Mineral Belt in southwestern Colorado. Twenty-nine of these lease tracts are actively held under lease and two lease tracts have been placed in inactive status indefinitely. Administrative duties include the ongoing monitoring and oversight of leaseholders' activities and the annual inspection of these lease tracts to identify and correct safety hazards or other environmental compliance issues. Program Summary Current Status The U.S. Department of Energy (DOE) has extended the public comment

9

EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties, Colorado  

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

This EIS evaluates the potential environmental impacts of management alternatives for DOEs Uranium Leasing Program, under which DOE administers tracts of land in western Colorado for exploration, development, and the extraction of uranium and vanadium ores.

10

Uranium Leasing Program: Lease Tract Metrics  

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

The Atomic Energy Act and other legislative actions authorized the U.S. Atomic Energy Commission (AEC), predecessor agency to the U.S. Department of Energy (DOE), to withdraw lands from the public...

11

Uranium and Its Compounds  

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

and Its Compounds Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects...

12

Abandoned Uranium Mines Report to Congress: LM Wants Your Input |  

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

Abandoned Uranium Mines Report to Congress: LM Wants Your Input Abandoned Uranium Mines Report to Congress: LM Wants Your Input Abandoned Uranium Mines Report to Congress: LM Wants Your Input April 11, 2013 - 1:33pm Addthis C-SR-10 Uintah Mine, Colorado, LM Uranium Lease Tracts C-SR-10 Uintah Mine, Colorado, LM Uranium Lease Tracts What does this project do? Goal 4. Optimize the use of land and assets Abandoned Uranium Mines Report to Congress The U.S. Department of Energy (DOE) Office of Legacy Management (LM) is seeking stakeholder input on an abandoned uranium mines report to Congress. On January 2, 2013, President Obama signed into law the National Defense Authorization Act for Fiscal Year 2013, which requires the Secretary of Energy, in consultation with the Secretary of the U.S Department of the Interior (DOI) and the Administrator

13

URANIUM ALLOYS  

DOE Patents (OSTI)

A uranium alloy is reported containing from 0.1 to 5 per cent by weight of molybdenum and from 0.1 to 5 per cent by weight of silicon, the balance being uranium.

Colbeck, E.W.

1959-12-29T23:59:59.000Z

14

Pyrolitic Uranium Compound (PYRUC)  

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

Pyrolitic Uranium Compound Pyrolitic Uranium Compound (PYRUC) PYRolitic Uranium Compound (PYRUC) is a shielding material consisting of depleted uranium UO2 or UC in either pellet...

15

URANIUM COMPOSITIONS  

DOE Patents (OSTI)

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

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

1959-05-12T23:59:59.000Z

16

Depleted Uranium and Uranium Alloys  

Science Conference Proceedings (OSTI)

...Naturally occurring uranium makes up 0.0004% of the crust of the Earth; it is 40 times more plentiful than silver, and 800 times more plentiful than gold. Natural uranium contains approximately 0.7% fissionable U 235 and 99.3%

17

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

18

Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment |  

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

Uranium Leasing Program Draft Programmatic EIS Issued for Public Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment March 15, 2013 - 11:08am Addthis Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment DOE has issued the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS)(DOE/EIS-0472D) for public review and comment. The document is available here and on the ULP PEIS website. Under the Uranium Leasing Program, the DOE Office of Legacy Management administers 31 tracts of land in Mesa, Montrose, and San Miguel counties that are leased to private entities to mine uranium and vanadium. The program covers an area of approximately 25,000 acres. No mining operations are active on the ULP lands at this time. DOE is preparing the ULP PEIS to

19

Management Controls over the Department of Energy's Uranium Leasing  

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

Management Controls over the Department of Energy's Uranium Leasing Management Controls over the Department of Energy's Uranium Leasing Program, OAS-M-08-05 Management Controls over the Department of Energy's Uranium Leasing Program, OAS-M-08-05 The Department of Energy's Uranium Leasing Program was established by the Atomic Energy Act of 1954 to develop a supply of domestic uranium to meet the nation's defense needs. Pursuant to the Act, the Program leases tracts of land to private sector entities for the purpose of mining uranium ore. According to Department officials, one purpose of the Program is to obtain a fair monetary return to the Government. The Program is administered by the Department's Office of Legacy Management through a contractor. The uranium leases issued by the Department include two types of royalty

20

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Table 21. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2008-2012

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

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

22

URANIUM IN ALKALINE ROCKS  

E-Print Network (OSTI)

combine to indicate uranium enrichment of an alkaline magma.uranium, the Ilfmaussaq intrusion contains an unusually high enrichment

Murphy, M.

2011-01-01T23:59:59.000Z

23

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%.

24

Uranium (U)  

Science Conference Proceedings (OSTI)

Table 63   Properties of unstable uranium isotopes with α-particle emission...Table 63 Properties of unstable uranium isotopes with α-particle emission Isotope Abundance, % Half-life ( t 1/2 ), years Energy, MeV 234 U 0.0055 2.47 ? 10 5 4.77, 4.72, 4.58, 4.47, 235 U 0.720 7.1 ? 10 6 4.40, 4.2 238 U 99.274 4.51 ? 10 9 4.18...

25

DOE Extends Public Comment Period for Uranium Program Environmental Impact  

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

Uranium Program Environmental Uranium Program Environmental Impact Statement DOE Extends Public Comment Period for Uranium Program Environmental Impact Statement April 18, 2013 - 1:08pm Addthis Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs, (720) 377-9672, ULinfo@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy (DOE) today announced that the public comment period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) has been extended to May 31, 2013. Under the Uranium Leasing Program, DOE's Office of Legacy Management manages 31 tracts of land in Mesa, Montrose, and San Miguel counties in Colorado - approximately 25,000 acres - that are leased to private entities for uranium and vanadium mining. No mining operations are active

26

Uranium-234  

SciTech Connect

Translation of Uran-234 by J. Sehmorak. The following subjects are discussed: /sup 234/U and other natural radioactive isotopes, fractionation of heavy radioactive elements in nature, fractionation of radioactive isotopes, /sup 234/U in nuclear geochemistry, /sup 234/U in uranium minerals, /sup 234/U in continental waters and in quaternary deposits, and /sup 234/U in the ocean. (LK)

Cherdyntsev, V.V.

1971-01-01T23:59:59.000Z

27

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

28

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

29

U.S. Department of Energy Office of Legacy Management National Environmental Policy Act Environmental Checldist  

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

28-10 28-10 U.S. Department of Energy Office of Legacy Management National Environmental Policy Act Environmental Checldist Project/Activity: New Verde Mine Investigations, Lease Tract C-G-26, Uranium Leasing Program A. Brief Project/Activity Description Energy Fuels Resources Corporation (EFRC), lessee to the U.S. Department of Energy Office of Legacy Management, proposes to evaluate former mine workings associated with the New Verde Mine on Lease Tract C-G-26 in preparation for potential future mine development. This lease tract is on Calamity Mesa, along the southern flank of the Uncompahgre Plateau in southwestern Mesa County. The mine site would be accessed by workers on a former mine access road and on public roads. A bulkhead, approximately 6 feet (ft) high and 9 ft wide, was constructed of concrete blocks in 1996 to seal the

30

CX-003488: Categorical Exclusion Determination | Department of Energy  

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

88: Categorical Exclusion Determination 88: Categorical Exclusion Determination CX-003488: Categorical Exclusion Determination New Verde Mine Investigations, Lease Tract C-G-26, Uranium Leasing Program CX(s) Applied: B1.28, B3.1 Date: 08/10/2010 Location(s): Mesa County, Colorado Office(s): Legacy Management Energy Fuels Resources Corporation (EFRC), lessee to the U.S. Department of Energy Office of Legacy Management, proposes to evaluate former mine workings associated with the New Verde Mine on Lease Tract C-G-26 in preparation for potential future mine development. This lease tract is on Calamity Mesa, along the southern flank of the Uncompahgre Plateau in southwestern Mesa County. The mine site would be accessed by workers on a former mine access road and on public roads. DOCUMENT(S) AVAILABLE FOR DOWNLOAD

31

Properties of Uranium Compounds  

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

Triuranium Octaoxide (U3O8) Uranium Dioxide (UO2) Uranium Tetrafluoride (U4) Uranyl Fluoride (UO2F2) The physical properties of the pertinent chemical forms of uranium are...

32

Uranium Quick Facts  

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

Uranium Quick Facts Uranium Quick Facts A collection of facts about uranium, DUF6, and DOEs DUF6 inventory. Over the years, the Department of Energy has received numerous...

33

PREPARATION OF URANIUM MONOSULFIDE  

DOE Patents (OSTI)

A process is given for preparing uranium monosulfide from uranium tetrafluoride dissolved in molten alkali metal chloride. A hydrogen-hydrogen sulfide gas mixture passed through the solution precipitates uranium monosulfide. (AEC)

Yoshioka, K.

1964-01-28T23:59:59.000Z

34

URANIUM IN ALKALINE ROCKS  

E-Print Network (OSTI)

1977. "Geology of Brazil's Uranium and Thorium Occurrences,"A tantalo-niobate of uranium, near pyrochlore. Isometric,niobate and tantalate of uranium, with ferrous iron and rare

Murphy, M.

2011-01-01T23:59:59.000Z

35

Derived enriched uranium market  

SciTech Connect

The potential impact on the uranium market of highly enriched uranium from nuclear weapons dismantling in the Russian Federation and the USA is analyzed. Uranium supply, conversion, and enrichment factors are outlined for each country; inventories are also listed. The enrichment component and conversion components are expected to cause little disruption to uranium markets. The uranium component of Russian derived enriched uranium hexafluoride is unresolved; US legislation places constraints on its introduction into the US market.

Rutkowski, E.

1996-12-01T23:59:59.000Z

36

Depleted Uranium Hexafluoride Management  

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

OFFICE OF DEPLETED URANIUM HEXAFLUORIDE MANAGEMENT Issuance Of Final Report On Preconceptual Designs For Depleted Uranium Hexafluoride Conversion Plants The Department of Energy...

37

Uranium Oxide Semiconductors  

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

of semiconductors, it would consume the annual production rate of depleted uranium from uranium enrichment facilities. For more information: PDF Semiconductive Properties of...

38

COPPER COATED URANIUM ARTICLE  

DOE Patents (OSTI)

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

Gray, A.G.

1958-10-01T23:59:59.000Z

39

Domestic Uranium Production Report  

U.S. Energy Information Administration (EIA)

Home > Nuclear > Domestic Uranium Production Report Domestic Uranium Production Report Data for: 2005 Release Date: May 15, 2006 Next Release: May 15, 2007

40

Manhattan Project: Uranium cubes  

Office of Scientific and Technical Information (OSTI)

Cubes of uranium metal, Los Alamos, 1945 Events > Difficult Choices, 1942 > More Uranium Research, 1942 Events > Bringing It All Together, 1942-1945 > Basic Research at Los Alamos,...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

DOE Prepares Programmatic Environmental Impact Statement for the Uranium  

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

Prepares Programmatic Environmental Impact Statement for the Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program DOE Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program January 18, 2012 - 3:13pm Addthis DOE Prepares Programmatic Environmental Impact Statement for the Uranium Leasing Program What does this project do? Goal 4. Optimize the use of land and assets The U.S. Department of Energy (DOE) Office of Legacy Management is responsible for administering the DOE Uranium Leasing Program (ULP) and its 31 uranium lease tracts located in the Uravan Mineral Belt of southwestern Colorado. The ULP began in 1948 when Congress authorized the U.S. Atomic Energy Commis-sion (AEC), a predecessor agency of DOE, to withdraw lands from the public domain for the sole purpose of exploring for, developing,

42

Uranium Industry Annual, 1992  

Science Conference Proceedings (OSTI)

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

43

PRODUCTION OF URANIUM TETRACHLORIDE  

DOE Patents (OSTI)

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

Calkins, V.P.

1958-12-16T23:59:59.000Z

44

PRODUCTION OF URANIUM MONOCARBIDE  

DOE Patents (OSTI)

A method of making essentially stoichiometric uranium monocarbide by pelletizing a mixture of uranium tetrafluoride, silicon, and carbon and reacting the mixture at a temperature of approximately 1500 to 1700 deg C until the reaction goes to completion, forming uranium monocarbide powder and volatile silicon tetrafluoride, is described. The powder is then melted to produce uranium monocarbide in massive form. (AEC)

Powers, R.M.

1962-07-24T23:59:59.000Z

45

FAQ 23-How much depleted uranium -- including depleted uranium...  

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

is stored in the United States? How much depleted uranium -- including depleted uranium hexafluoride -- is stored in the United States? In addition to the depleted uranium stored...

46

DECONTAMINATION OF URANIUM  

DOE Patents (OSTI)

This patent deals with the separation of rare earth and other fission products from neutron bombarded uranium. This is accomplished by melting the uranium in contact with either thorium oxide, maguesium oxide, alumnum oxide, beryllium oxide, or uranium dioxide. The melting is preferably carried out at from 1150 deg to 1400 deg C in an inert atmosphere, such as argon or helium. During this treatment a scale of uranium dioxide forms on the uranium whtch contains most of the fission products.

Feder, H.M.; Chellew, N.R.

1958-02-01T23:59:59.000Z

47

Uranium series disequilibrium in the Bargmann property area of Karnes County, Texas  

SciTech Connect

Historical evidence is presented for natural uranium series radioactive disequilibrium in uranium bearing soils in the Bargmann property area of karnes County on the Gulf Coastal Plain of south Texas. The early history of uranium exploration in the area is recounted and records of disequilibrium before milling and mining operations began are given. The property contains an open pit uranium mine associated with a larger ore body. In 1995, the US Department of Energy (DOE) directed Oak Ridge National Laboratory (ORNL) to evaluate the Bargmann tract for the presence of uranium mill tailings (ORNL 1996). There was a possibility that mill tailings had washed onto or blown onto the property from the former tailings piles in quantities that would warrant remediation under the Uranium Mill Tailings Remediation Action Project. Activity ratios illustrating disequilibrium between {sup 226}Ra and {sup 238}U in background soils during 1986 are listed and discussed. Derivations of uranium mass-to-activity conversion factors are covered in detail.

Davidson, J.R.

1998-02-01T23:59:59.000Z

48

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,

49

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

50

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

51

Process for electroslag refining of uranium and uranium alloys  

DOE Patents (OSTI)

A process is described for electroslag refining of uranium and uranium alloys wherein molten uranium and uranium alloys are melted in a molten layer of a fluoride slag containing up to about 8 weight percent calcium metal. The calcium metal reduces oxides in the uranium and uranium alloys to provide them with an oxygen content of less than 100 parts per million. (auth)

Lewis, P.S. Jr.; Agee, W.A.; Bullock, J.S. IV; Condon, J.B.

1975-07-22T23:59:59.000Z

52

SOLDERING OF URANIUM  

SciTech Connect

One of Its Monograph Series, The Industrial Atom.'' The joining of uranium to uranium has been done successfully using a number of commercial soft solders and fusible alloys. Soldering by using an ultrasonic soldering iron has proved the best method for making sound soldered joints of uranium to uranium and of uranium to other metals, such as stainless steel. Other method of soldering have shown some promise but did not give reliable joints all the time. The soldering characteristics of uranium may best be compared to those of aluminum. (auth)

Hanks, G.S.; Doll, D.T.; Taub, J.M.; Brundige, E.L.

1957-01-01T23:59:59.000Z

53

URANIUM RECOVERY PROCESS  

DOE Patents (OSTI)

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

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

1959-02-10T23:59:59.000Z

54

PRODUCTION OF PURIFIED URANIUM  

DOE Patents (OSTI)

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

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

1960-01-26T23:59:59.000Z

55

EPA Update: NESHAP Uranium Activities  

E-Print Network (OSTI)

measurements have been performed on high-enriched uranium (HEU) oxide fuel pins and depleted uranium metal

56

Method of recovering uranium hexafluoride  

DOE Patents (OSTI)

A method of recovering uranium hexafluoride from gaseous mixtures which comprises adsorbing said uranium hexafluoride on activated carbon is described.

Schuman, S.

1975-12-01T23:59:59.000Z

57

Atomic Data for Uranium (U )  

Science Conference Proceedings (OSTI)

... Uranium (U) Homepage - Introduction Finding list Select element by name. Select element by atomic number. ... Atomic Data for Uranium (U). ...

58

Uranium from phosphate ores  

SciTech Connect

The following topics are described briefly: the way phosphate fertilizers are made; how uranium is recovered in the phosphate industry; and how to detect covert uranium recovery operations in a phsophate plant.

Hurst, F.J.

1983-01-01T23:59:59.000Z

59

Uranium Health Effects  

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

For inhalation or ingestion of soluble or moderately soluble compounds such as uranyl fluoride (UO2F2) or uranium tetrafluoride (UF4), the uranium enters the bloodstream and...

60

METHOD FOR PURIFYING URANIUM  

DOE Patents (OSTI)

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

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

1960-04-26T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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 Quick Facts  

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

Uranium Quick Facts A collection of facts about uranium, DUF6, and DOEs DUF6 inventory. Over the years, the Department of Energy has received numerous inquiries from the...

62

Cathodoluminescence of uranium oxides  

SciTech Connect

The cathodoluminescence of uranium oxide surfaces prepared in-situ from clean uranium exposed to dry oxygen was studied. The broad asymmetric peak observed at 470 nm is attributed to F-center excitation.

Winer, K.; Colmenares, C.; Wooten, F.

1984-08-09T23:59:59.000Z

63

Bicarbonate leaching of uranium  

SciTech Connect

The alkaline leach process for extracting uranium from uranium ores is reviewed. This process is dependent on the chemistry of uranium and so is independent on the type of mining system (conventional, heap or in-situ) used. Particular reference is made to the geochemical conditions at Crownpoint. Some supporting data from studies using alkaline leach for remediation of uranium-contaminated sites is presented.

Mason, C.

1998-12-31T23:59:59.000Z

64

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

65

PREPARATION OF URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

A process is described for preparing uranium hexafluoride from carbonate- leach uranium ore concentrate. The briquetted, crushed, and screened concentrate is reacted with hydrogen fluoride in a fluidized bed, and the uranium tetrafluoride formed is mixed with a solid diluent, such as calcium fluoride. This mixture is fluorinated with fluorine and an inert diluent gas, also in a fluidized bed, and the uranium hexafluoride obtained is finally purified by fractional distillation.

Lawroski, S.; Jonke, A.A.; Steunenberg, R.K.

1959-10-01T23:59:59.000Z

66

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

67

Overview: A Legacy of Uranium Enrichment  

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

A Legacy of Uranium Enrichment Depleted Uranium is a Legacy of Uranium Enrichment Cylinders Photo Next Screen Management Responsibilities...

68

PRODUCTION OF URANIUM TETRAFLUORIDE  

DOE Patents (OSTI)

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

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

1959-08-01T23:59:59.000Z

69

FAQ 10-Why is uranium hexafluoride used?  

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

uranium hexafluoride used? Why is uranium hexafluoride used? Uranium hexafluoride is used in uranium processing because its unique properties make it very convenient. It can...

70

DOE Extends Public Comment Period for the Draft Uranium Leasing Program  

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

the Draft Uranium Leasing the Draft Uranium Leasing Program Programmatic Environmental Impact Statement DOE Extends Public Comment Period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement June 3, 2013 - 3:05pm Addthis Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs, (720) 377-9672, ULinfo@lm.doe.gov May 29, 2013 DOE Extends Public Comment Period for Uranium Program Environmental Impact Statement The U.S. Department of Energy (DOE) today announced that the public comment period for the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) has been extended to July 1, 2013. Under the Uranium Leasing Program, DOE's Office of Legacy Management manages 31 tracts of land in Mesa, Montrose, and San Miguel counties in

71

DOE Evaluates Environmental Impacts of Uranium Mining on Government Land in  

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

Evaluates Environmental Impacts of Uranium Mining on Government Evaluates Environmental Impacts of Uranium Mining on Government Land in Western Colorado DOE Evaluates Environmental Impacts of Uranium Mining on Government Land in Western Colorado March 15, 2013 - 12:20pm Addthis Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs, (720) 377-9672, ULinfo@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy (DOE) today announced that the Draft Uranium Leasing Program Programmatic Environmental Impact Statement (ULP PEIS) is available for public review and comment. Under the Uranium Leasing Program, DOE's Office of Legacy Management manages 31 tracts of land in Mesa, Montrose, and San Miguel counties in Colorado - approximately 25,000 acres - that are leased to private entities for uranium and vanadium mining. No mining operations are active

72

URANIUM RECOVERY PROCESS  

DOE Patents (OSTI)

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

Yeager, J.H.

1958-08-12T23:59:59.000Z

73

URANIUM SEPARATION PROCESS  

DOE Patents (OSTI)

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

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

1959-07-14T23:59:59.000Z

74

PRODUCTION OF URANIUM  

DOE Patents (OSTI)

The production of uranium metal by the reduction of uranium tetrafluoride is described. Massive uranium metal of high purily is produced by reacting uranium tetrafluoride with 2 to 20% stoichiometric excess of magnesium at a temperature sufficient to promote the reaction and then mantaining the reaction mass in a sealed vessel at temperature in the range of 1150 to 2000 d C, under a superatomospheric pressure of magnesium for a period of time sufficient 10 allow separation of liquid uranium and liquid magnesium fluoride into separate layers.

Spedding, F.H.; Wilhelm, H.A.; Keller, W.H.

1958-04-15T23:59:59.000Z

75

Method for converting uranium oxides to uranium metal  

DOE Green Energy (OSTI)

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

Duerksen, Walter K. (Norris, TN)

1988-01-01T23:59:59.000Z

76

Method for converting uranium oxides to uranium metal  

DOE Patents (OSTI)

A process is described for converting scrap and waste uranium oxide to uranium metal. The uranium oxide is sequentially reduced with a suitable reducing agent to a mixture of uranium metal and oxide products. The uranium metal is then converted to uranium hydride and the uranium hydride-containing mixtures is then cooled to a temperature less than -100/sup 0/C in an inert liquid which renders the uranium hydride ferromagnetic. The uranium hydride is then magnetically separated from the cooled mixture. The separated uranium hydride is readily converted to uranium metal by heating in an inert atmosphere. This process is environmentally acceptable and eliminates the use of hydrogen fluoride as well as the explosive conditions encountered in the previously employed bomb-reduction processes utilized for converting uranium oxides to uranium metal.

Duerksen, W.K.

1987-01-01T23:59:59.000Z

77

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.

78

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

79

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.

80

First Principles Calculations of Uranium and Uranium-Zirconium Alloys  

Science Conference Proceedings (OSTI)

Presentation Title, First Principles Calculations of Uranium and Uranium- Zirconium Alloys. Author(s), Benjamin Good, Benjamin Beeler, Chaitanya Deo, Sergey...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

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

82

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.

