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Note: This page contains sample records for the topic "uranium ore deposits" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


1

The Dispersion of Radon Above Deeply Buried Uranium Ore: Millennium Deposit, Athabasca Basin, SK , K Hattori1  

E-Print Network [OSTI]

The Dispersion of Radon Above Deeply Buried Uranium Ore: Millennium Deposit, Athabasca Basin, SK M, Ottawa, ON, 2 Cameco Corporation, Saskatoon, SK Depth Profiles Canada Mining Innovation Council Natural., Portella, P., Olson, R.A., 2007. Unconformity- associated uranium deposits of the Athabasca Basin

2

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

Office of Legacy Management (LM)

Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and...

3

Uranium 238U/235U isotope ratios as indicators of reduction: Results from an in situ biostimulation experiment at Rifle, Colorado, USA  

E-Print Network [OSTI]

sandstone-type uranium deposits. Economic Geology; 1962; (5)uranium ore deposits: Isotopic signatures of the U reduction process? ; Geology,

Bopp IV, C.J.

2010-01-01T23:59:59.000Z

4

PHASE ANALYSES OF URANIUM-BEARING MINERALS FROM THE HIGH GRADE ORE, NOPAL I, PENA BLANCA, MEXICO  

SciTech Connect (OSTI)

The Nopal I uranium deposit is located in the Pena Blanca district, approximately 40 miles north of Chihuahua City, Mexico. The deposit was formed by hydrothermal processes within the fracture zone of welded silicic volcanic tuff. The ages of volcanic formations are between 35 to 44 m.y. and there was secondary silicification of most of the formations. After the formation of at least part of the uranium deposit, the ore body was uplifted above the water table and is presently exposed at the surface. Detailed petrographic characterization, electron microprobe backscatter electron (BSE) imagery, and selected x-ray maps for the samples from Nopal I high-grade ore document different uranium phases in the ore. There are at least two stages of uranium precipitation. A small amount of uraninite is encapsulated in silica. Hexavalent uranium may also have been a primary precipitant. The uranium phases were precipitated along cleavages of feldspars, and along fractures in the tuff. Energy dispersive spectrometer data and x-ray maps suggest that the major uranium phases are uranophane and weeksite. Substitutions of Ca and K occur in both phases, implying that conditions were variable during the mineralization/alteration process, and that compositions of the original minerals have a major influence on later stage alteration. Continued study is needed to fully characterize uranium behavior in these semi-arid to arid conditions.

M. Ren; P. Goodell; A. Kelts; E.Y. Anthony; M. Fayek; C. Fan; C. Beshears

2005-07-11T23:59:59.000Z

5

Ground water remediation at the Moab, Utah, USA, former uranium-ore processing site  

Science Journals Connector (OSTI)

Seepage from the Moab, Utah, USA, former uranium-ore processing site resulted in ammonia and uranium contamination of naturally occurring saline ground water in alluvium adjacent to the Colorado River. An interim...

Donald R. Metzler; Joseph D. Ritchey; Kent A. Bostick…

2008-01-01T23:59:59.000Z

6

E-Print Network 3.0 - albarrana uranium ores Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: albarrana uranium ores Page: << < 1 2 3 4 5 > >> 1 geology and Ranger 1 open-pit uranium mine in...

7

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

SciTech Connect (OSTI)

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

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

2006-04-01T23:59:59.000Z

8

Part I: Typology of Uranium Deposits  

Science Journals Connector (OSTI)

A variety of global and regional classification schemes for uranium deposits have been proposed in the past by a number of geoscientists including Heinrich (1958), Roubault (1958), Ruzicka (1971), Ziegler (197...

Franz J. Dahlkamp

2009-01-01T23:59:59.000Z

9

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

E-Print Network [OSTI]

uranium budgets and behavior along a Hawaiian chronosequence. Chemical GeologyUranium isotopic evidence for the origin of the Bahariya iron deposits, Egypt. Ore Geology

Stewart, B.D.

2009-01-01T23:59:59.000Z

10

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

Science Journals Connector (OSTI)

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

A Meinrath; P Schneider; G Meinrath

2003-01-01T23:59:59.000Z

11

The coefficient of variation; a guide to the sampling of ore deposits  

Science Journals Connector (OSTI)

...deposits Reference Ore deposit C Homestake Saddle project, Nevada Loraine, SouthAfrica (basal reef). Freddle , South Africa President...vein) AMEXJoint Venture project, Crescent Valley, Nevada Loraine, South Africa (Breef) iRaridleases, South Africa (black...

George S. Koch; Richard F. Link

12

E-Print Network 3.0 - abandoned iron ore Sample Search Results  

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

these (now abandoned) ore deposits. ... Source: Connors, Christopher D. - Department of Geology, Washington and Lee University Collection: Geosciences 4 Chapter 2. Uranium Mining...

13

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

14

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

SciTech Connect (OSTI)

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

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

2014-04-01T23:59:59.000Z

15

A Study Of Scale Deposition- An Analogue Of Meso- To Epithermal Ore  

Open Energy Info (EERE)

Study Of Scale Deposition- An Analogue Of Meso- To Epithermal Ore Study Of Scale Deposition- An Analogue Of Meso- To Epithermal Ore Formation In The Volcano Of Milos, Aegean Arc, Greece Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: A Study Of Scale Deposition- An Analogue Of Meso- To Epithermal Ore Formation In The Volcano Of Milos, Aegean Arc, Greece Details Activities (0) Areas (0) Regions (0) Abstract: The viability of boiling as a mechanism for meso- to epithermal ore formation has been tested in the Milos volcano, Aegean Island Arc, by investigating rates of deposition and composition of scale, and by drawing an analogy between the results and actual field occurrences on the island. Milos offers ideal conditions for such testing: it consists of predominantly felsic volcanic rocks with numerous late-stage hydrovolcanic

16

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

17

A Geostatistical Study of the Uranium Deposit at Kvanefjeld,  

E-Print Network [OSTI]

with the geology. It is also shown that, although anisotropy exists, the uranium variation has a secondRisa-R-468 A Geostatistical Study of the Uranium Deposit at Kvanefjeld, The Ilimaussaq Intrusion A GEOSTATISTICAL STUDY OF THE URANIUM DEPOSIT AT KVANEFJELD, THE ILIMAUSSAQ INTRUSION, SOUTH GREENLAND Flemming

18

Nuclear Fuel Facts: Uranium | Department of Energy  

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

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

19

Geology and recognition criteria for sandstone uranium deposits in mixed fluvial-shallow marine sedimentary sequences, South Texas. Final report  

SciTech Connect (OSTI)

Uranium deposits in the South Texas Uranium Region are classical roll-type deposits that formed at the margin of tongues of altered sandstone by the encroachment of oxidizing, uraniferous solutions into reduced aquifers containing pyrite and, in a few cases, carbonaceous plant material. Many of the uranium deposits in South Texas are dissimilar from the roll fronts of the Wyoming basins. The host sands for many of the deposits contain essentially no carbonaceous plant material, only abundant disseminated pyrite. Many of the deposits do not occur at the margin of altered (ferric oxide-bearing) sandstone tongues but rather occur entirely within reduced, pyurite-bearing sandstone. The abundance of pyrite within the sands probably reflects the introduction of H/sub 2/S up along faults from hydrocarbon accumulations at depth. Such introductions before ore formation prepared the sands for roll-front development, whereas post-ore introductions produced re-reduction of portions of the altered tongue, leaving the deposit suspended in reduced sandstone. Evidence from three deposits suggests that ore formation was not accompanied by the introduction of significant amounts of H/sub 2/S.