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

1995-01-01T23:59:59.000Z

83

Preparation of uranium compounds  

SciTech Connect

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

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

2013-02-19T23:59:59.000Z

84

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration: Form EIA-851A, "Domestic Uranium Production Report"...

85

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

1. U.S. uranium drilling activities, 2003-2012 Exploration Drilling Development Drilling Exploration and Development Drilling Year Number of Holes Feet (thousand) Number of Holes...

86

Uranium 'pearls' before slime  

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

harm to themselves, scientists have wondered how on Earth these microbes do it. For Shewanella oneidensis, a microbe that modifies uranium chemistry, the pieces are coming...

87

Uranium Purchases Report  

Reports and Publications (EIA)

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

Douglas Bonnar

1996-06-01T23:59:59.000Z

88

PRODUCTION OF URANIUM  

DOE Patents (OSTI)

An improved process is described for the magnesium reduction of UF/sub 4/ to produce uranium metal. In the past, there have been undesirable premature reactions between the Mg and the bomb liner or the UF/sub 4/ before the actual ignition of the bomb reaction. Since these premature reactions impair the yield of uranium metal, they have been inhibited by forming a protective film upon the particles of Mg by reacting it with hydrated uranium tetrafluoride, sodium bifluoride, uranyl fluoride, or uranium trioxide. This may be accomplished by adding about 0.5 to 2% of the additive to the bomb charge.

Ruehle, A.E.; Stevenson, J.W.

1957-11-12T23:59:59.000Z

89

Uranium Purchases Report 1995  

U.S. Energy Information Administration (EIA)

DOE/EIA0570(95) Distribution Category UC950 Uranium Purchases Report 1995 June 1996 Energy Information Administration Office of Coal, Nuclear, ...

90

2012 Domestic Uranium Production Report  

U.S. Energy Information Administration (EIA)

udrilling 2012 Domestic Uranium Production Report Next Release Date: May 2014 Table 1. U.S. uranium drilling activities, 2003-2012 Year Exploration Drilling

91

URANIUM LEACHING AND RECOVERY PROCESS  

DOE Patents (OSTI)

A process is described for recovering uranium from carbonate leach solutions by precipitating uranium as a mixed oxidation state compound. Uranium is recovered by adding a quadrivalent uranium carbon;te solution to the carbonate solution, adjusting the pH to 13 or greater, and precipitating the uranium as a filterable mixed oxidation state compound. In the event vanadium occurs with the uranium, the vanadium is unaffected by the uranium precipitation step and remains in the carbonate solution. The uranium-free solution is electrolyzed in the cathode compartment of a mercury cathode diaphragm cell to reduce and precipitate the vanadium.

McClaine, L.A.

1959-08-18T23:59:59.000Z

92

PROCESS FOR MAKING URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

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

Rosen, R.

1959-07-14T23:59:59.000Z

93

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

94

EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties,  

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

2: Uranium Leasing Program, Mesa, Montrose, and San Miguel 2: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties, Colorado EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties, Colorado Summary This EIS evaluates the environmental impacts of management alternatives for DOE's Uranium Leasing Program, under which DOE administers tracts of land in western Colorado for exploration, development, and the extraction of uranium and vanadium ores. The cooperating agencies are U.S. Department of the Interior; Bureau of Land Management; U.S. Environmental Protection Agency; Colorado Department of Transportation; Colorado Division of Reclamation, Mining, and Safety; Colorado Parks and Wildlife; Mesa County Commission; Montrose County Commission; San Juan County Commission; San Miguel County Board of

95

URANIUM SEPARATION PROCESS  

DOE Patents (OSTI)

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

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

1959-03-10T23:59:59.000Z

96

Uranium from phosphate ores  

Science Conference Proceedings (OSTI)

Phosphate rock, the major raw material for phosphate fertilizers, contains uranium that can be recovered when the rock is processed. This makes it possible to produce uranium in a country that has no uranium ore deposits. The author briefly describes the way that phosphate fertilizers are made, how uranium is recovered in the phosphate industry, and how to detect uranium recovery operations in a phosphate plant. Uranium recovery from the wet-process phosphoric acid involves three unit operations: (1) pretreatment to prepare the acid; (2) solvent extraction to concentrate the uranium; (3) post treatment to insure that the acid returning to the acid plant will not be harmful downstream. There are 3 extractants that are capable of extracting uranium from phosphoric acid. The pyro or OPPA process uses a pyrophosphoric acid that is prepared on site by reacting an organic alcohol (usually capryl alcohol) with phosphorous pentoxide. The DEPA-TOPO process uses a mixture of di(2-ethylhexyl)phosphoric acid (DEPA) and trioctyl phosphine oxide (TOPO). The components can be bought separately or as a mixture. The OPAP process uses octylphenyl acid phosphate, a commercially available mixture of mono- and dioctylphenyl phosphoric acids. All three extractants are dissolved in kerosene-type diluents for process use.

Hurst, F.J.

1983-01-01T23:59:59.000Z

97

DECONTAMINATION OF URANIUM  

DOE Patents (OSTI)

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

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

1962-05-15T23:59:59.000Z

98

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,

99

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),

100

URANIUM PRECIPITATION PROCESS  

DOE Patents (OSTI)

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

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

1957-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.


101

India's Worsening Uranium Shortage  

Science Conference Proceedings (OSTI)

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

Curtis, Michael M.

2007-01-15T23:59:59.000Z

102

Video: The Depleted Uranium Hexafluoride Story  

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

Depleted UF6 Story The Depleted Uranium Hexafluoride Story An overview of Uranium, its isotopes, the need and history of diffusive separation, the handling of the Depleted Uranium...

103

BEHAVIOR OF METALLIC INCLUSIONS IN URANIUM DIOXIDE  

E-Print Network (OSTI)

Metallic Inclusions in Uranium Dioxide", LBL-11117 (1980).in Hypostoichiornetric Uranium Dioxide 11 , LBL-11095 (OF METALLIC INCLUSIONS IN URANIUM DIOXIDE Rosa L. Yang and

Yang, Rosa L.

2013-01-01T23:59:59.000Z

104

RECOVERY OF URANIUM VALUES  

DOE Patents (OSTI)

A liquid-liquid extraction method is presented for recovering uranium values from an aqueous acidic solution by means of certain high molecular weight amine in the amine classes of primary, secondary, heterocyclic secondary, tertiary, or heterocyclic tertiary. The uranium bearing aqueous acidic solution is contacted with the selected amine dissolved in a nonpolar water-immiscible organic solvent such as kerosene. The uranium which is substantially completely exiracted by the organic phase may be stripped therefrom by waters and recovered from the aqueous phase by treatment into ammonia to precipitate ammonium diuranate.

Brown, K.B.; Crouse, D.J. Jr.; Moore, J.G.

1959-03-10T23:59:59.000Z

105

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

106

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

107

Uranium-Based Catalysts  

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

Uranium-Based Catalysts S. H. Overbury, Cyrus Riahi-Nezhad, Zongtao Zhang, Sheng Dai, and Jonathan Haire Oak Ridge National Laboratory* P.O. Box 2008 Oak Ridge, Tennessee...

108

Domestic Uranium Production Report  

Annual Energy Outlook 2012 (EIA)

6. Employment in the U.S. uranium production industry by category, 2003-2012 person-years Year Exploration Mining Milling Processing Reclamation Total 2003 W W W W 117 321 2004 18...

109

Uranium Management and Policy  

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

The Office of Uranium Management and Policy (NE-54), as part of the Office of Fuel Cycle Technologies (NE-5), supports the Department of Energy (DOE) by assuring domestic supplies of fuel for...

110

Chemical Forms of Uranium  

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

such as water vapor in the air, the UF6 and water react, forming corrosive hydrogen fluoride (HF) and a uranium-fluoride compound called uranyl fluoride (UO2F2). For this reason,...

111

300 AREA URANIUM CONTAMINATION  

SciTech Connect

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

BORGHESE JV

2009-07-02T23:59:59.000Z

112

Depleted uranium valuation  

SciTech Connect

The following uses for depleted uranium were examined to determine its value: a substitute for lead in shielding applications, feed material in gaseous diffusion enrichment facilities, feed material for an advanced enrichment concept, Mixed Oxide (MOx) diluent and blanket material in LMFBRs, and fertile material in LMFBR systems. A range of depleted uranium values was calculated for each of these applications. The sensitivity of these values to analysis assumptions is discussed. 9 tables.

Lewallen, M.A.; White, M.K.; Jenquin, U.P.

1979-04-01T23:59:59.000Z

113

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.

1995-07-01T23:59:59.000Z

114

URANIUM SEPARATION PROCESS  

DOE Patents (OSTI)

A method of separating uranium oxides from PuO/sub 2/, ThO/sub 2/, and other actinide oxides is described. The oxide mixture is suspended in a fused salt melt and a chlorinating agent such as chlorine gas or phosgene is sparged through the suspension. Uranium oxides are selectively chlorinated and dissolve in the melt, which may then be filtered to remove the unchlorinated oxides of the other actinides. (AEC)

Lyon, W.L.

1962-04-17T23:59:59.000Z

115

Uranium tailings bibliography  

SciTech Connect

A bibliography containing 1,212 references is presented with its focus on the general problem of reducing human exposure to the radionuclides contained in the tailings from the milling of uranium ore. The references are divided into seven broad categories: uranium tailings pile (problems and perspectives), standards and philosophy, etiology of radiation effects, internal dosimetry and metabolism, environmental transport, background sources of tailings radionuclides, and large-area decontamination. (JSR)

Holoway, C.F.; Goldsmith, W.A.; Eldridge, V.M.

1975-12-01T23:59:59.000Z

116

URANIUM EXTRACTION PROCESS  

DOE Patents (OSTI)

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

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

1958-12-16T23:59:59.000Z

117

Method for the recovery of uranium values from uranium tetrafluoride  

DOE Patents (OSTI)

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

Kreuzmann, A.B.

1982-10-27T23:59:59.000Z

118

Method for the recovery of uranium values from uranium tetrafluoride  

DOE Patents (OSTI)

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

Kreuzmann, Alvin B. (Cincinnati, OH)

1983-01-01T23:59:59.000Z

119

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.

120

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.

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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 6-What is depleted uranium?  

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

depleted uranium? What is depleted uranium? Depleted uranium is created during the processing that is done to make natural uranium suitable for use as fuel in nuclear power plants...

122

Tag: uranium | Y-12 National Security Complex  

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

uranium Tag: uranium Displaying 1 - 10 of 23... Category: News The Nation's Expert in All Things Uranium Y-12 serves the nation and the world as a center of excellence for uranium...

123

The Nature of Vibrational Softening in ? - Uranium  

Science Conference Proceedings (OSTI)

... The Nature of Vibrational Softening in ? - Uranium. The standard textbook ... B / atom. All experiments used uranium powder. High ...

124

Education: Digital Resource Center - WEB: Uranium Information ...  

Science Conference Proceedings (OSTI)

Sep 24, 2007 ... Uranium, Electricity and the Greenhouse Effect ... Educational Resource Papers," Australian Uranium Association Ltd. Site updated weekly.

125

Energy Levels of Neutral Uranium ( U I )  

Science Conference Proceedings (OSTI)

... Data, Uranium (U) Homepage - Introduction Finding list Select element by name. ... Version Energy Levels of Neutral Uranium ( U I ). ...

126

Domestic Uranium Production Report - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel, nuclear reactors, generation, ... with currently proven mining and processing technology and under current law and regulations.

127

Domestic Uranium Production Report 2004 -2011  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

128

Process for electrolytically preparing uranium metal  

DOE Patents (OSTI)

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

Haas, Paul A. (Knoxville, TN)

1989-01-01T23:59:59.000Z

129

Microsoft Word - A07DN052 Uranium Leasing Final Report 01-15-08.doc  

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

Audit Services Audit Services Audit Report Management Controls over the Department of Energy's Uranium Leasing Program OAS-M-08-05 January 2008 Department of Energy Washington, DC 20585 J a n u a r y 2 3 , 2 0 0 8 MEMORANDUM FOR THE DIRECTOR, OFFICE OF LEGACY MANAGEMENT FROM: ~ssista/nt Lnspector General for NNSA and Energy Audits Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Management Controls over the Department of Energy's Uranium Leasing Program" BACKGROUND The Department of Energy's Uranium Leasing Program was established by the Atomic Energy Act of 1954 to develop a supply of domestic uranium to meet the nation's defense needs. Pursuant to the Act, the Program leases tracts of land to private sector entities for

130

Uranium resources: Issues and facts  

SciTech Connect

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

Delene, J.G.

1993-12-31T23:59:59.000Z

131

METHOD OF RECOVERING URANIUM COMPOUNDS  

DOE Patents (OSTI)

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

Poirier, R.H.

1957-10-29T23:59:59.000Z

132

METHOD OF SINTERING URANIUM DIOXIDE  

DOE Green Energy (OSTI)

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

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

1963-04-30T23:59:59.000Z

133

Uranium-titanium-niobium alloy  

DOE Patents (OSTI)

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

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

1990-01-01T23:59:59.000Z

134

It's Elemental - The Element Uranium  

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

into uranium-233, also through beta decay. If completely fissioned, one pound (0.45 kilograms) of uranium-233 will provide the same amount of energy as burning 1,500 tons...

135

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

136

PRODUCTION OF URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

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

Fowler, R.D.

1957-08-27T23:59:59.000Z

137

Uranium immobilization and nuclear waste  

SciTech Connect

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

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

1982-02-01T23:59:59.000Z

138

PROCESS OF PREPARING URANIUM CARBIDE  

DOE Patents (OSTI)

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

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

1964-03-24T23:59:59.000Z

139

EXTRACTION OF URANIUM  

DOE Patents (OSTI)

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

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

1959-07-28T23:59:59.000Z

140

PROCESS OF RECOVERING URANIUM  

DOE Patents (OSTI)

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

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

1958-06-17T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

TREATMENT OF URANIUM SURFACES  

DOE Patents (OSTI)

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

Slunder, C.J.

1959-02-01T23:59:59.000Z

142

Production and Handling Slide 21: Melting Points of Uranium and...  

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

Points of Uranium and Uranium Compounds Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Melting Points of Uranium and Uranium...

143

FAQ 26-Are there any uses for depleted uranium?  

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

uses for depleted uranium? Are there any uses for depleted uranium? Several current and potential uses exist for depleted uranium. Depleted uranium could be mixed with highly...

144

High loading uranium fuel plate  

DOE Patents (OSTI)

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

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

1990-01-01T23:59:59.000Z

145

STRIPPING OF URANIUM FROM ORGANIC EXTRACTANTS  

DOE Patents (OSTI)

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

Crouse, D.J. Jr.

1962-09-01T23:59:59.000Z

146

Depleted Uranium Technical Brief  

E-Print Network (OSTI)

. This Technical Brief specifically addresses DU in an environmental contamination setting and specifically does.S. Department of Energy (DOE) and other govern ment sources. DU occurs in a number of different compounds airborne releases of uranium at one DOE facility amounted to 310,000 kg between 1951 and 1988, which

147

URANIUM RECOVERY PROCESS  

DOE Patents (OSTI)

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

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

1959-07-01T23:59:59.000Z

148

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

149

PRODUCTION OF URANIUM METAL BY CARBON REDUCTION  

DOE Patents (OSTI)

The preparation of uranium metal by the carbon reduction of an oxide of uranium is described. In a preferred embodiment of the invention a charge composed of carbon and uranium oxide is heated to a solid mass after which it is further heated under vacuum to a temperature of about 2000 deg C to produce a fused uranium metal. Slowly ccoling the fused mass produces a dendritic structure of uranium carbide in uranium metal. Reacting the solidified charge with deionized water hydrolyzes the uranium carbide to finely divide uranium dioxide which can be separated from the coarser uranium metal by ordinary filtration methods.

Holden, R.B.; Powers, R.M.; Blaber, O.J.

1959-09-22T23:59:59.000Z

150

Remediation and Recovery of Uranium from Contaminated  

E-Print Network (OSTI)

uranium containing the mixture of isotopes occurring in nature; uranium depleted in the isotope 235; Depleted uranium 1000 kilograms; and Thorium 1000 kilograms. #12;INFCIRC/254/Rev.9/Part.1 November 2007 Annex B, section 4.); 2.5. Plants for the separation of isotopes of natural uranium, depleted uranium

Lovley, Derek

151

Method of preparation of uranium nitride  

SciTech Connect

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

Kiplinger, Jaqueline Loetsch; Thomson, Robert Kenneth James

2013-07-09T23:59:59.000Z

152

Method of preparing uranium nitride or uranium carbonitride bodies  

DOE Patents (OSTI)

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

Wilhelm, Harley A. (Ames, IA); McClusky, James K. (Valparaiso, IN)

1976-04-27T23:59:59.000Z

153

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

154

METHOD OF PRODUCING URANIUM  

DOE Patents (OSTI)

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

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

1958-05-13T23:59:59.000Z

155

ELECTROLYSIS OF THORIUM AND URANIUM  

DOE Patents (OSTI)

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

Hansen, W.N.

1960-09-01T23:59:59.000Z

156

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

157

WELDED JACKETED URANIUM BODY  

DOE Patents (OSTI)

A fuel element is presented for a neutronic reactor and is comprised of a uranium body, a non-fissionable jacket surrounding sald body, thu jacket including a portion sealed by a weld, and an inclusion in said sealed jacket at said weld of a fiux having a low neutron capture cross-section. The flux is provided by combining chlorine gas and hydrogen in the intense heat of-the arc, in a "Heliarc" welding muthod, to form dry hydrochloric acid gas.

Gurinsky, D.H.

1958-08-26T23:59:59.000Z

158

FAQ 2-Where does uranium come from?  

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

come from? Where does uranium come from? Small amounts of uranium are found almost everywhere in soil, rock, and water. However, concentrated deposits of uranium ores are found in...

159

IMPROVED PROCESSES FOR RECOVERING AND PURIFYING URANIUM  

DOE Patents (OSTI)

A process is described for reclaiming metallic uranium enriched with uranium-235 from the collector of a calutron upon which the enriched metallic uranium is Editor please delete 22166.

Price, T.D.; Henrickson, A.V.

1959-05-12T23:59:59.000Z

160

OXYGEN DIFFUSION IN HYPOSTOICHIOMETRIC URANIUM DIOXIDE  

E-Print Network (OSTI)

IN HYPOSTOICHIOMETRIC URANIUM DIOXIDE Kee Chul Kim Ph.D.727-366; Figure 1. Oxygen-uranium phase-equilibrium _ystem [18]. uranium dioxide powders and 18 0 enriched carbon

Kim, Kee Chul

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

Reoxidation of Bioreduced Uranium Under Reducing Conditions  

E-Print Network (OSTI)

Microbial reduction of uranium. Nature 350, 413-416 (1991).C. Enzymatic iron and uranium reduction by sulfate-reducingS. Reduction of hexavalent uranium from organic complexes by

2005-01-01T23:59:59.000Z

162

PROCESS FOR REMOVING NOBLE METALS FROM URANIUM  

DOE Patents (OSTI)

A pyrometallurgical method is given for purifying uranium containing ruthenium and palladium. The uranium is disintegrated and oxidized by exposure to air and then the ruthenium and palladium are extracted from the uranium with molten zinc.

Knighton, J.B.

1961-01-31T23:59:59.000Z

163

METHOD OF JACKETING URANIUM BODIES  

DOE Patents (OSTI)

An improved process is presented for providing uranium slugs with thin walled aluminum jackets. Since aluminum has a slightiy higher coefficient of thermal expansion than does uraaium, both uranium slugs and aluminum cans are heated to an elevated temperature of about 180 C, and the slug are inserted in the cans at that temperature. During the subsequent cooling of the assembly, the aluminum contracts more than does the uranium and a tight shrink fit is thus assured.

Maloney, J.O.; Haines, E.B.; Tepe, J.B.

1958-08-26T23:59:59.000Z

164

PROCESS FOR PREPARING URANIUM METAL  

DOE Patents (OSTI)

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

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

1959-01-13T23:59:59.000Z

165

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.

166

Page not found | Department of Energy  

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

61 - 26170 of 31,917 results. 61 - 26170 of 31,917 results. Download CX-004163: Categorical Exclusion Determination Mobile Meteorological Equipment CX(s) Applied: B3.1 Date: 08/02/2010 Location(s): New Mexico Office(s): Sandia Site Office http://energy.gov/nepa/downloads/cx-004163-categorical-exclusion-determination Download CX-003331: Categorical Exclusion Determination Reclamation Projects on Slick Rock Lease Tract C-SR-II, Uranium Leasing Program CX(s) Applied: B1.28 Date: 07/30/2010 Location(s): San Miguel County, Colorado Office(s): Legacy Management http://energy.gov/nepa/downloads/cx-003331-categorical-exclusion-determination Download CX-003333: Categorical Exclusion Determination Reclamation Projects in Lease Tract C-G-26, Uranium Leasing Program CX(s) Applied: B1.28 Date: 07/30/2010

167

Y-12 and uranium history  

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

German chemists, Otto Hahn and Fritz Strassman, successfully described a new term, nuclear fission, for their experiment that resulted in the first splitting of the uranium atom....

168

Highly Enriched Uranium Transparency Program  

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

and Climate Research Center for Geospatial Analysis Program Highlights Index Highly Enriched Uranium Transparency Program EVS staff members helped to implement transparency and...

169

ELECTROLYTIC PRODUCTION OF URANIUM TETRAFLUORIDE  

DOE Patents (OSTI)

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

Lofthouse, E.

1954-08-31T23:59:59.000Z

170

THERMAL DECOMPOSITION OF URANIUM COMPOUNDS  

DOE Patents (OSTI)

A method is presented of preparing uranium metal of high purity consisting contacting impure U metal with halogen vapor at between 450 and 550 C to form uranium halide vapor, contacting the uranium halide vapor in the presence of H/sub 2/ with a refractory surface at about 1400 C to thermally decompose the uranium halides and deposit molten U on the refractory surface and collecting the molten U dripping from the surface. The entire operation is carried on at a sub-atmospheric pressure of below 1 mm mercury.

Magel, T.T.; Brewer, L.

1959-02-10T23:59:59.000Z

171

SEPARATION OF THORIUM FROM URANIUM  

DOE Patents (OSTI)

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

Bane, R.W.

1959-09-01T23:59:59.000Z

172

PREPARATION OF URANIUM(IV) NITRATE SOLUTIONS  

SciTech Connect

A procedure was developed for the preparation of uranium(IV) nitrate solutions in dilute nitric acid. Zinc metal was used as a reducing agent for uranium(VI) in dilute sulfuric acid. The uranium(IV) was precipitated as the hydrated oxide and dissolved in nitric acid. Uranium(IV) nitrate solutions were prepared at a maximum concentration of 100 g/l. The uranium(VI) content was less than 2% of the uranium(IV). (auth)

Ondrejcin, R.S.