Adams, S.S.; Smith, R.B.

1981-01-01T23:59:59.000Z

20

Uranium and Thorium Ores Price List | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

and and Thorium Ores Price List New Brunswick Laboratory (NBL) NBL Home About Programs Certified Reference Materials (CRMs) Prices and Certificates Ordering Information Training Categorical Exclusion Determinations News Contact Information New Brunswick Laboratory U.S. Department of Energy Building 350 9800 South Cass Avenue Argonne, IL 60439-4899 P: (630) 252-2442 (NBL) P: (630) 252-2767 (CRM sales) F: (630) 252-6256 E: usdoe.nbl@ch.doe.gov Prices and Certificates Uranium and Thorium Ores Price List Print Text Size: A A A RSS Feeds FeedbackShare Page NOTE: These costs reflect pricing for CRMs shipped to U.S. addresses. Prices for CRMs shipped to non-U.S. addresses can be found on the International Price List. (Prices are valid December 1, 2012, through December 31, 2013)

Note: This page contains sample records for the topic "uranium ore deposits" 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

The Francevillian (Lower Proterozoic) uranium ore deposits of Gabon  

Science Journals Connector (OSTI)

...Vienna, Inter- nat. Atomic Energy Agency, p. 513-520. FRANCEVILLIANUDEPOSITS...Vienna, Internat. Atomic Energy Agency,p. 307-332. Weber...geothermalenergyresources:Geothermic Spec. Issue2, v. 1, p...Vienna, Internat. Atomic Energy Agency, p. 375-395.

F. Gauthier-Lafaye; F. Weber

22

Nopal I uranium deposit: A study of radionuclide migration  

SciTech Connect (OSTI)

This summary reports on activities of naturally-occurring radionuclides for the Nopal I uranium deposit located in the Pena Blanca Uranium District, Chihuahua, Mexico. Activities were determined using gamma-ray spectroscopy. In addition, data reduction procedures and sample preparation (for Rn retention) will be discussed here. Nopal I uranium deposit has been identified as one of the most promising sites for analogue studies to the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. The objective of this research is to study the potential for radionuclide migration by testing whether any portion of the deposit is in secular equilibrium.

Wong, V.; Anthony, E.; Goodell, P. [Univ. of Texas, El Paso, TX (United States)

1996-12-01T23:59:59.000Z

23

Stratigraphy of the PB-1 well, Nopal I uranium deposit, Sierra Pena Blanca, Chihuahua, Mexico  

E-Print Network [OSTI]

P.C. , 1981, Geology of the Peña Blanca uranium deposits,uranium mineralizations in the Sierra Peña Blanca district, Chihuahua, Mexico: Three genetic models: Economic Geology,

Dobson, P.

2009-01-01T23:59:59.000Z

24

Correlation between lead isotopes in Mexican ore deposits and tectono-stratigraphic terranes  

SciTech Connect (OSTI)

The systematics of lead isotopes are now sufficiently understood that they can sometimes fingerprint the source of lead in ore deposits. Previous studies of lead isotopes in galena of 34 Mexican ore-deposits showed that the deposits could be clustered on the basis of their lead isotopic composition. Here they authors show that the lead isotopic signature of the Mexican deposits is independent of geologic setting but is unambiguously related to the tectono-stratigraphic terrane that hosts the deposit. Four distinct clusters in 207/204Pb vs 206/204Pb and 208/204Pb vs 206/204Pb space correlate with the newly defined Guerrero, Chihuahua, Sierra Madre and Coahuila tectono-stratigraphic terranes. The least radiogenic lead is found in deposits of the Chihuahua terrane. The Sierra Madre terrane contains the most radiogenic lead. The crustal source of lead that produced the isotopic cluster of each terrane is consistent with the nature of the terrane's basement rocks, as deduced from geologic interpretations. Thus, for the Chihuahua terrane, the isotopic data is consistent with the North American craton as the lead source; for the Sierra madre terrane, which is a composite terrane thought to be formed by displaced fragments of old continental crust, the source of lead agrees with Doe and Zartman's (1979) cratonized or uncratonized crust. This crust, however, is different in isotopic composition to that underlying the Chihuahua terrane. For the Coahuila terrane, the source is consistent with uncratonized crust; and for the Guerrero terrane, the data agrees with a source composed of mature arc volcanic-sedimentary rock sequences.

Ruiz, J.; Coney, P.

1985-01-01T23:59:59.000Z

25

Criticality safety concerns of uranium deposits in cascade equipment  

SciTech Connect (OSTI)

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

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

1996-12-31T23:59:59.000Z

26

Chapter 2. Uranium Mining and Extraction Processes in the United States In 1946, Congress passed the Atomic Energy Act (AEA), establishing the Atomic Energy Commission  

E-Print Network [OSTI]

it is managed. This chapter examines the location and geology of uranium deposits in the United States, the methods used to mine uranium, and the methods used to extract it from ore. Many of the geological, the characteristic geologic forms of uranium ore bodies were small to moderate-sized isolated pods or linear sinuous

27

Mineral paragenesis and textures associated with sandstone-hosted roll-front uranium deposits, NW China  

E-Print Network [OSTI]

, People's Republic of China c Northwest Institute of Uranium Geology, China National Nuclear CorporationMineral paragenesis and textures associated with sandstone-hosted roll-front uranium deposits, NW, Wuyiyi and Shihongtan sandstone-hosted roll-front uranium deposits, northwest China. The mineralization

Fayek, Mostafa

28

E-Print Network 3.0 - antei uranium deposit Sample Search Results  

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

Search Powered by Explorit Topic List Advanced Search Sample search results for: antei uranium deposit Page: << < 1 2 3 4 5 > >> 1 geology and Ranger 1 open-pit uranium mine in...

29

Uranium deposition study on aluminum: results of early tests  

SciTech Connect (OSTI)

Laboratory experiments to quantify uranium compound deposition on Aluminum 3003 test coupons have been initiated. These experiments consist of exposing the coupons to normal assay UF/sub 6/ (0.7% /sup 235/U) in nickel reaction vessels under various conditions of UF/sub 6/ pressure, temperature, and time. To-date, runs from 5 minutes to 2000 hr have been completed at a UF/sub 6/ pressure of 100 torr and at a temperature of 60/sup 0/C. Longer exposure times are in progress. Initial results indicated that a surface film of uranium, primarily as uranyl fluoride (UO/sub 2/F/sub 2/), is deposited very soon after exposure to UF/sub 6/. In a five minute UF/sub 6/ exposure at a temperature of 60/sup 0/C, an average of 2.9 ..mu..g U/cm/sup 2/ was deposited; after 24 hr the deposit typically increased to 5.0 ..mu..g/cm/sup 2/ and then increased to 10.4 ..mu..g/cm/sup 2/ after 2000 hr. This amount of deposit (at 2000 hr exposure) would contribute roughly 10 to 20% to the total 186 keV gamma signal obtained from a GCEP product header pipe being operated at UF/sub 6/ pressures of 2 to 5 torr. The amount of isotopic exchange which would occur in the deposit in the event that HEU and LEU productions were alternated is considered. It is felt that isotopic exchange would not occur to any significant amount within the fixed deposit during relatively short HEU production periods since the HEU would be present primarily as adsorbed UF/sub 6/ molecules on the surface of the deposit. The adsorbed HEU molecules would be removed by evacuation and diluted by LEU production. Major increases in the deposit count would be observed if a leak occurred or moisture was introduced into the system while HEU was being produced.

Hughes, M.R.; Nolan, T.A.

1984-06-19T23:59:59.000Z

30

STRATIGRAPHY OF THE PB-1 WELL, NOPAL I URANIUM DEPOSIT, SIERRA PENA BLANCA, CHIHUAHUA, MEXICO  

SciTech Connect (OSTI)

Three wells, PB-1, PB-2, and PB-3, were drilled in 2003 at the Nopal I uranium deposit as part of a natural analogue study to evaluate radionuclide transport processes. The wells penetrate through the Tertiary volcanic section down to the Cretaceous limestone basement, and intersect the top of the regional aquifer system. The PB-1 well, drilled immediately adjacent to the Nopal I ore body, was cored to a depth of 250 m, thus providing an opportunity to document the local stratigraphy. The uppermost unit encountered in the PB-1 well is the Nopal Formation, a densely welded, crystal-rich rhyolitic ash-flow tuff. The cored section is highly altered and devitrified, with kaolinite, quartz, chlorite, and montmorillonite replacing feldspars and much of the groundmass. Breccia zones within the tuff contain fracture fillings of hematite, limonite, and goethite. A zone of intense clay alteration encountered in the depth interval 17.45-22.30 m was interpreted to represent the basal vitrophyre of this unit. Underlying the basal vitrophyre is the Coloradas Formation, which consists of a welded, lithic-rich rhyolitic ash-flow tuff. The cored section of this unit has undergone devitrification and oxidation, and has a similar alteration mineralogy to that observed in the Nopal tuff. The Nopal I ore body is restricted to a brecciated zone that intersects these two volcanic units. A sharp contact between the Coloradas tuff and the underlying Pozos Formation was observed at a depth of 136.38 m. The Pozos Formation in the PB-1 core consists of interbedded, poorly sorted sandstone and conglomerate layers. The conglomeratic clasts consist of subangular to subrounded fragments of volcanic rocks, limestone, and chert. Thin (2-6 m) intervals of intercalated pumiceous tuffs were observed within this unit. The contact between the Pozos Formation and the underlying Cretaceous limestone basement was observed at a depth of 244.4 m.

NA

2005-06-25T23:59:59.000Z

31

Geochemical anomalies in soil and sandstone overlying the Phoenix uranium deposit, Athabasca Basin Natural Resources  

E-Print Network [OSTI]

Co Mo Ni UU Geochemical anomalies in soil and sandstone overlying the Phoenix uranium deposit, Athabasca Basin Natural Resources Canada Geological Survey of Canada with Provincial and Territorial Collaboration Introduction The Wheeler River Property, host of Denison Mine's Phoenix uranium deposit

32

A study of uranium distribution in an upper Jackson lignite-sandstone ore body, South Texas  

E-Print Network [OSTI]

in the caprock of the Palangana salt dome (Weeks and Eargl e, 1960) . Many of the deposits are located at depths too great for open- pi t mining, and ' n situ leaching is being attempted . As this method advances the Duval district will undoubtably gain... in the caprock of the Palangana salt dome (Weeks and Eargl e, 1960) . Many of the deposits are located at depths too great for open- pi t mining, and ' n situ leaching is being attempted . As this method advances the Duval district will undoubtably gain...

Chatham, James Randall

2012-06-07T23:59:59.000Z

33

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

SciTech Connect (OSTI)

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

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

1980-09-01T23:59:59.000Z

34

The geochemistry of uranium in the Orca Basin  

E-Print Network [OSTI]

inhibit=. vertical mixing between basin brine and overlying seawater. This severely limits the transport of hexa- valent uranium across this boundary. Second, the major depositional process in the basin is mass transport of sediments from... The continuing growth of nuclear power combined with the steady depletion of existing high-grade uranium ore has brought about an increase in the use of and search for lower-grade uranium deposits. According to Lieberman (1976), there is little undiscovered...