1961-07-01T23:59:59.000Z

173

METHOD FOR RECOVERING URANIUM FROM OILS  

DOE Patents (OSTI)

A method is presented for recovering uranium from hydrocarbon oils, wherein the uranium is principally present as UF/sub 4/. According to the invention, substantially complete removal of the uranium from the hydrocarbon oil may be effected by intimately mixing one part of acetone to about 2 to 12 parts of the hydrocarbon oil containing uranium and separating the resulting cake of uranium from the resulting mixture. The uranium in the cake may be readily recovered by burning to the oxide.

Gooch, L.H.

1959-07-14T23:59:59.000Z

174

Uranium Compounds and Other Natural Radioactivities  

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

X-ray Science Division XSD Groups Industry Argonne Home Advanced Photon Source Uranium Compounds and Other Natural Radioactivities Uranium containing compounds and other...

175

Uranium Downblending and Disposition Project Technology Readiness...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Uranium Downblending and Disposition Project Technology Readiness Assessment Uranium...

176

Uranium Mining Tax (Nebraska) | Department of Energy  

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

Sites Power Marketing Administration Other Agencies You are here Home Savings Uranium Mining Tax (Nebraska) Uranium Mining Tax (Nebraska) Eligibility Agricultural...

177

Microsoft Word - UraniumBioreductionV3  

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

Science Highlight - March 2013 Biotic-Abiotic Pathways: A New Paradigm for Uranium Reduction in Sediments Uranium, one of the most common radioactive elements on Earth, makes its...

178

Uranium Leasing Program | Department of Energy  

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

Uranium Leasing Program Uranium Leasing Program Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado Abandoned Mine Reclamation, Uravan Mineral Belt, Colorado LM currently...

179

Consolidated Edison Uranium Solidification Project | Department...  

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

Consolidated Edison Uranium Solidification Project Consolidated Edison Uranium Solidification Project CEUSP Inventory11-6-13Finalprint-ready.pdf CEUSPtimelinefinalprint-ready...

180

PROCESS OF PRODUCING REFRACTORY URANIUM OXIDE ARTICLES  

DOE Patents (OSTI)

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

Hamilton, N.E.

1957-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

Uranium Enrichment Decontamination and Decommissioning Fund's...  

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

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

182

Understanding How Uranium Changes in Subsurface Environments...  

Office of Science (SC) Website

whether it is immobilized or moves out of a contaminated area, potentially into water supplies. The Impact New research on the transformation of uranium (VI) to uranium...

183

Domestic Uranium Production Report - Quarterly - Energy ...  

U.S. Energy Information Administration (EIA)

Total anticipated uranium market requirements at U.S. civilian nuclear power reactors are 50 million pounds for 2013. 2. 1 2012 Uranium Marketing ...

184

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

185

FLAME DENITRATION AND REDUCTION OF URANIUM NITRATE TO URANIUM DIOXIDE  

DOE Patents (OSTI)

A process is given for converting uranyl nitrate solution to uranium dioxide. The process comprises spraying fine droplets of aqueous uranyl nitrate solution into a hightemperature hydrocarbon flame, said flame being deficient in oxygen approximately 30%, retaining the feed in the flame for a sufficient length of time to reduce the nitrate to the dioxide, and recovering uranium dioxide. (AEC)

Hedley, W.H.; Roehrs, R.J.; Henderson, C.M.

1962-06-26T23:59:59.000Z

186

Solubility measurement of uranium in uranium-contaminated soils  

SciTech Connect

A short-term equilibration study involving two uranium-contaminated soils at the Fernald site was conducted as part of the In Situ Remediation Integrated Program. The goal of this study is to predict the behavior of uranium during on-site remediation of these soils. Geochemical modeling was performed on the aqueous species dissolved from these soils following the equilibration study to predict the on-site uranium leaching and transport processes. The soluble levels of total uranium, calcium, magnesium, and carbonate increased continually for the first four weeks. After the first four weeks, these components either reached a steady-state equilibrium or continued linearity throughout the study. Aluminum, potassium, and iron, reached a steady-state concentration within three days. Silica levels approximated the predicted solubility of quartz throughout the study. A much higher level of dissolved uranium was observed in the soil contaminated from spillage of uranium-laden solvents and process effluents than in the soil contaminated from settling of airborne uranium particles ejected from the nearby incinerator. The high levels observed for soluble calcium, magnesium, and bicarbonate are probably the result of magnesium and/or calcium carbonate minerals dissolving in these soils. Geochemical modeling confirms that the uranyl-carbonate complexes are the most stable and dominant in these solutions. The use of carbonate minerals on these soils for erosion control and road construction activities contributes to the leaching of uranium from contaminated soil particles. Dissolved carbonates promote uranium solubility, forming highly mobile anionic species. Mobile uranium species are contaminating the groundwater underlying these soils. The development of a site-specific remediation technology is urgently needed for the FEMP site.

Lee, S.Y.; Elless, M.; Hoffman, F.

1993-08-01T23:59:59.000Z

187

Final Environmental assessment for the Uranium Lease Management Program  

SciTech Connect

The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE`s ``best interest`` is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI).

NONE

1995-07-01T23:59:59.000Z

188

Aluminosilicate Precipitation Impact on Uranium  

SciTech Connect

Experiments have been conducted to examine the fate of uranium during the formation of sodium aluminosilicate (NAS) when wastes containing high aluminate concentrations are mixed with wastes of high silicate concentration. Testing was conducted at varying degrees of uranium saturation. Testing examined typical tank conditions, e.g., stagnant, slightly elevated temperature (50 C). The results showed that under sub-saturated conditions uranium is not removed from solution to any large extent in both simulant testing and actual tank waste testing. This aspect was not thoroughly understood prior to this work and was necessary to avoid criticality issues when actual tank wastes were aggregated. There are data supporting a small removal due to sorption of uranium on sites in the NAS. Above the solubility limit the data are clear that a reduction in uranium concentration occurs concomitant with the formation of aluminosilicate. This uranium precipitation is fairly rapid and ceases when uranium reaches its solubility limit. At the solubility limit, it appears that uranium is not affected, but further testing might be warranted.

WILMARTH, WILLIAM

2006-03-10T23:59:59.000Z

189

METHOD OF SEPARATING URANIUM SUSPENSIONS  

DOE Patents (OSTI)

A process is presented for separating colloidally dissed uranium oxides from the heavy water medium in upwhich they are contained. The method consists in treating such dispersions with hydrogen peroxide, thereby converting the uranium to non-colloidal UO/sub 4/, and separating the UO/sub 4/ sfter its rapid settling.

Wigner, E.P.; McAdams, W.A.

1958-08-26T23:59:59.000Z

190

CX-003333: Categorical Exclusion Determination | Department of Energy  

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

333: Categorical Exclusion Determination 333: Categorical Exclusion Determination CX-003333: Categorical Exclusion Determination Reclamation Projects in Lease Tract C-G-26, Uranium Leasing Program CX(s) Applied: B1.28 Date: 07/30/2010 Location(s): Mesa County, Colorado Office(s): Legacy Management The U.S. Department Of Energy (DOE) Office of Legacy Management (LM) proposes to reclaim mining features associated with abandoned mines inherited by LM as a result of realigning lease tract boundaries in 2007. The activities include closing mine portals, filling subsided areas, and closing shafts and vents. Independent contractors associated with Energy Fuels Resources, the leaseholder, would complete all work in an estimated 1 week in 2010. The presence of these features constitute a public and wildlife safety concern. This lease tract is on Calamity Mesa, along the

191

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

192

METHOD OF ELECTROPLATING ON URANIUM  

DOE Patents (OSTI)

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

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

1959-04-28T23:59:59.000Z

193

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

194

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

195

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.

196

THE RECOVERY OF URANIUM FROM GAS MIXTURE  

DOE Patents (OSTI)

A method of separating uranium from a mixture of uranium hexafluoride and other gases is described that comprises bringing the mixture into contact with anhydrous calcium sulfate to preferentially absorb the uranium hexafluoride on the sulfate. The calcium sulfate is then leached with a selective solvent for the adsorbed uranium. (AEC)

Jury, S.H.

1964-03-17T23:59:59.000Z

197

Process for removing carbon from uranium  

DOE Patents (OSTI)

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

Powell, George L. (Oak Ridge, TN); Holcombe, Jr., Cressie E. (Knoxville, TN)

1976-01-01T23:59:59.000Z

198

APPENDIX J Partition Coefficients For Uranium  

E-Print Network (OSTI)

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

199

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

2011-06-18T23:59:59.000Z

200

FAQ 11-What are the properties of uranium hexafluoride?  

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

properties of uranium hexafluoride? What are the properties of uranium hexafluoride? Uranium hexafluoride can be a solid, liquid, or gas, depending on its temperature and pressure....

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.
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to obtain the most current and comprehensive results.


201

THE THEORY OF URANIUM ENRICHMENT BY THE GAS CENTRIFUGE  

E-Print Network (OSTI)

Soubbaramayer, (1979) in "Uranium Enrichment", S. Villani,and Davies, E. (1973) "Uranium Enrichment by Gas Centrifuge"THE THEORY OF URANIUM ENRICHMENT BY THE GAS CENTRIFUGE

Olander, Donald R.

2013-01-01T23:59:59.000Z

202

Production and Handling Slide 43: The Uranium Fuel Cycle  

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

Presentation Table of Contents The Uranium Fuel Cycle Refer to caption below for image description Enriched uranium hexafluoride, generally containing 3 to 5% uranium-235, is sent...

203

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

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

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

204

Summary Production Statistics of the U.S. Uranium Industry ...  

U.S. Energy Information Administration (EIA)

Domestic Uranium Production Report presents information Operating Status of U.S. Uranium Expenditures, 2003-2005. ... Mine Production of Uranium

205

FLUX COMPOSITION AND METHOD FOR TREATING URANIUM-CONTAINING METAL  

DOE Patents (OSTI)

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

Foote, F.

1958-08-26T23:59:59.000Z

206

THE THEORY OF URANIUM ENRICHMENT BY THE GAS CENTRIFUGE  

E-Print Network (OSTI)

Soubbaramayer, (1979) in "Uranium Enrichment", S. Villani,and Davies, E. (1973) "Uranium Enrichment by Gas Centrifuge"Nuclear Energy THE THEORY OF URANIUM ENRICHMENT BY THE GAS

Olander, Donald R.

2013-01-01T23:59:59.000Z

207

Proteogenomic monitoring of Geobacter physiology during stimulated uranium bioremediation  

E-Print Network (OSTI)

Phillips. 1992. Bioremediationof uraniumcontaminationwith enzymaticuraniumreduction. Environ. Sci. Microbial reduction of uranium. Nature350:413?416.

Wilkins, M.J.

2010-01-01T23:59:59.000Z

208

CALIFORNIUM ISOTOPES FROM BOMBARDMENT OF URANIUM WITH CARBON IONS  

E-Print Network (OSTI)

Isotopes from Bombardment of Uranium with Carbon Ions A.ISOTOPES FROM BOMBARDMENT OF URANIUM WITH CARBON IONS A.the irradiations, the uranium was dissolved in dilute

Ghiorso, A.; Thompson, S.G.; Street, K. Jr.; Seaborg, G.T.

2008-01-01T23:59:59.000Z

209

THE HIGH TEMPERATURE BEHAVIOR OF METALLIC INCLUSIONS IN URANIUM DIOXIDE.  

E-Print Network (OSTI)

Products in Irradiated Uranium Dioxide," UKAEA Report AERE-OF METALLIC INCLUSIONS IN URANIUM DIOXIDE Rosa Lu Yang (Chemical State of Irradiated Uranium- Plutonium Oxide Fuel

Yang, Rosa Lu.

2010-01-01T23:59:59.000Z

210

THE HIGH TEMPERATURE BEHAVIOR OF METALLIC INCLUSIONS IN URANIUM DIOXIDE.  

E-Print Network (OSTI)

State of Irradiated Uranium- Plutonium Oxide Fuel Pins,"Ingots Formed in Uranium-Plutonium Oxide Irradiated in EBR-Roake, "Fission Products and Plutonium Migration in Uranium-

Yang, Rosa Lu.

2010-01-01T23:59:59.000Z

211

ELECTRODEPOSITION OF NICKEL ON URANIUM  

SciTech Connect

Electrodeposited nickel coatings on uranium for protection from destructive corrosion in boiling water wns investigated. Correlation between the pretreatment of the uranium and subsequent protection by thin nickel coatings was established. Thin electrodeposited nickel coatings provide better protection when applied to a matte surface produced by blasting with an aqueous suspension of silica (100 mesh) followed by a cathodic treatment in 35 wt% sulfuric acid than when applied to the rough surfaces produced on uranium by anodic pretreatments and acid pickling. Blistering of nickel electrodeposits arising from hydrogen was encountered and eliminated. (auth)

Beard, A.P.; Crooks, D.D.

1954-08-31T23:59:59.000Z

212

SEPARATION OF URANIUM FROM THORIUM  

DOE Patents (OSTI)

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

Hellman, N.N.

1959-07-01T23:59:59.000Z

213

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

214

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,

215

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

216

2012 Domestic Uranium Production Report  

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

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

217

Depleted Uranium (DU) Dioxide Fill  

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

Fill Depleted Uranium (DU) Dioxide Fill DU dioxide in the form of sand may be used to fill the void spaces in the waste package after the package is loaded with SNF. This...

218

Beneficial Uses of Depleted Uranium  

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

Table 2 (ref. 1). The content of 235 U in DU is dependent on economics. If the cost of natural uranium feed is high relative to the cost of enrichment services, then a low 235 U...

219

LIQUID METAL COMPOSITIONS CONTAINING URANIUM  

DOE Patents (OSTI)

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

Teitel, R.J.

1959-04-21T23:59:59.000Z

220

METHOD OF DEHYDRATING URANIUM TETRAFLUORIDE  

DOE Patents (OSTI)

Drying and dehydration of aqueous-precipitated uranium tetrafluoride are described. The UF/sub 4/ which normally contains 3 to 4% water, is dispersed into the reaction zone of an operating reactor wherein uranium hexafluoride is being reduced to UF/sub 4/ with hydrogen. The water-containing UF/sub 4/ is dried and blended with the UF/sub 4/ produced in the reactor without interfering with the reduction reaction. (AEC)

Davis, J.O.; Fogel, C.C.; Palmer, W.E.

1962-12-18T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

SURFACE TREATMENT OF METALLIC URANIUM  

DOE Patents (OSTI)

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

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

1958-05-27T23:59:59.000Z

222

Laser induced phosphorescence uranium analysis  

DOE Patents (OSTI)

A method is described for measuring the uranium content of aqueous solutions wherein a uranyl phosphate complex is irradiated with a 5 nanosecond pulse of 425 nanometer laser light and resultant 520 nanometer emissions are observed for a period of 50 to 400 microseconds after the pulse. Plotting the natural logarithm of emission intensity as a function of time yields an intercept value which is proportional to uranium concentration.

Bushaw, B.A.

1983-06-10T23:59:59.000Z

223

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

224

Rescuing a Treasure Uranium-233  

SciTech Connect

Uranium-233 (233U) is a synthetic isotope of uranium formed under reactor conditions during neutron capture by natural thorium (232Th). At high purities, this synthetic isotope serves as a crucial reference for accurately quantifying and characterizing natural uranium isotopes for domestic and international safeguards. Separated 233U is stored in vaults at Oak Ridge National Laboratory. These materials represent a broad spectrum of 233U from the standpoint isotopic purity the purest being crucial for precise analyses in safeguarding uranium. All 233U at ORNL currently is scheduled to be down blended with depleted uranium beginning in 2015. Such down blending will permanently destroy the potential value of pure 233U samples as certified reference material for use in uranium analyses. Furthermore, no replacement 233U stocks are expected to be produced in the future due to a lack of operating production capability and the high cost of returning to operation this currently shut down capability. This paper will describe the efforts to rescue the purest of the 233U materials arguably national treasures from their destruction by down blending.

Krichinsky, Alan M [ORNL; Goldberg, Dr. Steven A. [DOE SC - Chicago Office; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL)

2011-01-01T23:59:59.000Z

225

PROCESS FOR PRODUCING URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

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

Fowler, R.D.

1957-10-22T23:59:59.000Z

226

SOLVENT EXTRACTION PROCESS FOR URANIUM RECOVERY  

DOE Patents (OSTI)

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

Clark, H.M.; Duffey, D.

1958-06-17T23:59:59.000Z

227

Process for alloying uranium and niobium  

DOE Patents (OSTI)

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

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

1990-12-31T23:59:59.000Z

228

Available Technologies: Cost-effective Recovery of Uranium ...  

Uranium contamination of groundwater is an environmental problem at many DOE facilities and at uranium mining/processing sites.

229

U.S. Uranium Expenditures, 2003-2010  

U.S. Energy Information Administration (EIA)

Domestic Uranium Production Report presents information Operating Status of U.S. Uranium Expenditures, 2003-2005

230

U.S. mine production of uranium, 1993-2011  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel, nuclear reactors, generation, spent fuel. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites ...

231

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.

232

Uranium Tris-aryloxide Derivatives Supported by Triazacyclononane: Engendering a Reactive Uranium(III)  

E-Print Network (OSTI)

Uranium Tris-aryloxide Derivatives Supported by Triazacyclononane: Engendering a Reactive Uranium-mail: kmeyer@ucsd.edu Abstract: The synthesis and spectroscopic characterization of the mononuclear uranium complex [((ArO)3tacn)UIII (NCCH3)] is reported. The uranium(III) complex reacts with organic azides

Meyer, Karsten

233

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

234

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

235

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 

236

COLORIMETRIC DETERMINATION OF URANIUM(IV)  

SciTech Connect

A colorimetric method was developed for the determination of uranium(IV) in the presence of uranium(VI), nitric acid, hydroxylamine sulfate, and hydrazine. A coefficient of variation of 2.4% (n = 25) was obtained. (auth)

Dorsett, R.S.

1961-05-01T23:59:59.000Z

237

Uranium Management and Policy | Department of Energy  

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

Uranium Management and Policy Uranium Management and Policy The Paducah Gaseous Diffusion Plant is located 3 miles south of the Ohio River and is 12 miles west of Paducah,...

238

Draft Uranium Leasing Program Programmatic Environmental Impact...  

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

five times the uranium concentration; this ratio was selected on the basis of the mining production rate of vanadium versus that of uranium. The RfCs used in the calculation were...

239

U.S. Department of Energy Office of Legacy Management National Environmental Policy Act Environmental Checklist  

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

I.D. # LM 27-10 U.S. Department of Energy Office of Legacy Management National Environmental Policy Act Environmental Checklist Project/Activity: Reclamation Projects in Lease Tract C-G-26, Uranium Leasing Program A. Brief Proj ect/ Activity Description The U.S. Department Of Energy (DOE) Office of Legacy Management (LM) proposes to reclaim mining features associated with abandoned mines inherited by LM as a result of realigning lease tract boundaries in 2007. The activities include closing mine portals, filling subsided areas, and closing shafts and vents. Independent contractors associated with Energy Fuels Resources, the leaseholder, would complete all work in an estimated 1 week in 2010. The presence of these features constitute a public and wildlife safety concern. This

240

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 "tract c-g-26 uranium" 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 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

242

INHERENTLY SAFE IN SITU URANIUM RE OVERY  

Nuclear power and waste opportunities contact us at Mining operations Increased safety of uranium removal Environmentally friendly process

243

Molecular Mechanisms of Uranium Reduction by Clostridia  

SciTech Connect

The objective of this research is to elucidate systematically the molecular mechanisms involved in the reduction of uranium by Clostridia.

Francis, A.J.; Matin, A.C.; Gao, W.; Chidambaram, D.; Barak, Y.; Dodge, C.J.

2006-04-05T23:59:59.000Z

244

PROCESS FOR THE RECOVERY OF URANIUM  

DOE Patents (OSTI)

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

Morris, G.O.

1955-06-21T23:59:59.000Z

245

Domestic Uranium Production Report - Quarterly - Energy ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites U.S. ...

246

Highly Enriched Uranium Transparency Program | National Nuclear...  

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

Highly Enriched Uranium Transparency Program | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

247

Uranium Weapons Components Successfully Dismantled | National...  

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

Uranium Weapons Components Successfully Dismantled | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

248

Bacterial Community Succession During in situ Uranium Bioremediation: Spatial Similarities Along Controlled Flow Paths  

E-Print Network (OSTI)

uranium reduction in uranium mine sediment. Appl Environspp. can be stimulated in uranium mine sediments (Suzuki et

Hwang, Chiachi

2009-01-01T23:59:59.000Z

249

Safe Operating Procedure SAFETY PROTOCOL: URANIUM  

E-Print Network (OSTI)

bodies depleted by uranium solution extraction and which remain underground do not constitute byproductEPA Update: NESHAP Uranium Activities Reid J. Rosnick Environmental Protection Agency Radiation Protection Division (6608J) Washington, DC 20460 NMA/NRC Uranium Recovery Workshop July 2, 2009 #12

Farritor, Shane

250

Controlling uranium reactivity March 18, 2008  

E-Print Network (OSTI)

. Redistribution of depleted uranium (DU soils and water at two US Army proving grounds. Ann. M Health Phys. SocRemediation of uranium contaminated soils with bicarbonate extraction and microbial U(VI) reduction ElizabethJ.P.Phillips, Edward R. Landa and DerekR. Lovley Key words: Bioremediation; Uranium; Mill tailings

Meyer, Karsten

251

The Uranium Institute 24th Annual Symposium  

E-Print Network (OSTI)

:same as iron. 3.2 Preparation A standard analysis of the depleted uranium,provided by COGEMA, is given-sur-Tille, France Abstract : After reviewing briefly the influence of the incorporationof vanadium in the uranium,nickel and iron, on the properties of the uranium-0.2%vanadium alloys. Tensile tests at both ambient and elevated

Laughlin, Robert B.

252

Sustained Removal of Uranium From Contaminated Groundwater  

E-Print Network (OSTI)

approximately 5 mm in diameter by 5 mm tal/. Compositions measured ranged from depleted uranium oxide to mixtures of plutonium and depleted uranium oxide (MOX) and mixed oxides with small percentages of minor.1943 - - - Title: Resonant Ultrasound Spectroscopy Measurements of the Elastic Properties of Uranium

Lovley, Derek

253

PROCESS FOR SEPARATING URANIUM FISSION PRODUCTS  

DOE Patents (OSTI)

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

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

1959-03-10T23:59:59.000Z

254

High strength uranium-tungsten alloys  

SciTech Connect

Alloys of uranium and tungsten and a method for making the alloys. The amount of tungsten present in the alloys is from about 4 wt % to about 35 wt %. Tungsten particles are dispersed throughout the uranium and a small amount of tungsten is dissolved in the uranium.