Weber, Frederick Fewell

2012-06-07T23:59:59.000Z

35

INITIAL TEST WELL CONDITIONING AT NOPAL I URANIUM DEPOSIT, SIERRA PENA BLANCA, CHIHUAHUA, MEXICO  

SciTech Connect (OSTI)

Three test wells, PB-1, PB-2, and PB-3, were drilled at the Nopal I uranium deposit as part of a natural analogue study to evaluate radionuclide transport processes during March-April 2003. The initial pumping to condition the wells was completed during December 2003. The PB-1 well, drilled immediately adjacent to the Nopal I ore body, was continuously cored to a depth of 250 m, terminating 20 m below the top of the measured water level. The PB-2 and PB-3 wells, which were drilled on opposite sides of PB-1 at a radial distance of approximately 40 to 50 m outside of the remaining projected ore body, were also drilled to about 20 m below the top of the measured water level. Each test well was completed with 4-inch (10.2-cm) diameter PVC casing with a slotted liner below the water table. Initial conditioning of all three wells using a submersible pump at low pump rates [less than 1 gallon (3.8 1) per minute] resulted in measurable draw down and recoveries. The greatest drawdown ({approx}15 m) was observed in PB-2, whereas only minor (<1 m) drawdown occurred in PB-3. For PB-1 and PB-2, the water turbidity decreased as the wells were pumped and the pH values decreased, indicating that the contamination from the drilling fluid was reduced as the wells were conditioned. Test wells PB-1 and PB-2 showed increased inflow after several borehole volumes of fluid were removed, but their inflow rates remained less that the pumping rate. Test well PB-3 showed the smallest drawdown and least change in pH and conductivity during initial pumping and quickest recovery with a rise in measured water level after conditioning. The 195 gallons (750 l) of water pumped from PB-3 during conditioning was discharged through a household sponge. That sponge showed measurable gamma radiation, which decayed to background values in less than 12 hours. Preliminary interpretations include filtration of a radioisotope source with a short half-life or of a radioisotope that volatized as the sponge dried, such as Rn-222 and its short-lived daughters. No filtration was used during the pumping of PB-1 or PB-2.

R.D. Oliver; J.C. Dinsmoor; S.J. Goldstein; I. Reyes; R. De La Garza

2005-07-11T23:59:59.000Z

36

O and Pb isotopic analyses of uranium minerals by ion microprobe and UPb ages from the Cigar Lake deposit  

E-Print Network [OSTI]

O and Pb isotopic analyses of uranium minerals by ion microprobe and U­Pb ages from the Cigar Lake intergrown uranium minerals and oxygen isotopic analyes of uraninite from the unconformity-type Cigar Lake uranium deposit. Secondary uranium minerals intergrown with uraninite, such as coffinite, USiO4ÁnH2O

Fayek, Mostafa

37

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

E-Print Network [OSTI]

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

Fayek, Mostafa

38

Mineralogical analysis and uranium distribution of the sediments from the upper Jackson formation, Karnes County, Texas  

E-Print Network [OSTI]

of the relationship between uranium distribu- tion and mineralogic composition of the sediment may provide more reliable methods for uranium exploration. Open pit mining and subsequent milling, or in situ leach- ing, are the two methods of uranium recovery... of the oxidized deposits, at and directly above the water table, are larger deposits of generally lower-grade ore that contains unoxidized uranium. The Galen Mine was the first mine in the unoxidized ore. This open pit mine is about two miles (3 km) south...

Fishman, Paul Harold

1978-01-01T23:59:59.000Z

39

Geology, isotope geochemistry and ore genesis of the Shanshulin carbonate-hosted Pb–Zn deposit, southwest China  

Science Journals Connector (OSTI)

Abstract The Shanshulin Pb–Zn deposit occurs in Upper Carboniferous Huanglong Formation dolomitic limestone and dolostone, and is located in the western Yangtze Block, about 270 km west of Guiyang city in southwest China. Ore bodies occur along high angle thrust faults affiliated to the Weishui regional fault zone and within the northwestern part of the Guanyinshan anticline. Sulfide ores are composed of sphalerite, pyrite, and galena that are accompanied by calcite and subordinate dolomite. Twenty-two ore bodies have been found in the Shanshulin deposit area, with a combined 2.7 million tonnes of sulfide ores grading 0.54 to 8.94 wt.% Pb and 1.09 to 26.64 wt.% Zn. Calcite samples have ?13CPDB and ?18OSMOW values ranging from ? 3.1 to + 2.5‰ and + 18.8 to + 26.5‰, respectively. These values are higher than mantle and sedimentary organic matter, but are similar to marine carbonate rocks in a ?13CPDB vs. ?18OSMOW diagram, suggesting that carbon in the hydrothermal fluid was most likely derived from the carbonate country rocks. The ?34SCDT values of sphalerite and galena samples range from + 18.9 to + 20.3‰ and + 15.6 to + 17.1‰, respectively. These values suggest that evaporites are the most probable source of sulfur. The ?34SCDT values of symbiotic sphalerite–galena mineral pairs indicate that deposition of sulfides took place under chemical equilibrium conditions. Calculated temperatures of S isotope thermodynamic equilibrium fractionation based on sphalerite–galena mineral pairs range from 135 to 292 °C, consistent with previous fluid inclusion studies. Temperatures above 100 °C preclude derivation of sulfur through bacterial sulfate reduction (BSR) and suggest that reduced sulfur in the hydrothermal fluid was most likely supplied through thermo-chemical sulfate reduction (TSR). Twelve sphalerite samples have ?66Zn values ranging from 0.00 to + 0.55‰ (mean + 0.25‰) relative to the JMC 3-0749L zinc isotope standard. Stages I to III sphalerite samples have ?66Zn values ranging from 0.00 to + 0.07‰, + 0.12 to + 0.23‰, and + 0.29 to + 0.55‰, respectively, showing the relatively heavier Zn isotopic compositions in later versus earlier sphalerite. The variations of Zn isotope values are likely due to kinetic Raleigh fractional crystallization. The 206Pb/204Pb, 207Pb/204Pb and 208Pb/204Pb ratios of the sulfide samples fall in the range of 18.362 to 18.573, 15.505 to 15.769 and 38.302 to 39.223, respectively. The Pb isotopic ratios of the studied deposit plot in the field that covers the upper crust, orogenic belt and mantle Pb evolution curves and overlaps with the age-corrected Proterozoic folded basement rocks, Devonian to Lower Permian sedimentary rocks and Middle Permian Emeishan flood basalts in a 207Pb/204Pb vs. 206Pb/204Pb diagram. This observation points to the derivation of Pb metal from mixed sources. Sphalerite samples have 87Sr/86Sr200 Ma ratios ranging from 0.7107 to 0.7115 similar to the age-corrected Devonian to Lower Permian sedimentary rocks (0.7073 to 0.7111), higher than the age-corrected Middle Permian basalts (0.7039 to 0.7078), and lower than the age-corrected Proterozoic folded basement (0.7243 to 0.7288). Therefore, the Sr isotope data support a mixed source. Studies on the geology and isotope geochemistry suggest that the Shanshulin deposit is a carbonate-hosted, thrust fault-controlled, strata-bound, epigenetic, high grade deposit formed by fluids and metals of mixed origin.

Jia-Xi Zhou; Zhi-Long Huang; Zhi-Cheng Lv; Xiang-Kun Zhu; Jian-Guo Gao; Hassan Mirnejad

2014-01-01T23:59:59.000Z

40

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

SciTech Connect (OSTI)

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

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

2005-07-11T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

Stratigraphy of the PB-1 well, Nopal I uranium deposit, Sierra Pena Blanca, Chihuahua, Mexico  

SciTech Connect (OSTI)

The Nopal I site in the Pena Blanca uranium district has a number of geologic and hydrologic similarities to the proposed high-level radioactive waste repository at Yucca Mountain, making it a useful analogue to evaluate process models for radionuclide transport. The PB-1 well was drilled in 2003 at the Nopal I uranium deposit as part of a DOE-sponsored natural analogue study to constrain processes affecting radionuclide transport. The well penetrates through the Tertiary volcanic section down to Cretaceous limestone and intersects the regional aquifer system. The well, drilled along the margin of the Nopal I ore body, was continuously cored to a depth of 250 m, thus providing an opportunity to document the local stratigraphy. Detailed observations of these units were afforded through petrographic description and rock-property measurements of the core, together with geophysical logs of the well. The uppermost unit encountered in the PB-1 well is the Nopal Formation, a densely welded, crystal-rich, rhyolitic ash-flow tuff. This cored section is highly altered and devitrified, with kaolinite, quartz, chlorite, and montmorillonite replacing feldspars and much of the groundmass. Breccia zones within the tuff contain fracture fillings of hematite, limonite, goethite, jarosite, and opal. A zone of intense clay alteration encountered in the depth interval 17.45-22.30 m was interpreted to represent the basal vitrophyre of this unit. Underlying the Nopal Formation is the Coloradas Formation, which consists of a welded lithic-rich rhyolitic ash-flow tuff. The cored section of this unit has undergone devitrification and oxidation, and has a similar alteration mineralogy to that observed in the Nopal tuff. A sharp contact between the Coloradas tuff and the underlying Pozos Formation was observed at a depth of 136.38 m. The Pozos Formation consists of poorly sorted conglomerate containing clasts of subangular to subrounded fragments of volcanic rocks, limestone, and chert. Three thin (2-6 m) intervals of intercalated pumiceous tuffs were observed within this unit. The contact between the Pozos Formation and the underlying Cretaceous limestone basement was observed at a depth of 244.40 m. The water table is located at a depth of {approx}223 m. Several zones with elevated radioactivity in the PB-1 core are located above the current water table. These zones may be associated with changes in redox conditions that could have resulted in the precipitation of uraninite from downward flowing waters transporting U from the overlying Nopal deposit. All of the intersected units have low (typically submillidarcy) matrix permeability, thus fluid flow in this area is dominated by fracture flow. These stratigraphic and rock-property observations can be used to constrain flow and transport models for the Pena Blanca natural analogue.

Dobson, P.; Fayek, M.; Goodell, P.; Ghezzehei, T.; Melchor, F.; Murrell, M.; Oliver, R.; Reyes-Cortes, I.A.; de la Garza, R.; Simmons, A.

2008-08-01T23:59:59.000Z

42

Mobile Pb-isotopes in Proterozoic sedimentary basins as guides for exploration of uranium deposits  

E-Print Network [OSTI]

Mobile Pb-isotopes in Proterozoic sedimentary basins as guides for exploration of uranium deposits of Geological Sciences, California State University, Long Beach, 1250 Bellflower Blvd., Long Beach, CA 90840, USA b Department of Geological Sciences and Geological Engineering, Queen's University, Kingston

Hiatt, Eric E.

43

Uranium in the Oatman Creek granite of Central Texas and its economic potential  

E-Print Network [OSTI]

granitic rocks are enriched in uranium. Although at present uranium in granites cannot b compared w1th the h1gh grade concentrat1ons of uran1um in sedimentary rocks, as these h1gh grade ore deposits become depleted, however, gr anites will become a..., however, the need to explore for new materials containing uranium will incr ease as the high grade sedimentary uranium deposits become depleted. A logical place to begin this search lies with the source rock for many of the known sedimentary uranium...

Conrad, Curtis Paul

2012-06-07T23:59:59.000Z

44

Radionuclides in the terrestrial ecosystem near a Canadian uranium mill -- Part 3: Atmospheric deposition rates (pilot test)  

SciTech Connect (OSTI)

Atmospheric deposition rates of uranium series radionuclides were directly measured at three sites near the operating Key Lake uranium mill in northern Saskatchewan. Sites impacted by windblown tailings and mill dusts had elevated rates of uranium deposition near the mill and elevated {sup 226}Ra deposition near the tailings compared to a control site. Rainwater collectors, dust jars, and passive vinyl collectors previously used at the Ranger Mine in Australia were pilot-tested. Adhesive vinyl surfaces (1 m{sup 2}) were oriented horizontally, vertically, and facing the ground as a means of measuring gravitational settling, wind impaction, and soil resuspension, respectively. Although the adhesive glue on the vinyls proved difficult to digest, relative differences in deposition mode were found among radionuclides and among sites. Dry deposition was a more important transport mechanism for uranium, {sup 226}Ra, and {sup 210}Pb than rainfall, while more {sup 210}Po was deposited with rainfall.

Thomas, P.A.

2000-06-01T23:59:59.000Z

45

Radioecological Assessment of a Uranium Deposit for Validation of the Radiation-Migration Balance of Long-Lived Wastes  

Science Journals Connector (OSTI)

The irradiation dose to man along different pathways for exposure to radionuclides from deep and surface uranium deposits in the case the radionuclides emerge at the soil surface is determined. It is found tha...

E. V. Spirin; S. I. Spiridonov; R. M. Alexakhin; S. S. Utkin

2013-05-01T23:59:59.000Z

46

Geology and recognition criteria for uranium deposits of the quartz-pebble conglomerate type. Final report  

SciTech Connect (OSTI)

This report is concerned with Precambrian uraniferous conglomerates. This class of deposit has been estimated to contain between approximately 16 and 35 percent of the global uranium reserve in two rather small areas, one in Canada, the other in South Africa. Similar conglomerates, which are often gold-bearing, are, however, rather widespread, being found in parts of most Precambrian shield areas. Data have been synthesized on the geologic habitat and character of this deposit type. The primary objective has been to provide the most relevant geologic observations in a structural fashion to allow resource studies and exploration to focus on the most prospective targets in the shortest possible time.

Button, A.; Adams, S.S.