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

1991-01-01T23:59:59.000Z

255

High strength uranium-tungsten alloy process  

SciTech Connect

Alloys of uranium and tungsten and a method for making the alloys. The amount of tungsten present in the alloys is from about 4 wt % to about 35 wt %. Tungsten particles are dispersed throughout the uranium and a small amount of tungsten is dissolved in the uranium.

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

1990-01-01T23:59:59.000Z

256

METHOD AND FLUX COMPOSITION FOR TREATING URANIUM  

DOE Patents (OSTI)

ABS>A flux composition is described fer use with molten uranium or uranium alloys. The flux consists of about 46 weight per cent calcium fiuoride, 46 weight per cent magnesium fluoride and about 8 weight per cent of uranium tetrafiuoride.

Foote, F.

1958-08-23T23:59:59.000Z

257

CATALYZED OXIDATION OF URANIUM IN CARBONATE SOLUTIONS  

DOE Patents (OSTI)

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

Clifford, W.E.

1962-05-29T23:59:59.000Z

258

Clean Air Act Requirements: Uranium Mill Tailings  

E-Print Network (OSTI)

EPA'S Clean Air Act Requirements: Uranium Mill Tailings Radon Emissions Rulemaking Reid J. Rosnick Presentation to Environmental Protection Agency Uranium Contamination Radiation Protection Division (6608J requirements for operating uranium mill tailings (Subpart W) Status update on Subpart W activities Outreach

259

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS  

E-Print Network (OSTI)

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS PI?ON RIDGE PROJECT MONTROSE COUNTY, COLORADO (EFRC) proposes to license, construct, and operate a conventional acid leach uranium and vanadium mill storage pad, and access roads. The mill is designed to process ore containing uranium and vanadium

260

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

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

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

262

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"

263

PROCESS FOR PRODUCTION OF URANIUM  

DOE Patents (OSTI)

A process is described for the production of uranium by the autothermic reduction of an anhydrous uranium halide with an alkaline earth metal, preferably magnesium One feature is the initial reduction step which is brought about by locally bringing to reaction temperature a portion of a mixture of the reactants in an open reaction vessel having in contact with the mixture a lining of substantial thickness composed of calcium fluoride. The lining is prepared by coating the interior surface with a plastic mixture of calcium fluoride and water and subsequently heating the coating in situ until at last the exposed surface is substantially anhydrous.

Crawford, J.W.C.

1959-09-29T23:59:59.000Z

264

METHOD OF PROTECTIVELY COATING URANIUM  

DOE Patents (OSTI)

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

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

1959-02-01T23:59:59.000Z

265

Selective leaching of uranium from uranium-contaminated soils  

SciTech Connect

Three soils and a sediment contaminated with uranium were used to determine the effectiveness of sodium carbonate and citric acid leaching to decontaminate or remove uranium to acceptable regulatory levels. The objective was to selectively extract uranium using a soil washing/extraction process without seriously degrading the soil`s physicochemical characteristics or generating a secondary waste form that would be difficult to manage and/or dispose of. Two of the soils were surface soils from the DOE facility formerly called the Feed Materials Production Center (FMPC) at Fernald, Ohio. One of the soils is from near the Plant 1 storage pad and the other soil was taken from near a waste incinerator used to burn low-level contaminated trash. The third soil was a surface soil from an area formally used as a landfarm for the treatment of spent oils at the Oak Ridge Y-12 Plant. The sediment sample was material sampled from a storm sewer sediment trap at the Oak Ridge Y-12 Plant. Uranium concentrations in the Fernald soils ranged from 450 to 550 {mu}g U/g of soil while the samples from the Y-12 Plant ranged from 150 to 200 {mu}g U/g of soil.

Francis, C.W.; Mattus, A.J.; Farr, L.L.; Lee, S.Y. [Oak Ridge National Lab., TN (United States); Elless, M.P. [Oak Ridge National Lab., TN (United States)]|[Oak Ridge Associated Universities, Inc., TN (United States)

1993-06-01T23:59:59.000Z

266

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

SciTech Connect

Electron backscatter diffraction (EBSD) was used to examine the microstructures of unalloyed uranium, U-6Nb, U-10Mo, and U-0.75Ti. For unalloyed uranium, we used EBSD to examine the effects of various processes on microstructures including casting, rolling and forming, recrystallization, welding, and quasi-static and shock deformation. For U-6Nb we used EBSD to examine the microstructural evolution during shape memory loading. EBSD was used to study chemical homogenization in U-10Mo, and for U-0.75Ti, we used EBSD to study the microstructure and texture evolution during thermal cycling and deformation. The studied uranium alloys have significant microstructural and chemical differences and each of these alloys presents unique preparation challenges. Each of the alloys is prepared by a sequence of mechanical grinding and polishing followed by electropolishing with subtle differences between the alloys. U-6Nb and U-0.75Ti both have martensitic microstructures and both require special care in order to avoid mechanical polishing artifacts. Unalloyed uranium has a tendency to rapidly oxidize when exposed to air and a two-step electropolish is employed, the first step to remove the damaged surface layer resulting from the mechanical preparation and the second step to passivate the surface. All of the alloying additions provide a level of surface passivation and different one and two step electropolishes are employed to create good EBSD surfaces. Because of its low symmetry crystal structure, uranium exhibits complex deformation behavior including operation of multiple deformation twinning modes. EBSD was used to observe and quantify twinning contributions to deformation and to examine the fracture behavior. Figure 1 shows a cross section of two mating fracture surfaces in cast uranium showing the propensity of deformation twinning and intergranular fracture largely between dissimilarly oriented grains. Deformation of U-6Nb in the shape memory regime occurs by the motion of twin boundaries formed during the martensitic transformation. Deformation actually results in a coarsening of the microstructure making EBSD more practical following a limited amount of strain. Figure 2 shows the microstructure resulting from 6% compression. Casting of U-10Mo results in considerable chemical segregation as is apparent in Figure 2a. The segregation subsists through rolling and heat treatment processes as shown in Figure 2b. EBSD was used to study the effects of homogenization time and temperature on chemical heterogeneity. It was found that times and temperatures that result in a chemically homogeneous microstructure also result in a significant increase in grain size. U-0.75Ti forms an acicular martinsite as shown in Figure 4. This microstructure prevails through cycling into the higher temperature solid uranium phases.

McCabe, Rodney J. [Los Alamos National Laboratory; Kelly, Ann Marie [Los Alamos National Laboratory; Clarke, Amy J. [Los Alamos National Laboratory; Field, Robert D. [Los Alamos National Laboratory; Wenk, H. R. [University of California, Berkeley

2012-07-25T23:59:59.000Z

267

Isotopic ratio method for determining uranium contamination  

SciTech Connect

The presence of high concentrations of uranium in the subsurface can be attributed either to contamination from uranium processing activities or to naturally occurring uranium. A mathematical method has been employed to evaluate the isotope ratios from subsurface soils at the Rocky Flats Nuclear Weapons Plant (RFP) and demonstrates conclusively that the soil contains uranium from a natural source and has not been contaminated with enriched uranium resulting from RFP releases. This paper describes the method used in this determination which has widespread application in site characterizations and can be adapted to other radioisotopes used in manufacturing industries. The determination of radioisotope source can lead to a reduction of the remediation effort.

Miles, R.E.; Sieben, A.K.

1994-02-03T23:59:59.000Z

268

Uranium mill monitoring for natural fission reactors  

SciTech Connect

Isotopic monitoring of the product stream from operating uranium mills is proposed for discovering other possible natural fission reactors; aspects of their occurrence and discovery are considered. Uranium mill operating characteristics are formulated in terms of the total uranium capacity, the uranium throughput, and the dilution half-time of the mill. The requirements for detection of milled reactor-zone uranium are expressed in terms of the dilution half-time and the sampling frequency. Detection of different amounts of reactor ore with varying degrees of /sup 235/U depletion is considered.

Apt, K.E.

1977-12-01T23:59:59.000Z

269

Process for alloying uranium and niobium  

SciTech Connect

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

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

1991-01-01T23:59:59.000Z

270

Removal of uranium from aqueous HF solutions  

DOE Patents (OSTI)

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

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

1980-01-01T23:59:59.000Z

271

Method for producing uranium atomic beam source  

DOE Patents (OSTI)

A method for producing a beam of neutral uranium atoms is obtained by vaporizing uranium from a compound UM.sub.x heated to produce U vapor from an M boat or from some other suitable refractory container such as a tungsten boat, where M is a metal whose vapor pressure is negligible compared to that of uranium at the vaporization temperature. The compound, for example, may be the uranium-rhenium compound, URe.sub.2. An evaporation rate in excess of about 10 times that of conventional uranium beam sources is produced.

Krikorian, Oscar H. (Danville, CA)

1976-06-15T23:59:59.000Z

272

Removal of uranium from aqueous HF solutions  

Science Conference Proceedings (OSTI)

This invention is a simple and effective method for removing uranium from aqueous HF solutions containing trace quantities of the same. The method comprises contacting the solution with particulate calcium fluoride to form uranium-bearing particulates, permitting the particulates to settle, and separating the solution from the settled particulates. The CaF2 is selected to have a nitrogen surface area in a selected range and is employed in an amount providing a calcium fluoride/uranium weight ratio in a selected range. As applied to dilute HF solutions containing 120 ppm uranium, the method removes at least 92% of the uranium without introducing contaminants to the product solution.

Pulley, H.; Seltzer, S.F.

1980-11-18T23:59:59.000Z

273

Domestic utility attitudes toward foreign uranium supply  

SciTech Connect

The current embargo on the enrichment of foreign-origin uranium for use in domestic utilization facilities is scheduled to be removed in 1984. The pending removal of this embargo, complicated by a depressed worldwide market for uranium, has prompted consideration of a new or extended embargo within the US Government. As part of its on-going data collection activities, Nuclear Resources International (NRI) has surveyed 50 domestic utility/utility holding companies (representing 60 lead operator-utilities) on their foreign uranium purchase strategies and intentions. The most recent survey was conducted in early May 1981. A number of qualitative observations were made during the course of the survey. The major observations are: domestic utility views toward foreign uranium purchase are dynamic; all but three utilities had some considered foreign purchase strategy; some utilities have problems with buying foreign uranium from particular countries; an inducement is often required by some utilities to buy foreign uranium; opinions varied among utilities concerning the viability of the domestic uranium industry; and many utilities could have foreign uranium fed through their domestic uranium contracts (indirect purchases). The above observations are expanded in the final section of the report. However, it should be noted that two of the observations are particularly important and should be seriously considered in formulation of foreign uranium import restrictions. These important observations are the dynamic nature of the subject matter and the potentially large and imbalanced effect the indirect purchases could have on utility foreign uranium procurement.

1981-06-01T23:59:59.000Z

274

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"

275

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-

276

METHOD OF PURIFYING URANIUM METAL  

DOE Patents (OSTI)

The removal of lmpurities from uranlum metal can be done by a process conslstlng of contacting the metal with liquid mercury at 300 icient laborato C, separating the impunitycontalnlng slag formed, cooling the slag-free liquld substantlally below the point at which uranlum mercurlde sollds form, removlng the mercury from the solids, and recovering metallic uranium by heating the solids.

Blanco, R.E.; Morrison, B.H.

1958-12-23T23:59:59.000Z

277

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

278

Uranium Trace Elements Erik Hunter  

E-Print Network (OSTI)

be made. The electroscope relied upon the ability of the gamma radiation emitted by the sample to ionize that prove anomalous in the field can be subjected to more accurate tests in the lab that will determine #12;associated with the device was reported to be +/- 4% of the actual uranium content in the sample

279

Status of domestic uranium industry  

Science Conference Proceedings (OSTI)

The domestic uranium industry continues to operate at a reduced level, due to low prices and increased foreign competition. For four years (1984-1987) the Secretary of Energy declared the industry to be nonviable. A similar declaration is expected for 1988. Exploration and development drilling, at the rate of 2 million ft/year, continue in areas of producing mines and recent discoveries, especially in northwestern Arizona, northwestern Nebraska, south Texas, Wyoming, and the Paradox basin of Colorado and Utah. Production of uranium concentrate continues at a rate of 13 to 15 million lb of uranium oxide (U{sub 3}O{sub 8}) per year. Conventional mining in New Mexico, Arizona, Utah, Colorado, Wyoming, and Texas accounts for approximately 55% of the production. The remaining 45% comes from solution (in situ) mining, from mine water recovery, and as by-products from copper production and the manufacture of phosphoric acid. Solution mining is an important technique in Wyoming, Nebraska, and Texas. By-product production comes from phosphate plants in Florida and Louisiana and a copper mine in Utah. Unmined deposits in areas such as the Grants, New Mexico, district are being investigated for their application to solution mining technology. The discovered uranium resources in the US are quite large, and the potential to discover additional resources is excellent. However, higher prices and a strong market will be necessary for their exploitation.

Chenoweth, W.L.

1989-09-01T23:59:59.000Z

280

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

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

Inherently safe in situ uranium recovery.  

SciTech Connect

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

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

2009-05-01T23:59:59.000Z

282

Inherently safe in situ uranium recovery.  

SciTech Connect

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

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

2009-05-01T23:59:59.000Z

283

URANIUM RECOVERY, URANIUM GEOCHEMISTRY, THERMOLUMINESCENCE AND RELATED STUDIES. Final Report  

SciTech Connect

The recovery of urantum at the mine with portable equipment was shown to be feasible, using a process which involves grinding the ore, leaching with nitric acid, extracting with tributyl phosphate and kerosene, and precipitation with ammonia gas. The system is more expensive than a stationary plant but couid be used in an emergency or in difficulty accessible locations. The distribution of uranium was studied in various geographical locations and in several different materials including limestones, granites, clays, rivers and underground water, lignites, and volcanic ash and lavas. Geochemical studies, based on thermoluminescence, including stratigraphy, age determinations of limestones, and aragonite-calcite relations in calcium csrbonate are presented along with thermoluminescence studies of lithium fluoride, alkali halides, aluminum oxides, sulfates, and other inorganic salts and minerals. Radiation damage to lithium fluoride and metamixed minerals was studied, and apparatus was developed for measuring thermoluminescence of crystals exposed to gamma radiation, scintillameters for measuring alpha particle activity in materials containing a trace of uranium, and an analytical method for determining less than 1 part per million uranium. (J.R.D.)

Daniels, F.

1957-11-01T23:59:59.000Z

284

Table 4.10 Uranium Reserves, 2008 (Million Pounds Uranium Oxide)  

U.S. Energy Information Administration (EIA)

money. The forward costs used to estimate U.S. uranium ore reserves are independent of the price at which uranium produced from the estimated reserves might be sold ...

285

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

286

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

287

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"

288

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"

289

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"

290

:- : 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

291

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. _________________________

292

Measurement of Trace Uranium Isotopes  

Science Conference Proceedings (OSTI)

The extent to which thermal ionization mass spectrometry (TIMS) can measure trace quantities of 233U and 236U in the presence of a huge excess of natural uranium is evaluated. This is an important nuclear non-proliferation measurement. Four ion production methods were evaluated with three mass spectrometer combinations. The most favorable combinations are not limited by abundance sensitivity; rather, the limitations are the ability to generate a uranium ion beam of sufficient intensity to obtain the required number of counts on the minor isotopes in relationship to detector background. The most favorable situations can measure isotope ratios in the range of E10 if sufficient sample intensity is available. These are the triple sector mass spectrometer with porous ion emitters (PIE) and the single sector mass spectrometer with energy filtering.

Matthew G. Watrous; James E. Delmore

2011-05-01T23:59:59.000Z

293

Depleted uranium disposal options evaluation  

SciTech Connect

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

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

1994-05-01T23:59:59.000Z

294

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:

295

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.

296

Uranium Metal Analysis via Selective Dissolution  

DOE Green Energy (OSTI)

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

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

2008-09-10T23:59:59.000Z

297

PROCESS FOR THE PRODUCTION OF URANIUM TETRAFLUORIDE FROM URANIUM RAW MATERIAL  

SciTech Connect

This process consists oi the following steps: dissolving and leaching uranium raw material with sulfuric acid, adding a tetravalent uranium solution obtained by electrolytic reduction to the leach, subjecting the leach exuded by suifuric acid to an extraction with an organic solvent to refine and concentrate uranium, converting the extract to a tetravalent uranous solution by electrolytic reduction, and reacting hydrogen fluoride with the uranous solution to produce uranium tetrafluoride. (R.J.S.)

Ito, C.; Okuda, T.; Hamabe, N.

1962-11-20T23:59:59.000Z

298

PRETREATING URANIUM FOR METAL PLATING  

DOE Patents (OSTI)

A process is given for anodically treating the surface of uranium articles, prior to metal plating. The metal is electrolyzed in an aqueous solution of about 10% polycarboxylic acid, preferably oxalic acid, from 1 to 5% by weight of glycerine and from 1 to 5% by weight of hydrochloric acid at from 20 to 75 deg C for from 30 seconds to 15 minutes. A current density of from 60 to 100 amperes per square foot is used.

Wehrmann, R.F.

1961-05-01T23:59:59.000Z

299

2011 Uranium Marketing Annual Report - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Uranium Feed, Enrichment Services, Uranium Loaded In 2011, COOs delivered 51 million pounds U 3 O 8 e of natural uranium feed to U.S. and foreign enrichers. Fifty-

300

Production and Handling Slide 23: The Uranium Fuel Cycle  

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

Presentation Table of Contents The Uranium Fuel Cycle Refer to caption below for image description The fourth major step in the uranium fuel cycle is uranium enrichment. Slide 23...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

FAQ 9-Where does uranium hexafluoride come from?  

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

hexafluoride come from? Where does uranium hexafluoride come from? The gaseous diffusion process used to enrich uranium requires uranium in the form of UF6. In the first step of...

302

Health Effects Associated with Uranium Hexafluoride (UF6)  

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

Hexafluoride (UF6) UF6 Health Effects Uranium Hexafluoride (UF6) line line Properties of UF6 UF6 Health Effects Health Effects Associated with Uranium Hexafluoride (UF6) Uranium...

303

Think Uranium. Think Y-12 | Y-12 National Security Complex  

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

Think Uranium. Think Y-12 Think Uranium. Think Y-12 Posted: July 22, 2013 - 3:12pm | Y-12 Report | Volume 10, Issue 1 | 2013 Uranium fever: Much like the California gold rush of...

304

Dry process fluorination of uranium dioxide using ammonium bifluoride  

E-Print Network (OSTI)

An experimental study was conducted to determine the practicality of various unit operations for fluorination of uranium dioxide. The objective was to prepare ammonium uranium fluoride double salts from uranium dioxide and ...

Yeamans, Charles Burnett, 1978-

2003-01-01T23:59:59.000Z

305

Hexavalent uranium supports growth of Anaeromyxobacter dehalogenans and Geobacter spp.  

E-Print Network (OSTI)

Hexavalent uranium supports growth of Anaeromyxobacter dehalogenans and Geobacter spp. with lower cultures, there are problems associated with absolute quantification due to the presence of uranium (FRC) near Oak Ridge, TN, and several isolates have recently been obtained from uranium

Löffler, Frank E.

306

METHOD OF PRODUCING URANIUM METAL BY ELECTROLYSIS  

DOE Patents (OSTI)

A process is given for making uranium metal from oxidic material by electrolytic deposition on the cathode. The oxidic material admixed with two moles of carbon per one mole of uranium dioxide forms the anode, and the electrolyte is a mixture of from 40 to 75% of calcium fluoride or barium fluoride, 15 to 45% of uranium tetrafluoride, and from 10 to 20% of lithium fluoride or magnesium fluoride; the temperature of the electrolyte is between 1150 and 1175 deg C. (AEC)

Piper, R.D.

1962-09-01T23:59:59.000Z

307

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

308

METHOD FOR THE REDUCTION OF URANIUM COMPOUNDS  

DOE Patents (OSTI)

An improved technique of preparing massive metallic uranium by the reaction at elevated temperature between an excess of alkali in alkaline earth metal and a uranium halide, such ss uranium tetrafluoride is presented. The improvement comprises employing a reducing atmosphere of hydrogen or the like, such as coal gas, in the vessel during the reduction stage and then replacing the reducing atmosphere with argon gas prior to cooling to ambient temperature.

Cooke, W.H.; Crawford, J.W.C.

1959-05-12T23:59:59.000Z

309

PROCESS FOR PRODUCTION OF URANIUM HEXAFLUORIDE  

DOE Patents (OSTI)

A process is described for the manufacture of uranium bexafluoride which consists in contacting an oxide of uranium simultaneously with elemental carbon and elemental fluorine at an elevated temperature, using a proportion of the carbon to the oxide about 50% in excess of that theoretically required to combine with f the oxygen as C0/.sub 2/. The process has the advantage that the uranium oxide is reduced by tbe carbon aad converted to the hexafluoride in a single operation.

Fowler, R.D.

1958-11-01T23:59:59.000Z

310

ELECTROCHEMICAL DECONTAMINATION AND RECOVERY OF URANIUM VALUES  

DOE Patents (OSTI)

An electrochemical process is described for separating uranium from fission products. The method comprises subjecting the mass of uranium to anodic dissolution in an electrolytic cell containing aqueous alkali bicarbonate solution as its electrolyte, thereby promoting a settling from the solution of a solid sludge from about the electrodes and separating the resulting electrolyte solution containing the anodically dissolved uranium from the sludge which contains the rare earth fission products.

McLaren, J.A.; Goode, J.H.

1958-05-13T23:59:59.000Z

311

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).

312

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

313

SEPARATION OF URANIUM, PLUTONIUM AND FISSION PRODUCTS FROM NEUTRON- BOMBARDED URANIUM  

DOE Patents (OSTI)

A process is given for removing plutonium and/or fission products from uranium fuel. The fuel is dissolved in molten zinc--magnesium (10 to 18% Mg) alloy, more magnesium is added to obtain eutectic composition whereby uranium precipitates, and the uranium are separated from the Plutoniumand fission-product- containing eutectic. (AEC)

Martin, A.E.; Johnson, I.; Burris, L. Jr.; Winsch, I.O.; Feder, H.M.

1962-11-13T23:59:59.000Z

314

SEPARATION OF URANIUM, PLUTONIUM AND FISSION PRODUCTS  

DOE Patents (OSTI)

The separation of uranium and plutonium from neutronirradiated uranium is described. The neutron-irradiated uranium is dissolved in nitric acid to provide an aqueous solution 3N in nitric acid. The fission products of the solution are extruded by treating the solution with dibutyl carbitol substantially 1.8N in nitric acid. The organic solvent phase is separated and neutralized with ammonium hydroxide and the plutonium reduced with hydroxylamine base to the trivalent state. Treatment of the mixture with saturated ammonium nitrate extracts the reduced plutonium and leaves the uranium in the organic solvent.

Nicholls, C.M.; Wells, I.; Spence, R.

1959-10-13T23:59:59.000Z

315

Uranium Certified Reference Materials Price List  

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

Safety & Health spacer Office of Science Chicago Office - New Brunswick Laboratory Uranium Certified Reference Materials Price List Return to Price List Page NOTE: These costs...

316

Structural Sequestration of Uranium in Bacteriogenic Manganese...  

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

Highlightsbanner Structural Sequestration of Uranium in Bacteriogenic Manganese Oxides Samuel M. Webb (Stanford Synchrotron Radiation Laboratory), Bradley M. Tebo (Oregon Health...

317

SORPTION OF URANIUM ON ZIRCONIUM OXIDE  

SciTech Connect

The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solutions. Conclusions are drawn concerning the relationship between each of these factors and uranium sorption. (auth)

Goldstein, G.

1961-09-13T23:59:59.000Z

318

Unique Uranium Source in Naturally Bioreduced Sediment  

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

| 2006 | 2005 2004 | 2003 | 2002 | 2001 2000 Subscribe to APS News rss feed Unique Uranium Source in Naturally Bioreduced Sediment DECEMBER 2, 2009 Bookmark and Share Scanning...

319

Roadmap to the Project: Uranium Miners Resources  

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

suggested revisions of criteria for the compensation of lung cancer among underground uranium miners from the eligible regions of the U.S. Radioactive radon (more specifically...

320

WEB RESOURCE: Some Physics of Uranium - TMS  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... This online primer offers a general overview of the chemistry of uranium, with particular reference to nuclear reactors. Graphs and images are...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

Uranium Downblending and Disposition Project Technology Readiness...  

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

Simulated Operational Environment Environment that uses a range of waste simulants for testing of a virtual prototype. iv 233 Uranium Downblending and Disposition Project...

322

Uranium Weapons Components Successfully Dismantled | National...  

National Nuclear Security Administration (NNSA)

NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Uranium Weapons Components Successfully...

323

Domestic Uranium Production Report - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Short-Term Energy Outlook Annual Energy Outlook ... The EIA data covered approximately 200 uranium properties with reserve estimates, collected from 1984 through ...

324

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

325

Distribution of uranium-bearing phases in soils from Fernald  

SciTech Connect

Electron beam techniques have been used to characterize uranium-contaminated soils and the Fernald Site, Ohio. Uranium particulates have been deposited on the soil through chemical spills and from the operation of an incinerator plant on the site. The major uranium phases have been identified by electron microscopy as uraninite, autunite, and uranium phosphite [U(PO{sub 3}){sub 4}]. Some of the uranium has undergone weathering resulting in the redistribution of uranium within the soil.

Buck, E.C.; Brown, N.R.; Dietz, N.L.

1993-12-31T23:59:59.000Z

326

High strength and density tungsten-uranium alloys  

DOE Patents (OSTI)

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

Sheinberg, Haskell (Los Alamos, NM)

1993-01-01T23:59:59.000Z

327

Audit Report on "Depleted Uranium Hexafluoride Conversion," DOE...  

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

Marketing Administration Other Agencies You are here Home Audit Report on "Depleted Uranium Hexafluoride Conversion," DOEIG-0642 Audit Report on "Depleted Uranium Hexafluoride...

328

Uranium Leasing Program Draft PEIS Public Comment Period Extended...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Uranium Leasing Program Draft PEIS Public Comment Period Extended to May 31, 2013 Uranium...

329

DOE Extends Public Comment Period for Uranium Program Environmental...  

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

Other Agencies You are here Home DOE Extends Public Comment Period for Uranium Program Environmental Impact Statement DOE Extends Public Comment Period for Uranium...

330

Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751...  

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

Marketing Administration Other Agencies You are here Home Follow-up of Depleted Uranium Hexafluoride Conversion, IG-0751 Follow-up of Depleted Uranium Hexafluoride...

331

Depleted Uranium Operations at the Y-12 National Security Complex...  

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

Sites Power Marketing Administration Other Agencies You are here Home Depleted Uranium Operations at the Y-12 National Security Complex, G-0570 Depleted Uranium Operations...

332

Borehole Logging Methods for Exploration and Evaluation of Uranium...  

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

You are here Home Borehole Logging Methods for Exploration and Evaluation of Uranium Deposits (1967) Borehole Logging Methods for Exploration and Evaluation of Uranium...

333

SALE OF ENRICHED URANIUM AT THE FERNALD ENVIRONMENTAL MANAGEMENT...  

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

Power Marketing Administration Other Agencies You are here Home SALE OF ENRICHED URANIUM AT THE FERNALD ENVIRONMENTAL MANAGEMENT PROJECT, IG-0496 SALE OF ENRICHED URANIUM AT...

334

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

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

Agencies You are here Home Secretarial Determination for the Sale or Transfer of Uranium Secretarial Determination for the Sale or Transfer of Uranium Secretarial...

335

EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel...  

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

Sites Power Marketing Administration Other Agencies You are here Home EIS-0472: Uranium Leasing Program, Mesa, Montrose, and San Miguel Counties, Colorado EIS-0472: Uranium...

336

Production and Handling Slide 37: The Uranium Fuel Cycle  

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

Table of Contents The Uranium Fuel Cycle Refer to caption below for image description The enrichment process generates two streams of uranium hexafluoride, one enriched in...

337

FAQ 12-What are the hazards associated with uranium hexafluoride...  

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

hazards associated with uranium hexafluoride? What are the hazards associated with uranium hexafluoride? The characteristics of UF6 pose potential health risks, and the material is...

338

uranium hexafluoride - U.S. Energy Information Administration (EIA)  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... UF 6 is the form of uranium required for the enrichment process. Thank You.

339

Decommissioning of U.S. Uranium Production Facilities  

Reports and Publications (EIA)

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

Information Center

1995-02-01T23:59:59.000Z

340

Production and Handling Slide 1: The Uranium Fuel Cycle  

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

and Handling The Uranium Fuel Cycle Skip Presentation Navigation Next Slide Last Presentation Table of Contents The Uranium Fuel Cycle Refer to caption below for image...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

FAQ 14-What does a depleted uranium hexafluoride cylinder look...  

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

depleted uranium hexafluoride cylinder look like? What does a depleted uranium hexafluoride cylinder look like? A picture is worth a thousand words The pictures below show typical...

342

Production and Handling Slide 5: The Uranium Fuel Cycle  

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

Refer to caption below for image description The third step in the uranium fuel cycle involves the conversion of "yellowcake" to uranium hexafluoride (UF6), the chemical form...

343

Production and Handling Slide 2: Natural Uranium and its Ores...  

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

Uranium and its Ores* Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Natural Uranium and its Ores* Refer to caption below...

344

CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Criticality Safety - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix...

345

CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Safety Basis - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to...

346

CRAD, Management - Y-12 Enriched Uranium Operations Oxide Conversion...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Management - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to DOE...

347

CRAD, Training - Y-12 Enriched Uranium Operations Oxide Conversion...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Training - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to DOE G...

348

CRAD, Conduct of Operations - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Conduct of Operations - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

349

CRAD, Occupational Safety & Health - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Occupational Safety & Health - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

350

CRAD, DOE Oversight - Y-12 Enriched Uranium Operations Oxide...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, DOE Oversight - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to...

351

CRAD, Environmental Protection - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Environmental Protection - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

352

CRAD, Radiological Controls - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Radiological Controls - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

353

DOE - Office of Legacy Management -- Falls City Uranium Ore Stockpile...  

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

Uranium Ore Stockpile - TX 04A FUSRAP Considered Sites Site: Falls City Uranium Ore Stockpile (TX.04A ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations:...

354

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

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

Legacy Management Work Progresses on Defense-Related Uranium Mines Report to Congress Legacy Management Work Progresses on Defense-Related Uranium Mines Report to Congress October...

355

Y-12 uranium storage facility?a dream come true?  

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

ranks and actually provides the first impedance for the just finished highly enriched uranium storage facility. Recently the Highly Enriched Uranium Material Facility was...

356

Researchers use light to create rare uranium molecule  

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

to create rare uranium molecule Uranium nitride materials show promise as advanced nuclear fuels due to their high density, high stability, and high thermal conductivity. July...

357

CRAD, Emergency Management - Y-12 Enriched Uranium Operations...  

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

Emergency Management - Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Emergency Management - Y-12 Enriched Uranium Operations Oxide Conversion Facility January...

358

Guidelines for Leasing State Highway Right of Way Tracts | Open...  

Open Energy Info (EERE)

Search Page Edit with form History Facebook icon Twitter icon Guidelines for Leasing State Highway Right of Way Tracts Jump to: navigation, search GEOTHERMAL ENERGYGeothermal...

359

Uranium and Aluminosilicate Surface Precipitation Tests  

SciTech Connect

The 2H evaporator at the Savannah River Site has been used to treat an aluminum-rich waste stream from canyon operations and a silicon-rich waste stream from the Defense Waste Processing Facility. The formation of aluminosilicate scale in the evaporator has caused significant operational problems. Because uranium has been found to accumulate in the aluminosilicate solids, the scale deposition has introduced criticality concerns as well. The objective of the tests described in this report is to determine possible causes of the uranium incorporation in the evaporator scale materials. The scope of this task is to perform laboratory experiments with simulant solutions to determine if (1) uranium can be deposited on the surfaces of various sodium aluminosilicate (NAS) forms and (2) aluminosilicates can form on the surfaces of uranium-containing solids. Batch experiments with simulant solutions of three types were conducted: (1) contact of uranium solutions/sols with NAS coatings on stainless steel surfaces, (2) contact of uranium solutions with NAS particles, and (3) contact of precipitated uranium-containing particles with solutions containing aluminum and silicon. The results show that uranium can be incorporated in NAS solids through encapsulation in bulk agglomerated NAS particles of different phases (amorphous, zeolite A, sodalite, and cancrinite) as well as through heterogeneous deposition on the surfaces of NAS coatings (amorphous and cancrinite) grown on stainless steel. The results also indicate that NAS particles can grow on the surfaces of precipitated uranium solids. Particularly notable for evaporator operations is the finding that uranium solids can form on existing NAS scale, including cancrinite solids. If NAS scale is present, and uranium is in sufficient concentration in solution to precipitate, a portion of the uranium can be expected to become associated with the scale. The data obtained to date on uranium-NAS affinity are qualitative. A necessary next step is to quantitatively determine the amounts of uranium that may be incorporated into NAS scale solids under differing conditions e.g., varying silicon/aluminum ratio, uranium concentration, temperature, and deposition time.

Hu, M.Z.

2002-11-27T23:59:59.000Z

360

Final report: Research project chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes  

SciTech Connect

This report discusses the development of an etchant composition to chemically mill counterbore recesses in each end of the uranium walls of Zircaloy-2 clad uranium tubes.

Atkins, D.C. [United States Chemical Milling Corp., Manhattan Beach, CA (United States)

1994-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.
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to obtain the most current and comprehensive results.


361

A PILOT PLANT FOR THE REDUCTION OF URANIUM HEXAFLUORIDE TO URANIUM TETRAFLUORIDE WITH TRICHLOROETHYLENE  

SciTech Connect

Pilot plant experiments are described in which trichloroethylene was used for the reduction of uranium hexafluoride to uranium tetrafluoride. After unsatisfactory preliminary results with liquid phase reduction, satisfactory results were obtained with a vapor phase reduction system. It was found that vapor phase reduction at approximately 450 deg F, produced a low density product which contained only small quantities of uranium(VI); sintering the uranium tetrafluoride in a hydrogen fluoride atmosphere increased the product density to approximately 3 g/cc. The reduction was essentially complete, and the effluent gas contained less than 1 ppm of uranium hexafluoride. The purity of the uranium tetrafluoride produced was equivalent to that of the uranium hexafluoride used as feed. A complete discussion is given of the operation of the various parts of the system. (auth)

Baker, J.E.; Klaus, H.V.; Schmidt, R.A.; Smiley, S.H.

1956-05-31T23:59:59.000Z

362

MECHANISMS AND KINETICS OF URANIUM CORROSION AND URANIUM CORE FUEL ELEMENT RUPTURES IN WATER AND STEAM  

DOE Green Energy (OSTI)

The mechanisms and kinetics of uranium corrosion and fuel element ruptures were investigated in water and steam at 170 to 500 deg C and at 100 to 2800 psig. The fuel element samples were coextruded Zircaloy-clad uranium-core rods and tubes which were defected prior to exposure. Uranium corrosion was found to be the sum of two processes; direct oxidation by water, and oxidation of uranium hydride intermediate. Fuel element ruptures occur in two stages; an initial induction period followed by an accelerating corrosion of the core causing the cladding to blister, swell, and fracture. Uranium corrosion and fuel element ruptures were examined with respect to temperature, pressure, steam versus liquid water, heat treatment, carbon content of uranium, zirconium content of uranium, cladding thickness, fuel geometry, annular spacings, defect geometry and size, coolant flow, hydriding of Zircaloy components, and irradiation effects. (auth)

Troutner, V.H.

1960-07-21T23:59:59.000Z

363

Bioremediation of uranium contaminated soils and wastes  

SciTech Connect

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

Francis, A.J.

1998-12-31T23:59:59.000Z

364

Microbial uptake of uranium, cesium, and radium  

SciTech Connect

The ability of diverse microbial species to concentrate uranium, cesium, and radium was examined. Saccharomyces cerevisiae, Pseudomonas aeruginosa, and a mixed culture of denitrifying bacteria accumulated uranium to 10 to 15% of the dry cell weight. Only a fraction of the cells in a given population had visible uranium deposits in electron micrographs. While metabolism was not required for uranium uptake, mechanistic differences in the metal uptake process were indicated. Uranium accumulated slowly (hours) on the surface of S. cerevisiae and was subject to environmental factors (i.e., temperature, pH, interfering cations and anions). In contrast, P. aeruginosa and the mixed culture of denitrifying bacteria accumulated uranium rapidly (minutes) as dense, apparently random, intracellular deposits. This very rapid accumulation has prevented us from determining whether the uptake rate during the transient between the initial and equilibrium distribution of uranium is affected by environmental conditions. However, the final equilibrium distributions are not affected by those conditions which affect uptake by S. cerevisiae. Cesium and radium were concentrated to a considerably lesser extent than uranium by the several microbial species tested. The potential utility of microorganisms for the removal and concentration of these metals from nuclear processing wastes and several bioreactor designs for contacting microorganisms with contaminated waste streams will be discussed.

Strandberg, G.W.; Shumate, S.E. II; Parrott, J.R. Jr.; McWhirter, D.A.

1980-01-01T23:59:59.000Z

365

Uranium Exploration Report 2007 Cottonwood District, Utah  

E-Print Network (OSTI)

, undertook several field trips to determine the state of the uranium mining industry in Colorado and Utah. These field trips included active mines, abandoned mines, and active mills. Samples from some of the minesMNGN 599 Uranium Exploration Report 2007 Cottonwood District, Utah Erik Hunter Colorado School

366

HOT PRESSING TO FORM CANNED URANIUM SLUGS  

DOE Patents (OSTI)

A method of making compacts and cladded slugs from powdered uranium is described. The powdered uranium is introduced into a die and subjected to pressures of 30 to 100 tsi while maintaining a temperature within the range of 450 to 660 deg C.

Roboff, S.B.; Kingston, W.E.

1961-07-25T23:59:59.000Z

367

PRODUCTION OF URANIUM AND THORIUM COMPOUNDS  

DOE Patents (OSTI)

Compounds of Th and U are extracted with an organic solvent in the presence of an adsorbent substance which has greater retentivity for impurities present than for the uranium and/or thorium. The preferred adsorbent material is noted as being cellulose. The uranium and thoriumcontaining substances treated are preferably in the form of dissolved nitrates, and the preferred organic solvent is diethyl ether.

Arden, T.V.; Burstall, F.H.; Linstead, R.P.; Wells, R.A.

1955-12-27T23:59:59.000Z

368

Uranium Management - Preservation of a National Asset  

Science Conference Proceedings (OSTI)

The Uranium Management Group (UMG) was established at the Department of Energy's (DOE's) Oak Ridge Operations in 1999 as a mechanism to expedite the de-inventory of surplus uranium from the Fernald Environmental Management Project site. This successful initial venture has broadened into providing uranium material de-inventory and consolidation support to the Hanford site as well as retrieving uranium materials that the Department had previously provided to universities under the loan/lease program. As of December 31, 2001, {approx} 4,300 metric tons of uranium (MTU) have been consolidated into a more cost effective interim storage location at the Portsmouth site near Piketon, OH. The UMG continues to uphold its corporate support mission by promoting the Nuclear Materials Stewardship Initiative (NMSI) and the twenty-five (25) action items of the Integrated Nuclear Materials Management Plan (1). Before additional consolidation efforts may commence to remove excess inventory from Environmental Management closure sites and universities, a Programmatic Environmental Assessment (PEA) must be completed. Two (2) noteworthy efforts currently being pursued involve the investigation of re-use opportunities for surplus uranium materials and the recovery of usable uranium from the shutdown Portsmouth cascade. In summary, the UMG is available as a DOE complex-wide technical resource to promote the responsible management of surplus uranium.

Jackson, J. D.; Stroud, J. C.

2002-02-27T23:59:59.000Z

369

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

370

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

371

Page not found | Department of Energy  

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

71 - 16480 of 28,905 results. 71 - 16480 of 28,905 results. Download CX-004797: Categorical Exclusion Determination 3M Columbia Solar Film Date: 12/22/2010 Location(s): Columbia, Missouri Office(s): Energy Efficiency and Renewable Energy, Golden Field Office http://energy.gov/nepa/downloads/cx-004797-categorical-exclusion-determination Download CX-004739: Categorical Exclusion Determination Evaluation of Wilcox Geothermal Reservoir and Demonstration of Geothermal Energy Production -Phase 1 CX(s) Applied: A9, B3.1 Date: 12/14/2010 Location(s): Texas Office(s): Energy Efficiency and Renewable Energy, Golden Field Office http://energy.gov/nepa/downloads/cx-004739-categorical-exclusion-determination Download CX-003488: Categorical Exclusion Determination New Verde Mine Investigations, Lease Tract C-G-26, Uranium Leasing Program

372

Colorado | Department of Energy  

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

10, 2010 10, 2010 CX-003490: Categorical Exclusion Determination Install Monitoring Wells at Slick Rock West, Colorado, Processing Site CX(s) Applied: B3.1 Date: 08/10/2010 Location(s): Slick Rock, Colorado Office(s): Legacy Management August 10, 2010 CX-003488: Categorical Exclusion Determination New Verde Mine Investigations, Lease Tract C-G-26, Uranium Leasing Program CX(s) Applied: B1.28, B3.1 Date: 08/10/2010 Location(s): Mesa County, Colorado Office(s): Legacy Management August 5, 2010 COLORADO RECOVERY ACT SNAPSHOT The American Recovery & Reinvestment Act (ARRA) is making a meaningful down payment on the nation's energy and environmental future. The Recovery Act investments in Colorado are supporting a broad range of clean energy projects, from energy efficiency and the smart grid to solar power and

373

Diagnosis of In Situ Metabolic State and Rates of Microbial Metabolism During In Situ Uranium Bioremediation with Molecular Techniques  

Science Conference Proceedings (OSTI)

The goal of these projects was to develop molecule tools to tract the metabolic activity and physiological status of microorganisms during in situ uranium bioremediation. Such information is important in able to design improved bioremediation strategies. As summarized below, the research was highly successful with new strategies developed for estimating in situ rates of metabolism and diagnosing the physiological status of the predominant subsurface microorganisms. This is a first not only for groundwater bioremediation studies, but also for subsurface microbiology in general. The tools and approaches developed in these studies should be applicable to the study of microbial communities in a diversity of soils and sediments.

Lovley, Derek R.

2012-11-28T23:59:59.000Z

374

Uranium Pyrophoricity Phenomena and Prediction  

Science Conference Proceedings (OSTI)

We have compiled a topical reference on the phenomena, experiences, experiments, and prediction of uranium pyrophoricity for the Hanford Spent Nuclear Fuel Project (SNFP) with specific applications to SNFP process and situations. The purpose of the compilation is to create a reference to integrate and preserve this knowledge. Decades ago, uranium and zirconium fires were commonplace at Atomic Energy Commission facilities, and good documentation of experiences is surprisingly sparse. Today, these phenomena are important to site remediation and analysis of packaging, transportation, and processing of unirradiated metal scrap and spent nuclear fuel. Our document, bearing the same title as this paper, will soon be available in the Hanford document system [Plys, et al., 2000]. This paper explains general content of our topical reference and provides examples useful throughout the DOE complex. Moreover, the methods described here can be applied to analysis of potentially pyrophoric plutonium, metal, or metal hydride compounds provided that kinetic data are available. A key feature of this paper is a set of straightforward equations and values that are immediately applicable to safety analysis.

DUNCAN, D.R.

2000-04-20T23:59:59.000Z

375

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.

376

EPA Uranium Program Update Loren W. Setlow and  

E-Print Network (OSTI)

30, 2008 #12;2 Overview EPA Radiation protection program Uranium reports and abandoned mine lands and Liability Act #12;4 Uranium Reports and Abandoned Mine Lands Program ·Technologically Enhanced Naturally Abandoned Uranium Mines (Final released April 2008) ·Uranium Location Database (August 2006) · Compilation

377

2012 Uranium Survey Form Proposals - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, ... Office of Management and Budget, ... Environment Markets & Finance Today in Energy. Geography

378

DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID  

DOE Patents (OSTI)

A method of dissolving and separating uranium from a uranium matrix fuel element by dissolving the uraniumcontaining matrix in monofluorophosphoric acid and/or difluorophosphoric acid at temperatures ranging from 150 to 275 un. Concent 85% C, thereafter neutralizing the solution to precipitate uranium solids, and converting the solids to uranium hexafluoride by treatment with a halogen trifluoride is presented. (AEC)

Johnson, R.; Horn, F.L.; Strickland, G.