1981-03-01T23:59:59.000Z

47

EPA Update: NESHAP Uranium Activities  

E-Print Network [OSTI]

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

48

Borehole Logging Methods for Exploration and Evaluation of Uranium Deposits (1967)  

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

Borehole logging methods for exploration Borehole logging methods for exploration and evaluation o f uranium deposits . Philip H. O d d , Robert F. Bmullad and Carl P. Lathan rej~rinkttl fnlm Mining and Groundwater Geophysiall967 Borehole logging methods for exploration and evaluation of uranium deposits Philip H. Dodd, Robert F. Droullard and Carl P. Lathan US. Atomic Energy Commhwn GmrPd Jtinct&n, Colorado Abstract, M o l e 1 - i s thc geophysical methad mast exten&@ w r t i n the Udtrrd States for exploratio~ md edwtim of wanhi &pod&. dammow lop, C o r n r n d j suppkrnentd with a singbz-pobt msfstailee log, m t l y supply about 80 percent of the bask data for om regerve c W t i o R a d mu& of the w ~ k r 6 . p ~ &ngk inf~nnatio~ Tmck-mounted 'rotmy eqnipmcnt i s EMhmody emphy&& holes usually hwre a nominai b

49

Uranium Mining and Enrichment  

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

50

Ore mineralization related to geological evolution of the Karkonosze–Izera Massif (the Sudetes, Poland) — Towards a model  

Science Journals Connector (OSTI)

Abstract The Karkonosze–Izera Massif is a large tectonic unit located in the northern periphery of the Bohemian Massif. It includes the Variscan Karkonosze Granite (about 328–304 Ma) surrounded by the following four older units:- Izera–Kowary (the Early Paleozoic continental crust of the Saxothuringian Basin), - Ješt?d (the Middle Devonian to Lower Viséan sedimentary succession deposited on the NE passive margin of the Saxothuringian Terrane), out of the present study area, - Southern Karkonosze (metamorphosed sediments and volcanics filling the Saxothuringian Basin), out of the present study area, - Leszczyniec (Early Ordovician, obducted fragment of Saxothuringian Basin sea floor). The authors present a genetic model of ore mineralization in the Karkonosze–Izera Massif, in which ore deposits and ore minerals occurrences are related to the successive episodes of the geological history of the Karkonosze–Izera Massif:- formation of the Saxothuringian Basin and its passive continental margin (about 500–490 Ma) - Variscan thermal events:- regional metamorphism (360–340 Ma) - Karkonosze Granite intrusion (328–304 Ma) - Late Cretaceous and Neogene-to-Recent hypergenic processes. The oldest ore deposits and ore minerals occurrences of the Karkonosze–Izera Massif are represented by pyrite and magnetite deposits hosted in the Leszczyniec Unit as well as by magnetite deposit and, presumably, by a small part of tin mineralization hosted in the Izera–Kowary Unit. All these deposits and occurrences were subjected to the pre-Variscan regional metamorphism. Most of the Karkonosze–Izera Massif ore deposits and occurrences are related to the Karkonosze Granite intrusion. This group includes a spatially diversified assemblage of small ore deposits and ore mineral occurrences of: Fe, Cu, Sn, As, U, Co, Au, Ag, Pb, Ni, Bi, Zn, Sb, Se, S, Th, REE, Mo, W and Hg located within the granite and in granite-related pegmatites, in the close contact aureole of the granite and within the metamorphic envelope, at various distances from the granite. Assuming world standards, all these deposits are now uneconomic. Various age determinations indicated that ore formation connected with the Karkonosze Granite might have taken place mostly between about 326 and 270 Ma. The last ore-forming episode in the Karkonosze–Izera Massif is related to hypergenic processes, particularly important in the northern part of the massif, in the Izera–Kowary Unit where some uranium deposits and occurrences resulted from the infiltration of ore solutions that originated from the weathering of pre-existing accumulations of uranium minerals. A separate problem is the presence of oxidation zones of ore deposits and occurrences, both the fossil and the recent. A full list of ore minerals identified in described deposits and occurrences of the Karkonosze–Izera Massif together with relevant, key references is presented in the form of an appendix.

Ksenia Mochnacka; Teresa Oberc-Dziedzic; Wojciech Mayer; Adam Pieczka

2015-01-01T23:59:59.000Z

51

Exploration for Uranium Ore (Virginia)  

Broader source: Energy.gov [DOE]

This legislation describes permitting procedures and requirements for exploration activities. For the purpose of this legislation, exploration is defined as the drilling of test holes or...

52

Geographical Coincidence of High Heat Flow, High Seismicity, and Upwelling, with Hydrocarbon Deposits, Phosphorites, Evaporites, and Uranium Ores  

Science Journals Connector (OSTI)

...sea and seismicity and geothermal heat flux. We suggest...upwelling caused by the geothermal heat (2), which brings...sedimentary rocks. High geothermal heat fluxes correlate...Lawrence River, as well as a fourth line along...Arizona, Montana, New Mexico, and Utah. Lignites...

L. M. Libby; W. F. Libby

1974-01-01T23:59:59.000Z

53

Origin of the ore-forming fluids of the Tongchang porphyry Cu–Mo deposit in the Jinshajiang–Red River alkaline igneous belt, SW China: Constraints from He, Ar and S isotopes  

Science Journals Connector (OSTI)

The Jinshajiang–Red River alkaline igneous belt with abundant Cu–Mo–Au mineralization, in the eastern Indian–Asian collision zone, is an important Cenozoic magmatic belt formed under an intra-continental strike-slip system in southwestern (SW) China. The Tongchang deposit is a representative porphyry Cu–Mo deposit in southern segment of the Jinshajiang–Red River alkaline igneous belt, with 8621 t Cu @ 1.24 wt.% and 17,060 t Mo @ 0.218 wt.%. In this study, He, Ar and S isotopic compositions of the Tongchang deposit were determined. He and Ar isotopic compositions suggest that the ore-forming fluids, with 3He/4He ratios varying from 0.17 to 1.50 Ra and 40Ar/36Ar ratios from 299.1 to 347.3 for the deposit, are a mixture between a crust-derived fluid (MASW) with near atmospheric Ar and crustal He, and a mantle-derived fluid. However, the ?34S values of the hydrothermal pyrite samples ranging from 1.0‰ to 1.5‰ with an average of 1.2‰, indicate that the sulfur in the ore-forming fluids of the Tongchang deposit was primarily derived from the magma or indirectly mantle-derived without assimilation of crustal sulfur. In combination with previously published He and Ar isotopic data of the Yulong and Machangqing deposits in northern and central segments of the Jinshajiang–Red River alkaline igneous belt, respectively, the ore-forming fluids of the Yulong and Machangqing deposits are obviously richer in 3He and 40Ar, and poorer in 36Ar in comparison with the Tongchang deposit, implying that more mantle-derived fluids were involved in the ore-forming fluids of the Yulong and Machangqing deposits than those for the Tongchang deposit. This might be one of the most important factors producing larger scales of mineralization in the Yulong and Machangqing deposits than the Tongchang deposit.