1963-05-01T23:59:59.000Z

379

Technical Basis for Assessing Uranium Bioremediation Performance  

SciTech Connect

In situ bioremediation of uranium holds significant promise for effective stabilization of U(VI) from groundwater at reduced cost compared to conventional pump and treat. This promise is unlikely to be realized unless researchers and practitioners successfully predict and demonstrate the long-term effectiveness of uranium bioremediation protocols. Field research to date has focused on both proof of principle and a mechanistic level of understanding. Current practice typically involves an engineering approach using proprietary amendments that focuses mainly on monitoring U(VI) concentration for a limited time period. Given the complexity of uranium biogeochemistry and uranium secondary minerals, and the lack of documented case studies, a systematic monitoring approach using multiple performance indicators is needed. This document provides an overview of uranium bioremediation, summarizes design considerations, and identifies and prioritizes field performance indicators for the application of uranium bioremediation. The performance indicators provided as part of this document are based on current biogeochemical understanding of uranium and will enable practitioners to monitor the performance of their system and make a strong case to clients, regulators, and the public that the future performance of the system can be assured and changes in performance addressed as needed. The performance indicators established by this document and the information gained by using these indicators do add to the cost of uranium bioremediation. However, they are vital to the long-term success of the application of uranium bioremediation and provide a significant assurance that regulatory goals will be met. The document also emphasizes the need for systematic development of key information from bench scale tests and pilot scales tests prior to full-scale implementation.

PE Long; SB Yabusaki; PD Meyer; CJ Murray; AL NGuessan

2008-04-01T23:59:59.000Z

380

DETERMINATION OF TETRAVALENT URANIUM IN THORIUM OXIDE-URANIUM OXIDE MIXTURES. PARTS I, II, AND III  

SciTech Connect

For the determination of milligram quantities of uranium(N) in thorium oxide-uranium oxide mixtures which may also contain uranium(VI), it was necessary to devise a means of dissolving the sample so as to prevent any air oxidation of the uranium(IV) to uranium(VI). For this determination, the conventional potassium dichromate volumetric method was used except that the sample was dissolved under reflux in 7 M H/sub 3/PO/sub 4/ which contained an excess of standard dichromate solution. Following the dissolution of the sample, this excess was determined by back titration with a standard solution of iron(II). Barium diphenylaminesulfonate was used as the indicator. Initial tests on the dissolution of samples of thorium oxide-uranium oxide in hot HC1O/sub 4/ and hot HCI are described. (auth)

Menis, O.

1959-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

EIS-0293: Transfer of Land Tracts Located at Los Alamos National...  

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

293: Transfer of Land Tracts Located at Los Alamos National Laboratory, New Mexico EIS-0293: Transfer of Land Tracts Located at Los Alamos National Laboratory, New Mexico Summary...

382

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

383

Over 90% of uranium purchased by U.S. commercial nuclear reactors ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors ... and enrichment. EIA's 2010 Uranium Marketing Annual Report presents data on purchases and sales of uranium contracts and ...

384

FAQ 25-What are the options for managing depleted uranium in...  

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

options for managing depleted uranium in the future? What are the options for managing depleted uranium in the future? The options for managing depleted uranium were evaluated in...

385

Sulfur isotopes as indicators of amended bacterial sulfate reduction processes influencing field scale uranium bioremediation  

E-Print Network (OSTI)

in situ bioremediation of uranium in a highly contaminatedwith bioremediation of uranium to submicromolar levels.Reoxidation of bioreduced uranium under reducing conditions.

Druhan, J.L.

2009-01-01T23:59:59.000Z

386

Magnetic Exchange Coupling and Single-Molecule Magnetism in Uranium Complexes  

E-Print Network (OSTI)

method for interpreting uranium magnetism and will becontaining lower-valent uranium centers can be seen to1995. Chapter 4: Tetranuclear Uranium Clusters via Reductive

Rinehart, Jeffrey Dennis

2010-01-01T23:59:59.000Z

387

Hexavalent uranium diffusion into soils from concentrated acidic and alkaline solutions  

E-Print Network (OSTI)

Chemical Thermodynamics of Uranium, Neptunium, Plutonium,Hexavalent Uranium Diffusion into Soils from Concentratedtktokunaga@lbl.gov) Abstract Uranium contamination of soils

Tokunaga, Tetsu K.; Wan, Jiamin; Pena, Jasquelin; Sutton, Stephen R.; Newville, Matthew

2004-01-01T23:59:59.000Z

388

Electrodic voltages accompanying stimulated bioremediation of a uranium-contaminated aquifer  

E-Print Network (OSTI)

2002), In-situ evidence for uranium immobilization andheterogeneity in an in situ uranium bioremediation fieldin situ bioremediation of uranium in a highly contaminated

Williams, K.H.

2010-01-01T23:59:59.000Z

389

Stability of uranium incorporated into Fe(hydr)oxides under fluctuating redox conditions  

E-Print Network (OSTI)

for Bioremediation of uranium-contaminated aquifers withReoxidation of bioreduced uranium under reducing conditions.Komlos, J. ; Jaffe, P. R. Uranium reoxidation in previously

Stewart, B.D.

2009-01-01T23:59:59.000Z

390

Behavior of Uranium(VI) during HEDPA Leaching for Aluminum Dissolution in Tank Waste Sludges  

E-Print Network (OSTI)

Behavior of Uranium(VI) during HEDPA Leaching for Aluminuman increase in the aqueous phase uranium concentration.The concentration of uranium continually increased over 59

Powell, Brian A.; Rao, Linfeng; Nash, Kenneth L.; Martin, Leigh

2006-01-01T23:59:59.000Z

391

Detection of hexavalent uranium with inline and field-portable immunosensors  

E-Print Network (OSTI)

Detection of hexavalent uranium with inline and field-form of hexavalent uranium was used in the developmentdifferent immunosensors for uranium detection. Specifically,

Melton, Scott J.

2009-01-01T23:59:59.000Z

392

Incorporation of oxidized uranium into Fe (hydr)oxides during Fe(II) catalyzed remineralization  

E-Print Network (OSTI)

B. M. ; Geesey, G. G. Uranium complexes formed at hematiteheterogeneity in an in situ uranium bioremediation fieldL. R. In-situ evidence for uranium immobilization and

Nico, Peter S.

2010-01-01T23:59:59.000Z

393

Uranium-series comminution ages of continental sediments: Case study of a Pleistocene alluvial fan  

E-Print Network (OSTI)

and river transport. Uranium-Series Geochemistry 52, 533-using high- precision uranium isotopic measurements.B. , Turner, S.P. , 2008. Uranium-series isotopes in river

Lee, Victoria E.

2010-01-01T23:59:59.000Z

394

Composition, stability, and measurement of reduced uranium phases for groundwater bioremediation at Old Rifle, CO  

E-Print Network (OSTI)

subsurface bioreduction in a uranium-contaminated aquifer.and measurement of reduced uranium phases for groundwaterGeobacter species to remove uranium from the groundwater of

Campbell, K.M.

2013-01-01T23:59:59.000Z

395

Decolonizing cartographies : sovereignty, territoriality, and maps of meaning in the uranium landscape  

E-Print Network (OSTI)

Figure 8 Colorado Plateau uranium district, Life magazine in146! Figure 12 Navajo Nation and uranium industry162! Figure 14 An undated poster protesting uranium

Voyles, Traci Brynne

2010-01-01T23:59:59.000Z

396

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

E-Print Network (OSTI)

Lemaire, Selective concentration of uranium from seawater byfor exploration of uranium. Reaktortagung, 7th (1975), 307-Germany. 41. H. G. Bals, Uranium extraction from seawater.

Rao, Linfeng

2011-01-01T23:59:59.000Z

397

In-well sediment incubators to evaluate microbial community stability and dynamics following bioimmobilization of uranium  

E-Print Network (OSTI)

D. R. (1992). Enzymatic uranium precipitation. Environmentalof technetium and uranium in a nitrate-contaminated aquifer.in situ bioremediation of uranium-contaminated groundwater.

Baldwin, B.R.

2010-01-01T23:59:59.000Z

398

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

E-Print Network (OSTI)

data_request/cif. OECD, Uranium 2009: Resources, Productionthermodynamics of uranium, (H. Wanner and I. Forest,of California. Sequestering uranium from seawater: binding

Tian, Guoxin

2013-01-01T23:59:59.000Z

399

Electrolytic process for preparing uranium metal  

SciTech Connect

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

Haas, Paul A. (Knoxville, TN)

1990-01-01T23:59:59.000Z

400

SEPARATION OF THORIUM FROM URANIUM BY EXTRACTION  

DOE Patents (OSTI)

A method is presented for the recovery and separation of uranium and thorium values contained in an aqueous nitric acid solution which is more than 3 M in nitric acid. The uranium and thorium containing solution preferable about 7 M in nitric acid is contacted with tributyl phosphatekerosene mixture. Both U and Th are extracted by the immiscible organic. After phase separation the Th is selectively back extracted by contacting with an aqueous nitric acid solution preferably between 0.1 to 1.5 M in nitric acid. The uranium which is still in the organic extractant phase may be recovered by contacting with water.

Bohlmann, E.G.

1959-07-28T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

METHOD OF SEPARATING URANIUM FROM ALLOYS  

DOE Patents (OSTI)

Uranium can be recovered from metallic uraniumthorium mixtures containing uranium in comparatively small amounts. The method of recovery comprises adding a quantity of magnesium to a mass to obtain a content of from 48 to 85% by weight; melting and forming a magnesium-thorium alloy at a temperature of between 585 and 800 deg C; agitating the mixture, allowing the mixture to settle whereby two phases, a thorium-containing magnesium-rich liquid phase and a solid uranium-rich phase, are formed; and separating the two phases.

Chiotti, P.; Shoemaker, H.E.

1960-06-28T23:59:59.000Z

402

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

403

L'URANIUM ET LES ARMES L'URANIUM APPAUVRI. Pierre Roussel*  

E-Print Network (OSTI)

(depleted uranium) · 4 oxidation states (+4, +6 most common) · U(VI) water-soluble, U(IV) in-soluble Metals Uranium ­ heaviest natural element - 17 isotopes · Natural form % = U-238 (99.27), U-235 (0.72), U-234 (0 in nuclear fuel ­ U-235 (readily fissionable) · Used in nuclear and conventional weapons · Uranium enrichment

Paris-Sud XI, Université de

404

PROCESS FOR PRODUCING URANIUM HALIDES  

DOE Patents (OSTI)

A process amd associated apparatus for producing UF/sub 4/ from U/sub 3/ O/sub 8/ by a fluidized'' technique are reported. The U/sub 3/O/sub 8/ is first reduced to UO/sub 2/ by reaction with hydrogen, and the lower oxide of uranium is then reacted with gaseous HF to produce UF/sub 4/. In each case the reactant gas is used, alone or in combination with inert gases, to fluidize'' the finely divided reactant solid. The complete setup of the plant equipment including bins, reactor and the associated piping and valving, is described. An auxiliary fluorination reactor allows for the direct production of UF/sub 6/ from UF/sub 4/ and fluorine gas, or if desired, UF/sub 4/ may be collected as the product.

Murphree, E.V.

1957-10-29T23:59:59.000Z

405

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.

406

Dissolving uranium oxide--aluminum fuel  

SciTech Connect

The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for dissolving this type of enriched uranium fuel at the Savannah River Plant. The studies also included the dissolution of a similar material prepared from scrap uranium oxides that were to be recycled through the solvent extraction process. The dissolving behavior of uranium oxide-aluminum core material is similar to that of U-Al alloy. Dissolving rates are rapid in HNO/sub 3/-Hg(NO/sub 3/)/sub 2/ solutions. Irradiation reduce s the dissolving rate and increases mechanical strength. A dissolution model for use in nuclear safety analyses is developed, . based on the observed dissolving characteristics. (auth)

Perkins, W.C.

1973-11-01T23:59:59.000Z

407

Uranium Marketing Annual Report - Energy Information Administration  

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

Uranium Marketing Annual Report Uranium Marketing Annual Report With Data for 2012 | Release Date: May 16, 2013 | Next Release Date: May 2014 | full report Previous uranium marketing annual reports Year: 2011 2010 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1998 1997 1996 1995 1994 1993 1992 Go Uranium purchases and prices Owners and operators of U.S. civilian nuclear power reactors ("civilian owner/operators" or "COOs") purchased a total of 58 million pounds U3O8e (equivalent1) of deliveries from U.S. suppliers and foreign suppliers during 2012, at a weighted-average price of $54.99 per pound U3O8e. The 2012 total of 58 million pounds U3O8e increased 5 percent compared with the 2011 total of 55 million pounds U3O8e. The 2012 weighted-average price of

408

It's Elemental - Isotopes of the Element Uranium  

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

Periodic Table of Elements Next Element (Neptunium) Neptunium Isotopes of the Element Uranium Click for Main Data Most of the isotope data on this site has been obtained from...

409

Remediation of Uranium-Contaminated Ground Water  

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

The shallow alluvial aquifer at Fry Canyon, Utah, is contaminated with up to 17 mgL uranium leached from processed tailings at an ore upgrader processing plant that was operated...

410

PROCESSES OF RECLAIMING URANIUM FROM SOLUTIONS  

DOE Patents (OSTI)

A process is described for reclaiming residual enriched uranium from calutron wash solutions containing Fe, Cr, Cu, Ni, and Mn as impurities. The solution is adjusted to a pH of between 2 and 4 and is contacted with a metallic reducing agent, such as iron or zinc, in order to reduce the copper to metal and thereby remove it from the solution. At the same time the uranium present is reduced to the uranous state The solution is then contacted with a precipitate of zinc hydroxide or barium carbonate in order to precipitate and carry uranium, iron, and chromium away from the nickel and manganese ions in the solution. The uranium is then recovered fronm this precipitate.

Zumwalt, L.R.

1959-02-10T23:59:59.000Z

411

Interim Report on Uranium Metal Segregation Testing  

SciTech Connect

This report describes the preliminary results of laboratory and bench-scale vendor testing to evaluate the effectiveness of the gravity mineral concentration technology for removing and concentrating uranium metal from K Basin sludge.

Schmidt, Andrew J.; Elmore, Monte R.

2004-04-18T23:59:59.000Z

412

Innovative design of uranium startup fast reactors  

E-Print Network (OSTI)

Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic ...

Fei, Tingzhou

2012-01-01T23:59:59.000Z

413

Remedial actions at the former Climax Uranium Company, Uranium Mill site, Grand Junction, Mesa County, Colorado. Volume 1, Text: Final environmental impact statement  

SciTech Connect

This statement evaluates and compares the environmental impacts associated with the remedial actions of the residual radioactive materials remaining at the inactive uranium processing site and associated vicinity properties at Grand Junction, Mesa County, Colorado. This statement is also intended to aid the BLM in amending their management framework plans and final resource management plan, as well as assisting in compliance with the withdrawal application as appropriate. The site is a 114-acre tract of private and state owned land which contains approximately 3.1 million cubic yards of tailings and associated contaminated soils. The vicinity properties are homes, businesses, public buildings, and vacant lots which may have been contaminated during construction by the use of tailings as building material. An estimated 3465 vicinity properties would be cleaned up during remedial action of the tailings pile. The tailings were produced by the former Climax Uranium Company which processed uranium ore, which it sold to the US Atomic Energy Commission from 1951 to 1966 and to private sources from 1966 to 1970. This statement evaluates six alternatives for stabilization and disposal of the tailings and other contaminated materials: (1) No action. (2) Stabilization at the Grand Junction site. (3) Disposal at the Cheney Reservoir site with truck transport. (4) Disposal at the Cheney Reservoir site with train and truck transport. (5) Disposal at the Two Road site with truck transport. (6) Disposal at the Two Road site with train and truck transport. All of the alternatives except no action include remedial action at an estimated 3465 vicinity properties. Alternative 3 is DOE`s preferred alternative.

None

1986-12-01T23:59:59.000Z

414

Uranium enrichment in the United States  

SciTech Connect

History, improvement programs, status of electrical power availability, demands for uranium enrichment, operating plan for the U. S. enriching facilities, working inventory of enriched uranium, possible factors affecting deviations in the operating plan, status of gaseous diffusion technology, status of U. S. gas centrifuge advances, transfer of enrichment technology, gaseous diffusion--gas centrifuge comparison, new enrichment capacity, U. S. separative work pricing, and investment in nuclear energy are discussed. (LK)

Hill, J.H.; Parks, J.W.

1975-01-01T23:59:59.000Z

415

Stream sediment geochemical surveys for uranium  

SciTech Connect

Stream sediment is more universally available than ground and surface waters and comprises the bulk of NURE samples. Orientation studies conducted by the Savannah River Laboratory indicate that several mesh sizes can offer nearly equivalent information. Sediment is normally sieved in the field to pass a 420-micrometer screen (US Std. 40 mesh) and that portion of the dried sediment passing a 149-micrometer screen (US Std. 100 mesh) is recovered for analysis. Sampling densities usually vary with survey objectives and types of deposits anticipated. Principal geologic features that can be portrayed at a scale of 1:250,000, such as major tectonic units, plutons, and pegmatite districts, are readily defined using a sampling density of 1 site per 5 square miles (13 km/sup 2/). More detailed studies designed to define individual deposits require greater sampling density. Analyses for elements known to be associated with uranium in a particular mineral host may be used to estimate the relative proportion of uranium in several forms. For example, uranium may be associated with thorium and cerium in monazite, and with zirconium and hafnium in zircon. Readily leachable uranium may be adsorbed to trapped in oxide coatings on mineral particles. Soluble or mobile uranium may indicate an ore source, whereas uranium in monazite or zircon is not likely to be economically attractive. Various schemes may be used to estimate for form of uranium in a sample. Simple elemental ratios are a useful first approach. Multiple ratios and subtractive formulas empirically designed to account for the presence of particular minerals are more useful. Residuals calculated from computer-derived regression equations or factor scores appear to have the greatest potential for locating uranium anomalies.

Price, V.; Ferguson, R.B.

1979-01-01T23:59:59.000Z

416

BIOREMEDIATION OF URANIUM CONTAMINATED SOILS AND WASTES.  

SciTech Connect

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

FRANCIS,A.J.

1998-09-17T23:59:59.000Z

417

RECOVERY OF URANIUM BY SECONDARY XANTHATE COMPLEXING  

DOE Patents (OSTI)

A method is described for separating and recovering uranium values contained in an acidic aqueous solution together with thorium or protactinium values. In accordance with the invention, the acidic solution containing uranium in the uranyl form is contacted with an organic xanthate. The xanthate forms a urano-xanthate complex but is substantially non-reactive with thorium and protactinium. The urano-xanthate complex is recovered by organic solvent extraction.

Neville, O.K.

1959-09-01T23:59:59.000Z

418

Depleted uranium: A DOE management guide  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has a management challenge and financial liability in the form of 50,000 cylinders containing 555,000 metric tons of depleted uranium hexafluoride (UF{sub 6}) that are stored at the gaseous diffusion plants. The annual storage and maintenance cost is approximately $10 million. This report summarizes several studies undertaken by the DOE Office of Technology Development (OTD) to evaluate options for long-term depleted uranium management. Based on studies conducted to date, the most likely use of the depleted uranium is for shielding of spent nuclear fuel (SNF) or vitrified high-level waste (HLW) containers. The alternative to finding a use for the depleted uranium is disposal as a radioactive waste. Estimated disposal costs, utilizing existing technologies, range between $3.8 and $11.3 billion, depending on factors such as applicability of the Resource Conservation and Recovery Act (RCRA) and the location of the disposal site. The cost of recycling the depleted uranium in a concrete based shielding in SNF/HLW containers, although substantial, is comparable to or less than the cost of disposal. Consequently, the case can be made that if DOE invests in developing depleted uranium shielded containers instead of disposal, a long-term solution to the UF{sub 6} problem is attained at comparable or lower cost than disposal as a waste. Two concepts for depleted uranium storage casks were considered in these studies. The first is based on standard fabrication concepts previously developed for depleted uranium metal. The second converts the UF{sub 6} to an oxide aggregate that is used in concrete to make dry storage casks.

NONE

1995-10-01T23:59:59.000Z

419

Y-12 Knows Uranium | Y-12 National Security Complex  

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

Knows Uranium Knows Uranium Y-12 Knows Uranium Posted: July 22, 2013 - 3:45pm | Y-12 Report | Volume 10, Issue 1 | 2013 Y-12 produces many forms of uranium. They may be used in chemical processing steps on-site or shipped elsewhere to serve as raw materials for nuclear fuel or as research tools. All of uranium's uses, defense related and otherwise, are critical to the nation. Y-12's understanding of uranium, coupled with the site's work with enriched uranium metal, alloys, oxides, compounds and solutions, is unique in the Nuclear Security Enterprise. "The Y-12 work force understands both established uranium science and the esoteric things related to uranium's behavior," said engineer Alan Moore. "Such a deep, detailed understanding comes from experience,

420

URANIUM ALLOY POWDERS BY DIRECT REDUCTION OF OXIDES  

SciTech Connect

A process is outlined for the production of uranium alloy powders by co- reduction of mintures of uranium oxide and alloy element oxides. The reduction of mechanical mintures of the oxides of uranium and alloy element with calcium in a sealed reaction vessel is shown to produce powder wtth a variation in particle composition, although of consistert composition over various size fractions. The particular alloy systems which are considered are uranium--nickel, uranium-- chromium, uranium --molybdenum, and uranium--niobium. The uranium-molybdenum and uranium--niobium powders are single phase (metastable gamma), which is of consequence in the production of dimensionaHy stable nuclear fuels. Potential applications of some of these alloys are discussed. (auth)

Myers, R.H.; Robins, R.G.

1959-10-31T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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

Electrochemical method of producing eutectic uranium alloy and apparatus  

DOE Patents (OSTI)

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

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

1995-01-01T23:59:59.000Z

422

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

SciTech Connect

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

1995-07-05T23:59:59.000Z

423

DOE - Office of Legacy Management -- LASL Tract OO - NM 06  

Office of Legacy Management (LM)

Tract OO - NM 06 Tract OO - NM 06 FUSRAP Considered Sites Site: LASL TRACT OO (NM.06 ) Eliminated from consideration under FUSRAP - Site was released by the AEC for sale and unrestricted use in 1976 Designated Name: Not Designated Alternate Name: None Location: Los Alamos , New Mexico NM.06-1 Evaluation Year: 1987 NM.06-1 Site Operations: Site consists of an area of 3.85 acres on the Los Alamos Scientific Laboratory compound. This tract of land was a location for a fire alarm equipment building and part of power plant and several warehouses. NM.06-2 Site Disposition: Eliminated - Radiological survey report declares the area to be free of residual radioactive contamination from site operations NM.06-1 Radioactive Materials Handled: No Primary Radioactive Materials Handled: None

424

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.