Leiluo Xu; Xianwu Bi; Ruizhong Hu; Yongyong Tang; Guohao Jiang; Youqiang Qi

2014-01-01T23:59:59.000Z

54

U.S. Uranium Reserves Estimates  

Gasoline and Diesel Fuel Update (EIA)

2. U.S. Forward-Cost Uranium Reserves by Mining Method, Year-End 2008 Mining Method 50 per pound 100 per pound Ore (million tons) Gradea (percent U3O8) U3O8 (million pounds) Ore...

55

U.S. Uranium Reserves Estimates  

Gasoline and Diesel Fuel Update (EIA)

1. U.S. Forward-Cost Uranium Reserves by State, Year-End 2008 State 50lb 100lb Ore (million tons) Gradea (%) U3O8 (million lbs) Ore (million tons) Gradea (%) U3O8 (million lbs)...

56

Structural Sequestration of Uranium in Bacteriogenic Manganese...  

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

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

57

DOE - Office of Legacy Management -- Shirley Basin AEC Ore Buying...  

Office of Legacy Management (LM)

Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and...

58

DOE - Office of Legacy Management -- Shiprock AEC Ore Buying...  

Office of Legacy Management (LM)

Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and...

59

DOE - Office of Legacy Management -- Grants AEC Ore Buying Station...  

Office of Legacy Management (LM)

Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and...

60

DOE - Office of Legacy Management -- Salt Lake City AEC Ore Buying Station  

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

AEC Ore Buying AEC Ore Buying Station - UT 0-03 FUSRAP Considered Sites Site: Salt Lake City AEC Ore Buying Station (UT.0-03 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The ideal scenario was to accumulate a sufficient stockpile of ore and

Note: This page contains sample records for the topic "uranium ore deposits" 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

DOE - Office of Legacy Management -- Mexican Hat AEC Ore Buying Station -  

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

AEC Ore Buying Station AEC Ore Buying Station - UT 0-02 FUSRAP Considered Sites Site: Mexican Hat AEC Ore Buying Station (UT.0-02) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The ideal scenario was to accumulate a sufficient stockpile of ore and

62

DOE - Office of Legacy Management -- Tuba City AEC Ore Buying Station - AZ  

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

AEC Ore Buying Station - AEC Ore Buying Station - AZ 0-02A FUSRAP Considered Sites Site: Tuba City AEC Ore Buying Station (AZ.0-02A) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The ideal scenario was to accumulate a sufficient stockpile of ore and

63

DOE - Office of Legacy Management -- Marysville AEC Ore Buying Station - UT  

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

Marysville AEC Ore Buying Station - Marysville AEC Ore Buying Station - UT 05 FUSRAP Considered Sites Site: Marysville AEC Ore Buying Station (UT.05 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

64

DOE - Office of Legacy Management -- Monticello AEC Ore Buying Station - UT  

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

Monticello AEC Ore Buying Station - Monticello AEC Ore Buying Station - UT 03A FUSRAP Considered Sites Site: Monticello AEC Ore Buying Station (UT.03A ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

65

DOE - Office of Legacy Management -- Riverton AEC Ore Buying Station - WY  

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

Riverton AEC Ore Buying Station - Riverton AEC Ore Buying Station - WY 0-03 FUSRAP Considered Sites Site: Riverton AEC Ore Buying Station (WY.0-03 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

66

DOE - Office of Legacy Management -- Globe Cutter AEC Ore Buying Station -  

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

Globe Cutter AEC Ore Buying Station Globe Cutter AEC Ore Buying Station - AZ 03 FUSRAP Considered Sites Site: Globe (Cutter) AEC Ore Buying Station (AZ.03 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

67

DOE - Office of Legacy Management -- Blue Water AEC Ore Buying Station - NM  

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

Blue Water AEC Ore Buying Station - Blue Water AEC Ore Buying Station - NM 0-02 FUSRAP Considered Sites Site: Blue Water AEC Ore Buying Station (NM.0-02 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

68

DOE - Office of Legacy Management -- White Canyon AEC Ore Buying Station -  

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

White Canyon AEC Ore Buying Station White Canyon AEC Ore Buying Station - UT 04 FUSRAP Considered Sites Site: White Canyon AEC Ore Buying Station (UT.04) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

69

DOE - Office of Legacy Management -- Crooks Gap AEC Ore Buying Station - WY  

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

Crooks Gap AEC Ore Buying Station - Crooks Gap AEC Ore Buying Station - WY 0-02 FUSRAP Considered Sites Site: Crooks Gap AEC Ore Buying Station (WY.0-02 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The history of domestic uranium procurement under U.S. Atomic Energy Commission (AEC) contracts identifies a number of ore buying stations (sampling and storage sites) that were operated during the period late-1949 through the mid-1960s. During this period the AEC established ore-buying stations in new uranium producing areas where it appeared that ore production would be sufficient to support a uranium milling operation. The

70

Uranium and its relationship to host rock mineralogy in an unoxidized roll front in the Jackson group, South Texas  

E-Print Network [OSTI]

-to-the-coast antithetic fault. Fault sets of this tyoe have affected uranium mineralization by serving as conduits for the miqration of ore solutions and reductants (Eargle and Weeks, 1961; Dickinson and Duval, 1977). There are also many diapiric salt intrusions... in south Texas, though none occur in the area of the ore deposit studied. The intru- sions developed from gravitational instability caused by the rapid accu- mulation of Tertiary sediments on top of a Jurassic salt layer. Urani- um is not commonly...

Prasse, Eric Martin

2012-06-07T23:59:59.000Z

71

Uranium mineralization in fluorine-enriched volcanic rocks  

SciTech Connect (OSTI)

Several uranium and other lithophile element deposits are located within or adjacent to small middle to late Cenozoic, fluorine-rich rhyolitic dome complexes. Examples studied include Spor Mountain, Utah (Be-U-F), the Honeycomb Hills, Utah (Be-U), the Wah Wah Mountains, Utah (U-F), and the Black Range-Sierra Cuchillo, New Mexico (Sn-Be-W-F). The formation of these and similar deposits begins with the emplacement of a rhyolitic magma, enriched in lithophile metals and complexing fluorine, that rises to a shallow crustal level, where its roof zone may become further enriched in volatiles and the ore elements. During initial explosive volcanic activity, aprons of lithicrich tuffs are erupted around the vents. These early pyroclastic deposits commonly host the mineralization, due to their initial enrichment in the lithophile elements, their permeability, and the reactivity of their foreign lithic inclusions (particularly carbonate rocks). The pyroclastics are capped and preserved by thick topaz rhyolite domes and flows that can serve as a source of heat and of additional quantities of ore elements. Devitrification, vapor-phase crystallization, or fumarolic alteration may free the ore elements from the glassy matrix and place them in a form readily leached by percolating meteoric waters. Heat from the rhyolitic sheets drives such waters through the system, generally into and up the vents and out through the early tuffs. Secondary alteration zones (K-feldspar, sericite, silica, clays, fluorite, carbonate, and zeolites) and economic mineral concentrations may form in response to this low temperature (less than 200 C) circulation. After cooling, meteoric water continues to migrate through the system, modifying the distribution and concentration of the ore elements (especially uranium).