425

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)

426

Assessing the Renal Toxicity of Capstone Depleted Uranium Oxides and Other Uranium Compounds  

SciTech Connect

The primary target for uranium toxicity is the kidney. The most frequently used guideline for uranium kidney burdens is the International Commission on Radiation Protection (ICRP) value of 3 g U/g kidney, a value that is based largely upon chronic studies in animals. In the present effort, we have developed a risk model equation to assess potential outcomes of acute uranium exposure. Twenty-seven previously published case studies in which workers were acutely exposed to soluble compounds of uranium (as a result of workplace accidents) were analyzed. Kidney burdens of uranium for these individuals were determined based on uranium in the urine, and correlated with health effects observed over a period of up to 38 years. Based upon the severity of health effects, each individual was assigned a score (- to +++) and then placed into an Effect Group. A discriminant analysis was used to build a model equation to predict the Effect Group based on the amount of uranium in the kidneys. The model equation was able to predict the Effect Group with 85% accuracy. The risk model was used to predict the Effect Group for Soldiers exposed to DU as a result of friendly fire incidents during the 1991 Gulf War. This model equation can also be used to predict the Effect Group of new cases in which acute exposures to uranium have occurred.

Roszell, Laurie E.; Hahn, Fletcher; Lee, Robyn B.; Parkhurst, MaryAnn

2009-02-26T23:59:59.000Z

427

Uranium removal from soils: An overview from the Uranium in Soils Integrated Demonstration program  

SciTech Connect

An integrated approach to remove uranium from uranium-contaminated soils is being conducted by four of the US Department of Energy national laboratories. In this approach, managed through the Uranium in Soils Integrated Demonstration program at the Fernald Environmental Management Project, Fernald, Ohio, these laboratories are developing processes that selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics or generating waste that is difficult to manage or dispose of. These processes include traditional uranium extractions that use carbonate as well as some nontraditional extraction techniques that use citric acid and complex organic chelating agents such as naturally occurring microbial siderophores. A bench-scale engineering design for heap leaching; a process that uses carbonate leaching media shows that >90% of the uranium can be removed from the Fernald soils. Other work involves amending soils with cultures of sulfur and ferrous oxidizing microbes or cultures of fungi whose role is to generate mycorrhiza that excrete strong complexers for uranium. Aqueous biphasic extraction, a physical separation technology, is also being evaluated because of its ability to segregate fine particulate, a fundamental requirement for soils containing high levels of silt and clay. Interactions among participating scientists have produced some significant progress not only in evaluating the feasibility of uranium removal but also in understanding some important technical aspects of the task.

Francis, C.W. [Oak Ridge National Lab., TN (United States); Brainard, J.R.; York, D.A. [Los Alamos National Lab., NM (United States); Chaiko, D.J. [Argonne National Lab., IL (United States); Matthern, G. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1994-09-01T23:59:59.000Z

428

Predicting 232U Content in Uranium  

SciTech Connect

The minor isotope 232U may ultimately be used for detection or confirmation of uranium in a variety of applications. The primary advantage of 232 U as an indicator of the presence of enriched uranium is the plentiful and penetrating nature of the radiation emitted by its daughter radionuclide 208Tl. A possible drawback to measuring uranium via 232U is the relatively high uncertainty in 232U abundance both within and between material populations. An important step in assessing this problem is to ascertain what determines the 232U concentration within any particular sample of uranium. To this end, we here analyze the production and eventual enrichment of 232 U during fuel-cycle operations. The goal of this analysis is to allow approximate prediction of 232 U quantities, or at least some interpretation of the results of 232U measurements. We have found that 232U is produced via a number of pathways during reactor irradiation of uranium and is subsequently concentrated during the later enrichment of the uranium' s 235U Content. While exact calculations are nearly impossible for both the reactor-production and cascade-enrichment parts of the prediction problem, estimates and physical bounds can be provided as listed below and detailed within the body of the report. Even if precise calculations for the irradiation and enrichment were possible, the ultimate 212U concentration would still depend upon the detailed fuel-cycle history. Assuming that a thennal-diffusion cascade is used to produce highly enriched uranium (HEU), dilution of reactor-processed fuel at the cascade input and the long-term holdup of 232U within the cascade both affect the 232U concentration in the product. Similar issues could be expected to apply for the other isotope-separation technologies that are used in other countries. Results of this analysis are listed below: 0 The 232U concentration depends strongly on the uranium enrichment, with depleted uranium (DU) containing between 1600 and 8000 times less 232U than HEU does. * The 236U/232U concentration ratio in HEU is likely to be between 10{sup 6} and 2 x 10{sup 7}. 0 Plutonium-production reactors yield uranium with between I and 10 ppt of 232u. 0 Much higher 132U concentrations can be obtained in some situations. * Significant variation in the 232U concentration is inevitable. * Cascade enrichment increases the 232U concentration by a factor of at least 200, and possibly as much as 1000. 0 The actual 232U concentration depends upon the dilution at the cascade input.

AJ Peurrung

1999-01-07T23:59:59.000Z

429

Predicting 232U Content in Uranium  

SciTech Connect

The minor isotope 232U may ultimately be used for detection or confirmation of uranium in a variety of applications. The primary advantage of 232 U as an indicator of the presence of enriched uranium is the plentiful and penetrating nature of the radiation emitted by its daughter radionuclide 208Tl. A possible drawback to measuring uranium via 232U is the relatively high uncertainty in 232U abundance both within and between material populations. An important step in assessing this problem is to ascertain what determines the 232U concentration within any particular sample of uranium. To this end, we here analyze the production and eventual enrichment of 232 U during fuel-cycle operations. The goal of this analysis is to allow approximate prediction of 232 U quantities, or at least some interpretation of the results of 232U measurements. We have found that 232U is produced via a number of pathways during reactor irradiation of uranium and is subsequently concentrated during the later enrichment of the uranium' s 235U Content. While exact calculations are nearly impossible for both the reactor-production and cascade-enrichment parts of the prediction problem, estimates and physical bounds can be provided as listed below and detailed within the body of the report. Even if precise calculations for the irradiation and enrichment were possible, the ultimate 212U concentration would still depend upon the detailed fuel-cycle history. Assuming that a thennal-diffusion cascade is used to produce highly enriched uranium (HEU), dilution of reactor-processed fuel at the cascade input and the long-term holdup of 232U within the cascade both affect the 232U concentration in the product. Similar issues could be expected to apply for the other isotope-separation technologies that are used in other countries. Results of this analysis are listed below: 0 The 232U concentration depends strongly on the uranium enrichment, with depleted uranium (DU) containing between 1600 and 8000 times less 232U than HEU does. * The 236U/232U concentration ratio in HEU is likely to be between 10{sup 6} and 2 x 10{sup 7}. 0 Plutonium-production reactors yield uranium with between I and 10 ppt of 232u. 0 Much higher 132U concentrations can be obtained in some situations. * Significant variation in the 232U concentration is inevitable. * Cascade enrichment increases the 232U concentration by a factor of at least 200, and possibly as much as 1000. 0 The actual 232U concentration depends upon the dilution at the cascade input.

AJ Peurrung

1999-01-07T23:59:59.000Z

430

Table S1a. Uranium Purchased by Owners and Operators of U.S ...  

U.S. Energy Information Administration (EIA)

U.S. Energy Information Administration / 2010 Uranium Marketing ... deliveries, domestic, enrichers, enriched uranium, enrichment, fabricators, feed, foreign, fuel ...

431

Decolonizing cartographies : sovereignty, territoriality, and maps of meaning in the uranium landscape  

E-Print Network (OSTI)

type deposits in the Ambrosia Lake uranium district. Thein form todeposits in the Ambrosia Lake uranium district),

Voyles, Traci Brynne

2010-01-01T23:59:59.000Z

432

URANIUM RECOVERY AND PURIFICATION PROCESS AND PRODUCTION OF HIGH PURITY URANIUM TETRAFLUORIDE  

DOE Patents (OSTI)

A process is described wherein an anionic exchange technique is employed to separate uramium from a large variety of impurities. Very efficient and economical purification of contamimated uranium can be achieved by treatment of the contaminated uranium to produce a solution containing a high concentration of chloride. Under these conditions the uranium exists as an aniomic chloride complex. Then the uranium chloride complex is adsorbed from the solution on an aniomic exchange resin, whereby a portion of the impurities remain in the solution and others are retained with the uramium by the resin. The adsorbed impurities are then removed by washing the resin with pure concentrated hydrochloric acid, after which operation the uranium is eluted with pure water yielding an acidic uranyl chloride solution of high purity.

Bailes, R.H.; Long, R.S.; Grinstead, R.R.

1957-09-17T23:59:59.000Z

433

Synthesis of uranium metal using laser-initiated reduction of uranium tetrafluoride by calcium metal  

SciTech Connect

Uranium metal has numerous uses in conventional weapons (armor penetrators) and nuclear weapons. It also has application to nuclear reactor designs utilizing metallic fuels--for example, the former Integral Fast Reactor program at Argonne National Laboratory. Uranium metal also has promise as a material of construction for spent-nuclear-fuel storage casks. A new avenue for the production of uranium metal is presented that offers several advantages over existing technology. A carbon dioxide (CO{sub 2}) laser is used to initiate the reaction between uranium tetrafluoride (UF{sub 4}) and calcium metal. The new method does not require induction heating of a closed system (a pressure vessel) nor does it utilize iodine (I{sub 2}) as a chemical booster. The results of five reductions of UF{sub 4}, spanning 100 to 200 g of uranium, are evaluated, and suggestions are made for future work in this area.

West, M.H.; Martinez, M.M.; Nielsen, J.B.; Court, D.C.; Appert, Q.D.

1995-09-01T23:59:59.000Z

434

Depleted Uranium De-conversion  

E-Print Network (OSTI)

This Environmental Report (ER) constitutes one portion of an application being submitted by International Isotopes Fluorine Products (IIFP) to construct and operate a facility that will utilize depleted DUF6 to produce high purity inorganic fluorides, uranium oxides, and anhydrous hydrofluoric acid. The proposed IIFP facility will be located near Hobbs, New Mexico. IIFP has prepared the ER to meet the requirements specified in 10 CFR 51, Subpart A, particularly those requirements set forth in 10 CFR 51.45(b)-(e). The organization of this ER is generally consistent with NUREG-1748, Environmental Review Guidance for Licensing Actions Associated with NMSS Programs, Final Report. The Environmental Report for this proposed facility provides information that is specifically required by the NRC to assist it in meeting its obligations under the National Environmental Policy Act (NEPA) of 1969 and the agencys NEPA-implementing regulations. This ER demonstrates that the environmental protection measures proposed by IIFP are adequate to protect both the environment and the health and safety of the public. This Environmental Report evaluates the potential environmental impacts of the Proposed Action and its reasonable alternatives. This ER also describes the environment potentially affected by IIEFs proposal,

Fluorine Extraction Process

2009-01-01T23:59:59.000Z

435

EIS-0355: Remediation of the Moab Uranium Mill Tailings, Grand...  

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

355: Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah EIS-0355: Remediation of the Moab Uranium Mill Tailings, Grand and San Juan Counties, Utah...

436

Detection of uranium enrichment activities using environmental monitoring techniques  

SciTech Connect

Uranium enrichment processes have the capability of producing weapons-grade material in the form of highly enriched uranium. Thus, detection of undeclared uranium enrichment activities is an international safeguards concern. The uranium separation technologies currently in use employ UF{sub 6} gas as a separation medium, and trace quantities of enriched uranium are inevitably released to the environment from these facilities. The isotopic content of uranium in the vegetation, soil, and water near the plant site will be altered by these releases and can provide a signature for detecting the presence of enriched uranium activities. This paper discusses environmental sampling and analytical procedures that have been used for the detection of uranium enrichment facilities and possible safeguards applications of these techniques.

Belew, W.L.; Carter, J.A.; Smith, D.H.; Walker, R.L.

1993-03-30T23:59:59.000Z

437

Management Controls over the Department of Energy's Uranium Leasing...  

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

of Energy's Uranium Leasing Program was established by the Atomic Energy Act of 1954 to develop a supply of domestic uranium to meet the nation's defense needs. Pursuant to...

438

DOE Announces Policy for Managing Excess Uranium Inventory | Department of  

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

Policy for Managing Excess Uranium Inventory Policy for Managing Excess Uranium Inventory DOE Announces Policy for Managing Excess Uranium Inventory March 12, 2008 - 10:52am Addthis WASHINGTON, DC - U.S. Secretary of Energy Samuel W. Bodman today released a Policy Statement on the management of the Department of Energy's (DOE) excess uranium inventory, providing the framework within which DOE will make decisions concerning future use and disposition of its inventory. During the coming year, DOE will continue its ongoing program for downblending excess highly enriched uranium (HEU) into low enriched uranium (LEU), evaluate the benefits of enriching a portion of its excess natural uranium into LEU, and complete an analysis on enriching and/or selling some of its depleted uranium. Specific transactions are expected to occur in

439

The Office of Environmental Management Uranium Enrichment D&D...  

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

Uranium Enrichment D&D The Office of Environmental Management Uranium Enrichment D&D Microsoft Word - B996F741.doc More Documents & Publications Microsoft Word - PSRP Updates...

440

FAQ 24-Who is responsible for managing depleted uranium?  

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

Who is responsible for managing depleted uranium? Who is responsible for managing depleted uranium? In the United States, the U.S. Department of Energy is responsible for managing...

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.


441

Production and Handling Slide 3: The Uranium Fuel Cycle  

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

First Slide Previous Slide Next Slide Last Presentation Table of Contents The Uranium Fuel Cycle See caption below for image description The second step in the uranium fuel cycle...

442

2nd Quarter 2013 Domestic Uranium Production Report  

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

nd Quarter 2013 Domestic Uranium Production Report 2nd Quarter 2013 Domestic Uranium Production Report Release Date: August 7, 2013 Next Release Date: November 2013 0 500,000...

443

FAQ 19-Is storage of uranium hexafluoride safe?  

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

storage of uranium hexafluoride safe? Is storage of uranium hexafluoride safe? The advanced age of some of the steel cylinders in which the depleted UF6 is contained, and the way...

444

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

Office of Legacy Management (LM)

Climax Uranium Co Grand Junction Mill - CO 0-03 FUSRAP Considered Sites Site: Climax Uranium Co. (Grand Junction Mill) (CO.0-03) Designated Name: Alternate Name: Location:...

445

Uranium Made Easy: 1663 Science and Technology Magazine | Los...  

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

Uranium Made Easy "Uranium possesses a lot of unique properties and has been shown to catalyze reactions that no other element can," says Jaqueline Kiplinger of the Los Alamos...

446

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

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

Inspection Uranium at Y-12: Inspection Posted: July 22, 2013 - 3:36pm | Y-12 Report | Volume 10, Issue 1 | 2013 Inspection of enriched uranium is performed by dimensional checks...

447

Y-12 Bulletin Uranium Articles | Y-12 National Security Complex  

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

Y-12 Bulletin Uranium ... Y-12 Bulletin Uranium Articles Posted: July 22, 2013 - 3:13pm | Y-12 Report | Volume 10, Issue 1 | 2013 These and other articles can be found in archived...

448

U.S. Energy Information Administration / 2012 Uranium Marketing...  

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

U.S. Energy Information Administration 2012 Uranium Marketing Annual Report 2012 Uranium Marketing Annual Report Release Date: May 16, 2013 Next Release Date: May 2014 U.S....

449

Reducing the environmental impact of uranium in-situ recovery.  

Science Conference Proceedings (OSTI)

This session will explore the current technical approaches to reducing the environmental effects of uranium ISR in comparison to the historical environmental impact of uranium mining to demonstrate advances in this controversial subject.

Siegel, Malcolm Dean; Simmons, Ardyth

2010-10-01T23:59:59.000Z

450

Prospects for the recovery of uranium from seawater  

E-Print Network (OSTI)

A computer program entitled URPE (Uranium Recovery Performance and Economics) has been developed to simulate the engineering performance and provide an economic analysis O of a plant recovering uranium from seawater. The ...

Best, F. R.

1980-01-01T23:59:59.000Z

451

Y-12 and the super enriched Uranium 235?  

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

"super enriched Uranium 235" Ken Bernander called me to say that he had read in the newspaper about the 100 milligrams of uranium oxide that is 99.999% U-235. He was chuckling when...

452

Bioreduction and precipitation of uranium in ionic liquid aqueous...  

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

Nuclear Engineering, Pohang University of Science and Technology, Pohang 790-784, South Korea h i g h l i g h t s &21; Uranium forms various complexes with ionic liquids. &21; Uranium...

453

Uranium internal exposure evaluation based on urine assay data  

SciTech Connect

The difficulties in assessing internal exposures to uranium from urine assay data are described. A simplified application of the ICRP-30 and ICRP Lung Model concepts to the estimation of uranium intake is presented. A discussion follows on the development of a computer code utilizing the ICRP-30-based uranium elimination model with the existing urine assay information. The calculated uranium exposures from 1949 through 1983 are discussed. 13 references, 1 table.

Lawrence, J.N.P.

1984-09-01T23:59:59.000Z

454

NIST: Uranium, Atomic Ref. Data for Elect. Struct. Calc.  

Science Conference Proceedings (OSTI)

Table of contents logo, Atomic Reference Data for Electronic Structure Calculations. Uranium. Key to notation | HTML table ...

455

Modeling Uranium-Proton Ion Exchange in Biosorption  

E-Print Network (OSTI)

Modeling Uranium-Proton Ion Exchange in Biosorption J I N B A I Y A N G A N D B O H U M I L V O L E, Quebec, Canada H3A 2B2 Biosorption of uranium metal ions by a nonliving protonated Sargassum fluitans seaweed biomass was used to remove the heavy metal uranium from the aqueous solution. Uranium biosorption

Volesky, Bohumil

456

In-Situ Evidence for Uranium Immobilization and Remobilization  

E-Print Network (OSTI)

, together with depleted uranium, for fabrication of mixed oxide fuel (MOX) for reuse in a light water with depleted uranium to produce a metallic fuel for a fast reactor. The fast reactor can be designed to produce of depleted uranium and the cost of fabricating the MOX fuel: ( ) ( ) 2,22,22,22,2 bpzupf ++= . (11) The back

Istok, Jonathan "Jack"

457

Electrokinetic removal of uranium from contaminated, unsaturated soils  

SciTech Connect

Electrokinetic remediation of uranium-contaminated soil was studied in a series of laboratory-scale experiments in test cells with identical geometry using quartz sand at approximately 10 percent moisture content. Uranium, when present in the soil system as an anionic complex, could be migrated through unsaturated soil using electrokinetics. The distance that the uranium migrated in the test cell was dependent upon the initial molar ratio of citrate to uranium used. Over 50 percent of the uranium was recovered from the test cells using the citrate and carbonate complexing agents over of period of 15 days. Soil analyses showed that the uranium remaining in the test cells had been mobilized and ultimately would have been extracted. Uranium extraction exceeded 90 percent in an experiment that was operated for 37 days. Over 70 percent of the uranium was removed from a Hanford waste sample over a 55 day operating period. Citrate and carbonate ligand utilization ratios required for removing 50 percent of the uranium from the uranium-contaminated sand systems were approximately 230 moles ligand per mole uranium and 1320 moles ligand per mole uranium for the waste. Modifying the operating conditions to increasing the residence time of the complexants is expected to improved the utilization efficiency of the complexing agent.

Booher, W.F. [IT Corp., Albuquerque, NM (United States); Lindgren, E.R.; Brady, P.V. [Sandia National Laboratories, Albuquerque, NM (United States)

1997-01-01T23:59:59.000Z

458

The Uranium Availability and Uptake in the Vegetables  

Science Conference Proceedings (OSTI)

The research of a potted experiment ruling uranium availability and uptake by four kinds of vegetables (lettuce,carrot , potatoes , peas) are described. Four kinds of vegetables spiked with the different uranium concentration in the aqueous and different ... Keywords: vegetables, uranium, Soil-liquid distribution, Uptake, Soil-to-plant transfer

Zhang Jing; Chen Diyun; Liu Juan

2012-05-01T23:59:59.000Z

459

Appendix IV. Risks Associated with Conventional Uranium Milling Introduction  

E-Print Network (OSTI)

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 Radioactive Materials from Uranium Mining. Volume 1: Mining and Reclamation Background" by U.S. EPA (2006

460

Soil to plant transfer of 238 Th on a uranium  

E-Print Network (OSTI)

Soil to plant transfer of 238 U, 226 Ra and 232 Th on a uranium mining-impacted soil from species grown in soils from southeastern China contaminated with uranium mine tailings were analyzed The radioactive waste (e.g. tailings) produced by uranium mining activities contains a series of long

Hu, Qinhong "Max"

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.


461

The Evaluation Index System and Method of Sustainable Uranium Development  

Science Conference Proceedings (OSTI)

Under the construction of sustainable development index system of uranium, I use factor analysis in the study of the Henan Province in 2000, 2003 and 2006, the uranium resources for sustainable development of the situation. The conclusion is: from the ... Keywords: evaluation index system, evaluation method, sustainable uranium development

Chenggang Gong; Songlin Liu

2009-01-01T23:59:59.000Z

462

Plutonium recovery from spent reactor fuel by uranium displacement  

DOE Patents (OSTI)

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

Ackerman, John P. (Downers Grove, IL)

1992-01-01T23:59:59.000Z

463

Plutonium recovery from spent reactor fuel by uranium displacement  

DOE Patents (OSTI)

This report discusses a process for separating uranium values and transuranic values from fission products containing rare earth values when the values which 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 re-established.

Ackerman, J.P.

1991-01-01T23:59:59.000Z

464

Bioremediation of Uranium Plumes with Nano-scale  

E-Print Network (OSTI)

Bioremediation of Uranium Plumes with Nano-scale Zero-valent Iron Angela Athey Advisers: Dr. Reyes Undergraduate Student Fellowship Program April 15, 2011 #12;Main Sources of Uranium Natural · Leaching from(IV) (UO2[s], uraninite) Anthropogenic · Release of mill tailings during uranium mining - Mobilization

Cushing, Jim. M.

465

Uranium Stocks in Slovenia for Nuclear Power Author: Matic Suhodolcan  

E-Print Network (OSTI)

Seminar Uranium Stocks in Slovenia for Nuclear Power Plant NEK Author: Matic Suhodolcan Supervisor and that reopening would make sense. We try to calculate the years of operating NEK only with uranium ore for reprocessing fuel. #12;Uranium Stocks in Slovenia for Slovenian Nuclear Power Plant NEK Matic Suhodolcan FMF 2

Prosen, Toma?

466

Uranium Mill Tailings Remedial Action Project surface project management plan  

SciTech Connect

This Project Management Plan describes the planning, systems, and organization that shall be used to manage the Uranium Mill Tailings Remedial Action Project (UMTRA). US DOE is authorized to stabilize and control surface tailings and ground water contamination at 24 inactive uranium processing sites and associated vicinity properties containing uranium mill tailings and related residual radioactive materials.

Not Available

1994-09-01T23:59:59.000Z

467

NUREG/CR-6911 Tests of Uranium (VI) Adsorption  

E-Print Network (OSTI)

was a uranium mill tailings site at Naturita, Colorado. The techniques tested included: 1) the use of downhole was a uranium mill tailings site at Naturita, Colorado. This report is one in a series of reports documenting. The field site used for the study was the uranium mill tailings site at Naturita, Colorado (Davis and Curtis

468

Method for fluorination of uranium oxide  

SciTech Connect

Highly pure uranium hexafluoride is made from uranium oxide and fluorine. The uranium oxide, which includes UO.sub.3, UO.sub.2, U.sub.3 O.sub.8 and mixtures thereof, is introduced together with a small amount of a fluorine-reactive substance, selected from alkali chlorides, silicon dioxide, silicic acid, ferric oxide, and bromine, into a constant volume reaction zone. Sufficient fluorine is charged into the zone at a temperature below approximately 0.degree. C. to provide an initial pressure of at least approximately 600 lbs/sq. in. at the ambient atmospheric temperature. The temperature is then allowed to rise in the reaction zone until reaction occurs.

Petit, George S. (Oak Ridge, TN)

1987-01-01T23:59:59.000Z

469

Depleted uranium plasma reduction system study  

Science Conference Proceedings (OSTI)

A system life-cycle cost study was conducted of a preliminary design concept for a plasma reduction process for converting depleted uranium to uranium metal and anhydrous HF. The plasma-based process is expected to offer significant economic and environmental advantages over present technology. Depleted Uranium is currently stored in the form of solid UF{sub 6}, of which approximately 575,000 metric tons is stored at three locations in the U.S. The proposed system is preconceptual in nature, but includes all necessary processing equipment and facilities to perform the process. The study has identified total processing cost of approximately $3.00/kg of UF{sub 6} processed. Based on the results of this study, the development of a laboratory-scale system (1 kg/h throughput of UF6) is warranted. Further scaling of the process to pilot scale will be determined after laboratory testing is complete.

Rekemeyer, P.; Feizollahi, F.; Quapp, W.J.; Brown, B.W.

1994-12-01T23:59:59.000Z

470

SEPARATION OF URANIUM FROM THORIUM AND PROTACTINIUM  

DOE Patents (OSTI)

This patent relates to the separation of uranium from thorium and protactinium; such mixtures of elements usually being obtained by neutron irradiation of thorium. The method of separating the constituents has been first to dissolve the mixture of elements in concertrated nitric acid and then to remove the protactinium by absorption on manganese dioxide and the uranium by solvent extraction with ether. Prior to now, comparatively large amounts of thorium were extracted with the uranium. According to the invention this is completely prevented by adding sodium diethyldithiocarbamate to the mixture of soluble nitrate salts. The organic salt has the effect of reacting only with the uranyl nitrate to form the corresponding uranyl salt which can then be selectively extracted from the mixture with amyl acetate.

Musgrave, W.K.R.

1959-06-30T23:59:59.000Z

471

TRACE ELEMENT ANALYSES OF URANIUM MATERIALS  

SciTech Connect

The Savannah River National Laboratory (SRNL) has developed an analytical method to measure many trace elements in a variety of uranium materials at the high part-per-billion (ppb) to low part-per-million (ppm) levels using matrix removal and analysis by quadrapole ICP-MS. Over 35 elements were measured in uranium oxides, acetate, ore and metal. Replicate analyses of samples did provide precise results however none of the materials was certified for trace element content thus no measure of the accuracy could be made. The DOE New Brunswick Laboratory (NBL) does provide a Certified Reference Material (CRM) that has provisional values for a series of trace elements. The NBL CRM were purchased and analyzed to determine the accuracy of the method for the analysis of trace elements in uranium oxide. These results are presented and discussed in the following paper.

Beals, D; Charles Shick, C

2008-06-09T23:59:59.000Z

472

U. S. forms uranium enrichment corporation  

SciTech Connect

After almost 40 years of operation, the federal government is withdrawing from the uranium enrichment business. On July 1, the Department of Energy turned over to a new government-owned entity--the US Enrichment Corp. (USEC)--both the DOE enrichment plants at Paducah, Ky., and Portsmouth, Ohio, and domestic and international marketing of enriched uranium from them. Pushed by the inability of DOE's enrichment operations to meet foreign competition, Congress established USEC under the National Energy Policy Act of 1992, envisioning the new corporation as the first step to full privatization. With gross revenues of $1.5 billion in fiscal 1992, USEC would rank 275th on the Fortune 500 list of top US companies. USEC will lease from DOE the Paducah and Portsmouth facilities, built in the early 1950s, which use the gaseous diffusion process for uranium enrichment. USEC's stock is held by the US Treasury, to which it will pay annual dividends. Martin Marietta Energy Systems, which has operated Paducah since 1984 and Portsmouth since 1986 for DOE, will continue to operate both plants for USEC. Closing one of the two facilities will be studied, especially in light of a 40% world surplus of capacity over demand. USEC also will consider other nuclear-fuel-related ventures. USEC will produce only low-enriched uranium, not weapons-grade material. Indeed, USEC will implement a contract now being completed under which the US will purchase weapons-grade uranium from dismantled Russian nuclear weapons and convert it into low-enriched uranium for power reactor fuel.

Seltzer, R.

1993-07-12T23:59:59.000Z

473

REDUCTION DE L'OCTOOXYDE D'URANIUM EN DIOXYDE D'URANIUM PAR L'AMMONIAC  

E-Print Network (OSTI)

REDUCTION DE L'OCTOOXYDE D'URANIUM EN DIOXYDE D'URANIUM PAR L'AMMONIAC P. Suhubiette1 , F mines, 158 Cours Fauriel, 42023 Saint Etienne Cedex2, France Résumé. Ce travail présente l'étude cinétique de la réduction de l'octooxyde d'uranium par l'ammoniac en dioxyde d'uranium. Cette réduction

474

SciTech Connect: enriched uranium  

Office of Scientific and Technical Information (OSTI)

enriched uranium Find enriched uranium Find How should I search Scitech Connect ... Basic or Advanced? Basic Search Advanced × Advanced Search Options Full Text: Bibliographic Data: Creator / Author: Name Name ORCID Title: Subject: Identifier Numbers: Research Org.: Sponsoring Org.: Site: All Alaska Power Administration, Juneau, Alaska (United States) Albany Research Center (ARC), Albany, OR (United States) Albuquerque Complex - NNSA Albuquerque Operations Office, Albuquerque, NM (United States) Amarillo National Resource Center for Plutonium, Amarillo, TX (United States) Ames Laboratory (AMES), Ames, IA (United States) Argonne National Laboratory (ANL), Argonne, IL (United States) Argonne National Laboratory-Advanced Photon Source (United States) Atlanta Regional Office, Atlanta, GA (United States) Atmospheric Radiation Measurement (ARM)

475

Uranium in the Savannah River Site environment  

SciTech Connect

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

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

1992-12-09T23:59:59.000Z

476

Uranium in the Savannah River Site environment  

SciTech Connect

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

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

1992-12-09T23:59:59.000Z

477

METHOD OF HOT ROLLING URANIUM METAL  

DOE Patents (OSTI)

A method is given for quickly and efficiently hot rolling uranium metal in the upper part of the alpha phase temperature region to obtain sound bars and sheets possessing a good surface finish. The uranium metal billet is heated to a temperature in the range of 1000 deg F to 1220 deg F by immersion iii a molten lead bath. The heated billet is then passed through the rolls. The temperature is restored to the desired range between successive passes through the rolls, and the rolls are turned down approximately 0.050 inch between successive passes.

Kaufmann, A.R.

1959-03-10T23:59:59.000Z

478

Standard specification for uranium metal enriched to more than 15 % and less Than 20 % 235U  

E-Print Network (OSTI)

1.1 This specification covers nuclear grade uranium metal that has either 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 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural uranium, recovered uranium, or highly enriched uranium. Commercial natural uranium, recovered uranium and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium isotope limits for commercial grade enriched uranium metal. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used in the production of research reactor fuel. In addition to this specification, the parties concerned may agree to other appropriate conditions. ...

American Society for Testing and Materials. Philadelphia

2000-01-01T23:59:59.000Z

479

RECENT ADVANCES IN THE POWDER METALLURGY OF URANIUM CARBIDE  

SciTech Connect

uranium carbide, uranium metal is converted to uranium hydride powder and then carburized using propane gas. The carbide particles are irregular, of a relatively uniform size, and highly pyrophoric. Paraffin, camphor, cetyl alcohol, beeswax, and carbowax are used as lubricants and binders for compacting uranium carbide powder. Sintering studies were conducted for various times and temperatures, primarily in vacuum. An investigation is in progress to evaluate the effect of carbon content on the properties and irradiation stability of uranium carbide. It is shown that the powder metallurgy technique achieves a product wfth reasonably good density and apparentiy adequate properties for reactor utilization. (M.C.G.)

Kalish, H.S.

1962-10-31T23:59:59.000Z

480

PROCESS FOR THE PRODUCTION OF AMMONIUM URANIUM FLUORIDE  

DOE Patents (OSTI)

This patent relates to the preparation of ammonium uranium fluoride. The process comprises adding a water soluble fluoride to an aqueous solution of a uranous compound containing an ammonium salt, and isolating the resulting precipitate. This patent relates to the manufacture of uranium tetnafluoride from ammonium uranium fluoride, NH/sub 4/UF/sub 5/. Uranium tetrafluoride is prepared by heating the ammonium uranium fluoride to a temperature at which dissociation occurs with liberation of ammonium fluoride. Preferably the process is carried out under reduced pressure, or in a current of an inert gas.

Ellis, A.S.; Mooney, R.B.

1953-08-25T23:59:59.000Z

Note: This page contains sample records for the topic "tract c-g-26 uranium" 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.


481

Possibility of nuclear pumped laser experiment using low enriched uranium  

SciTech Connect

Possibility to perform experiments for nuclear pumped laser oscillation by using low enriched uranium is investigated. Kinetic analyses are performed for two types of reactor design, one is using highly enriched uranium and the other is using low enriched uranium. The reactor design is based on the experiment reactor in IPPE. The results show the oscillation of nuclear pumped laser in the case of low enriched uranium reactor is also possible. The use of low enriched uranium in the experiment will make experiment easier.

Obara, Toru; Takezawa, Hiroki [Center for Research into Innovative Nuclear Energy Systems Tokyo Institute of Technology 2-12-1-N1-19, Ookayama Meguro-ku, Tokyo 152-8550 (Japan)

2012-06-06T23:59:59.000Z

482

Ion exchange separation and mass spectrometric analysis of uranium for solutions containing plutonium  

SciTech Connect

An ion exchange technique separates plutonium from uranium using Dowex-1 resin and a methanol--HCl plutonium elutriant. The method is applicable to both trace uranium determination and uranium isotopic distribution analysis by mass spectrometry. Distribution coefficients for plutonium, and elution curves for uranium and plutonium are shown. For uranium analysis the percent relative standard deviation is 0.8 at 120-2400 micrograms uranium per gram plutonium and 5.0 at 5 micrograms uranium per gram plutonium. (auth)

McBride, K.C.

1975-06-01T23:59:59.000Z

483

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.

1995-07-05T23:59:59.000Z

484

DOE/EA-1607: Final Environmental Assessment for Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium (June 2009)  

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

μCi/cc microcuries per cubic centimeter μCi/cc microcuries per cubic centimeter MAP mitigation action plan MEI maximally exposed individual mg/kg milligrams per kilogram mrem millirem mSv millisievert MT metric ton MTCA Model Toxics Control Act MTU metric tons of uranium N/A not applicable Final Environmental Assessment: Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium vi NAAQS National Ambient Air Quality Standards NEF National Enrichment Facility NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission NU natural uranium NUF 6 natural uranium hexafluoride pCi/g picocuries per gram PEIS programmatic environmental impact statement PM 2.5 particulate matter with a diameter of 2.5 microns or less PM 10 particulate matter with a diameter of 10 microns or less

485

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

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

Recovery Recovery Uranium at Y-12: Recovery Posted: July 22, 2013 - 3:44pm | Y-12 Report | Volume 10, Issue 1 | 2013 Recovery involves reclaiming uranium from numerous sources and configurations and handling uranium in almost any form, including oxides and liquids (see A Rich Resource Requires Recovery). Y-12 has the equipment and expertise to recover uranium that is present in filters, wipes, mop water and elsewhere. For many salvage materials, the uranium is extracted and then manipulated into a uranyl nitrate solution, purified and chemically converted through several stages. Then it is reduced to a mass of uranium metal. This mass, called a button, is used in casting operations. The chemical operators who recover and purify uranium understand and monitor complex chemical reactions, flow rates, temperatures

486

Uranium Leasing Program: Program Summary | Department of Energy  

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

Uranium Leasing Program » Uranium Leasing Uranium Leasing Program » Uranium Leasing Program: Program Summary Uranium Leasing Program: Program Summary Uranium Leasing Program: Program Summary The Atomic Energy Act and other legislative actions authorized the U.S. Atomic Energy Commission (AEC), predecessor agency to the DOE, to withdraw lands from the public domain and then lease them to private industry for mineral exploration and for development and mining of uranium and vanadium ore. A total of 25,000 acres of land in southwestern Colorado, northern New Mexico, and southeastern Utah was withdrawn from the public domain during the late 1940s and early 1950s. In 1948, AEC included portions of these lands in 48 mineral leases that were negotiated with adjacent mine owners/operators. This early leasing

487

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

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

... ... Uranium at Y-12: Accountability Posted: July 22, 2013 - 3:37pm | Y-12 Report | Volume 10, Issue 1 | 2013 Accountability of enriched uranium is facilitated by the ability to put uranium into well-blended aqueous, organic, crystalline, powder, granular, metallic and compound forms that can be sampled and analyzed. Periodic inventories are necessary to find and account for all the enriched uranium that hides in equipment corners and crevices. This allows enriched uranium to be processed in large quantities and accounted for by the gram. Y-12 employees know where uranium resides in large, complex facilities and how to use computer tools to track and monitor its movement (see Uranium Track Team). Learn more about some of the complexities in reprocessing and safeguarding

488

FAQ 8-What is uranium hexafluoride (UF6)?  

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

is uranium hexafluoride (UF6)? is uranium hexafluoride (UF6)? What is uranium hexafluoride (UF6)? 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. Liquid UF6 is formed only at temperatures greater than 147° F (64° C) and at pressures greater than 1.5 times atmospheric pressure (22 psia). At atmospheric pressure, solid UF6 will transform directly to UF6 gas (sublimation) when the temperature is raised to 134° F (57° C), without going through a liquid phase.

489

DOE Releases Excess Uranium Inventory Plan | Department of Energy  

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

Excess Uranium Inventory Plan Excess Uranium Inventory Plan DOE Releases Excess Uranium Inventory Plan December 16, 2008 - 8:51am Addthis WASHINGTON, D.C. - The United States Department of Energy (DOE) today issued its Excess Uranium Inventory Management Plan (the Plan), which outlines the Department's strategy for the management and disposition of its excess uranium inventories. The Plan highlights DOE's ongoing efforts to enhance national security and promote a healthy domestic nuclear infrastructure through the efficient and cost-effective management of its excess uranium inventories. The Department has a significant inventory of uranium that is excess to national defense needs and is expensive both to manage and secure. "The Plan provides the general public and interested stakeholders more

490

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

491

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

492

EA-1290: Disposition of Russian Federation Titled Natural Uranium |  

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

290: Disposition of Russian Federation Titled Natural Uranium 290: Disposition of Russian Federation Titled Natural Uranium EA-1290: Disposition of Russian Federation Titled Natural Uranium SUMMARY This EA evaluates the potential environmental impacts of a proposal to transport up to an average of 9,000 metric tons per year of natural uranium as uranium hexafluoride (UF6) from the United States to the Russian Federation. This amount of uranium is equivalent to 13,3000 metric tons of UF6. The EA also examines the impacts of this action on the global commons. Transfer of natural UF6 to the Russian Federation is part of a joint U.S./Russian program to dispose of highly enriched uranium (HEU) from dismantled Russian nuclear weapons. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD

493

Excess Uranium Inventory Management Plan | Department of Energy  

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

Excess Uranium Inventory Management Plan Excess Uranium Inventory Management Plan Excess Uranium Inventory Management Plan The 2013 Excess Uranium Inventory Management Plan describes a framework for the effective management of the Energy Department's surplus uranium inventory in support of meeting its critical environmental cleanup and national security missions. The Plan is not a commitment to specific activities beyond those that have already been contracted nor is it a restriction on actions that the Department may undertake in the future as a result of changing conditions. It replaces an earlier plan issued in 2008 and reflects updated information on the Department of Energy's management and disposition of its excess uranium inventories. Excess Uranium Inventory Management Plan More Documents & Publications

494

IRON COATED URANIUM AND ITS PRODUCTION  

DOE Patents (OSTI)

A method of applying a protective coating to a metallic uranium article is given. The method comprises etching the surface of the article with an etchant solution containlng chloride ions, such as a solution of phosphoric acid and hydrochloric acid, cleaning the etched surface, electroplating iron thereon from a ferrous ammonium sulfate electroplating bath, and soldering an aluminum sheath to the resultant iron layer.

Gray, A.G.

1960-03-15T23:59:59.000Z

495

RECOVERY OF URANIUM VALUES FROM RESIDUES  

DOE Patents (OSTI)

A process is described for the recovery of uranium from insoluble oxide residues resistant to repeated leaching with mineral acids. The residue is treated with gaseous hydrogen fluoride, then with hydrogen and again with hydrogen fluoride, preferably at 500 to 700 deg C, prior to the mineral acid leaching.

Schaap, W.B.

1959-08-18T23:59:59.000Z

496

National Uranium Resource Evaluation, Trona Quadrangle, California  

SciTech Connect

The Trona 2/sup 0/ Quadrangle, in southeastern California, was evaluated according to criteria of developed for the National Uranium Resource Evaluation Program to identify areas favorable for the occurrence of uranium deposits. General reconnaissance and sampling were conducted in all accessible areas of the quadrangle. Detailed surface investigations were conducted in potentially favorable environments. Subsurface data were limited to the available results of previous drilling. The results of these studies indicate that granitic rock in the Castle Butte and Boron 15' quadrangles is favorable for authigenic uranium deposits; vein-type and stratabound deposits within tuffaceous sandstones of the Tropico Group in the same area are favorable; Barstow Formation sandstones and shales are favorable in carbonaceous shale and in peneconcordant sandstone in the south-central part of the quadrangle; and sediments of the Lake Tecopa Beds in the northeast of the quadrangle are favorable for hydroallogenic deposits. Environments unfavorable for uranium deposits are in Precambrian and Paleozoic metasedimentary and metavolcanic rocks, except those in unevaluated areas; in plutonic and volcanic rocks of Mesozoic Age, except the favorable granite in the Castle Butte and Boron quadrangles; in Tertiary sedimentary and volcanic rocks, except those favorable in the Tropico Group and Barstow Formation; and in Quaternary volcanic rocks and sediments, except the favorable deposits at Lake Tecopa and the unevaluated alluvium. Two inaccessible areas and the alluvium are unevaluated.

Bushnell, M.M.; Morton, P.K.

1982-07-01T23:59:59.000Z

497

Statistical design of a uranium corrosion experiment  

DOE Green Energy (OSTI)

This work supports an experiment being conducted by Roland Schulze and Mary Ann Hill to study hydride formation, one of the most important forms of corrosion observed in uranium and uranium alloys. The study goals and objectives are described in Schulze and Hill (2008), and the work described here focuses on development of a statistical experiment plan being used for the study. The results of this study will contribute to the development of a uranium hydriding model for use in lifetime prediction models. A parametric study of the effect of hydrogen pressure, gap size and abrasion on hydride initiation and growth is being planned where results can be analyzed statistically to determine individual effects as well as multi-variable interactions. Input to ESC from this experiment will include expected hydride nucleation, size, distribution, and volume on various uranium surface situations (geometry) as a function of age. This study will also address the effect of hydrogen threshold pressure on corrosion nucleation and the effect of oxide abrasion/breach on hydriding processes. Statistical experiment plans provide for efficient collection of data that aids in understanding the impact of specific experiment factors on initiation and growth of corrosion. The experiment planning methods used here also allow for robust data collection accommodating other sources of variation such as the density of inclusions, assumed to vary linearly along the cast rods from which samples are obtained.

Wendelberger, Joanne R [Los Alamos National Laboratory; Moore, Leslie M [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

498

Microbiological treatment of uranium mine waters  

SciTech Connect

Percolation of uranium mine discharge water through Ambrosia Lake, NM, soil is shown to be an effective method for lowering selenium, uranium, molybdenum, and sulfate concentrations in the mine water. Selenium concentrations were lowered from approx.1.6 to <0.05 mg/L by reduction of soluble selenate and selenite to insoluble selenium metal. This reaction is most likely performed by bacteria belonging to the genus Clostridium. In addition, sulfate-reducing bacteria in the soil, such as Desulfovibrio bacteria, metabolize sulfate to hydrogen sulfide, which reacts with uranyl and molybdate ions to form insoluble uranium and molybdenum species. The concentrations of sulfate, uranium, and molybdenum were reduced to less than 600, 0.1, and 0.05 mg/L, respectively. A qualitative understanding of the effects of mine water temperature, flow rate, and nutrients on metals removal is provided. The process was successfully field tested for 7 months in a soil column 1.5 m deep. 13 references, 3 figures, 4 tables.

Kauffman, J.W.; Laughlin, W.C.; Baldwin, R.A.

1986-03-01T23:59:59.000Z

499

The Quest for the Heaviest Uranium Isotope  

E-Print Network (OSTI)

We study Uranium isotopes and surrounding elements at very large neutron number excess. Relativistic mean field and Skyrme-type approaches with different parametrizations are used in the study. Most models show clear indications for isotopes that are stable with respect to neutron emission far beyond N=184 up to the range of around N=258.

S. Schramm; D. Gridnev; D. V. Tarasov; V. N. Tarasov; W. Greiner

2011-07-06T23:59:59.000Z

500

Complex defects in the oxidation of uranium  

Science Conference Proceedings (OSTI)

We are reporting EPR results obtained with uranium powder samples fully oxidized in dry air, water vapor, and air/water vapor mixtures. The results reported previously are confirmed and additional paramagnetic centers, associated with chemisorbed species, have been identified. The temperature dependence of the g-value for these centers from room temperature to 10K is also reported.

MacCrone, R.K.; Sankaran, S.; Shatynski, S.R.; Colmenares, C.A.

1986-06-10T23:59:59.000Z