Burt, D.M.; Sheridan, M.F.; Bikun, J.; Christiansen, E.; Correa, B.; Murphy, B.; Self, S.

1980-09-01T23:59:59.000Z

72

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

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

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

73

DOE - Office of Legacy Management -- Palmerton Ore Buying Site - PA 33  

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

Palmerton Ore Buying Site - PA 33 Palmerton Ore Buying Site - PA 33 FUSRAP Considered Sites Site: PALMERTON ORE BUYING SITE (PA.33) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: New Jersey Zinc Company PA.33-1 Location: Palmerton , Pennsylvania PA.33-2 Evaluation Year: 1994 PA.33-3 Site Operations: Mid-1950s - AEC leased the New Jersey Zinc Company property and established a uranium ore stockpile on the property in the vicinity of Palmerton, PA. PA.33-4 Site Disposition: Eliminated - Potential for residual contamination and resulting exposure beyond that associated with natural background radiation considered remote PA.33-3 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium Ore PA.33-4 Radiological Survey(s): Yes PA.33-5

74

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

Broader source: Energy.gov [DOE]

This EIS evaluated the potential 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.

75

Micropixe as a tool to search for uranium-bearing particles in lung tissues  

SciTech Connect (OSTI)

A proton microbeam is proposed as a tool to search for uranium-bearing particles in lung tissues. Preliminary experiments have been undertaken by irradiating with protons lung tissues of dogs previously exposed to uranium ore. 7 references.

Paschoa, A.S.; Wrenn, S.C.; Miller, M.E.; Jones, K.W.; Cholewa, M.; Hanson, A.L.

1982-01-01T23:59:59.000Z

76

An assessment of the radiological scenario around uranium mines in Singhbhum East district, Jharkhand, India  

Science Journals Connector (OSTI)

......storing low-specific active waste after the recovery of uranium...ore mining and radioactive waste around a storage centre from Mexico. Radioprotection...K., Puranik V. D. Long-term management of uranium mill waste: proposal for stewardship......

R. M. Tripathi; S. K. Sahoo; S. Mohapatra; A. C. Patra; P. Lenka; J. S. Dubey; V. N. Jha; V. D. Puranik

2012-07-01T23:59:59.000Z

77

Safeguards assessment of gamma-ray detection for process monitoring at natural uranium conversion facilities.  

E-Print Network [OSTI]

??Conversion, the process by which natural uranium ore (yellowcake) is puri?ed and converted through a series of chemical processes into uranium hexa?uoride gas (UF6), has… (more)

Dewji, Shaheen Azim

2014-01-01T23:59:59.000Z

78

Chapter 3. Volume and Characteristics of Uranium Mine Wastes Uranium has been found and mined in a wide variety of rocks, including sandstone, carbonates1  

E-Print Network [OSTI]

3-1 Chapter 3. Volume and Characteristics of Uranium Mine Wastes Uranium has been found and mined conventional mining, solution extraction, and milling of uranium, a principal focus of this report is TENORM, or which may need future reclamation. When uranium mining first started, most of the ores were recovered

79

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

80

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

Gasoline and Diesel Fuel Update (EIA)

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

Note: This page contains sample records for the topic "uranium ore deposits" 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

Uranium industry annual 1993  

SciTech Connect (OSTI)

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

82

Uranium Leasing Program: Program Summary | Department of Energy  

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

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

83

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

84

Depleted Uranium  

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

85

Swelling related to ettringite crystal formation in chromite ore processing residue  

Science Journals Connector (OSTI)

Several million tons of Chromite Ore Processing Residue (COPR) were deposited at two sites in New Jersey and Maryland, USA, and over time they exhibited extensive heaving phenomena. Ettringite, a needle-shaped mi...

Deok Hyun Moon; Dimitris Dermatas; Mahmoud Wazne…

2007-08-01T23:59:59.000Z

86

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

SciTech Connect (OSTI)

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

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

2013-11-01T23:59:59.000Z

87

Kumba Iron Ore | Open Energy Information  

Open Energy Info (EERE)

Kumba Iron Ore Jump to: navigation, search Name: Kumba Iron Ore Place: Pretoria, South Africa Zip: 175 Sector: Solar Product: South Africa based mining company. The firm is...

88

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"

89

Integrated hydrothermal model for proposed deep crustal borehole on Texas Gulf Coast - origins of geopressured brines and lead-zinc, uranium, hydrocarbon, and cap-rock deposits  

SciTech Connect (OSTI)

Sediment accumulation over Jurassic salt in the Gulf coast has resulted in an interrelated sequential development of salt domes and diagenetic, hydrothermal, and hydrocarbon generation zones. Primary anhydrites within the salt with high /sup 87/Sr//sup 86/Sr ratios suggest early generation of underlying fluids rich in radiogenic strontium that were incorporated in the salt during its diapiric rise to the surface. Subsequently, late-stage, hydrocarbon-rich, saline hydrothermal fluids migrated up the margins of the salt domes, and caused precipitation of several generation of calcite cements, followed by uranium and Mississippi Valley-type lead-zinc-barite deposits near or at salt dome rims. Present fluids in the lower Frio (deeper than 4270 m or 14,000 ft) at the Pleasant Bayou geopressured-geothermal test well (Brazoria County, Texas) are highly saline and enriched in iron, manganese, lead, zinc, and carbon dioxide, and are saturated in methane. These lower Frio waters must have migrated into the area recently because they are not in isotopic equilibrium with diagenetic albite cements formed at temperatures greater than 120/sup 0/C (248/sup 0/F) less than 7.5 million years ago. Isotopic and geochemical data suggest that the fluids trapped by geopressure in the lower Frio at the Pleasant Bayou well are the parent fluids of those causing salt dome cap-rock mineralization.

Light, M.P.R.; Posey, H.H.

1986-05-01T23:59:59.000Z

90

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

E-Print Network [OSTI]

boom starting immediately after World War II, making uranium the most important commodity in the mining). Some uranium mining continues in the United States, and relatively high-grade resources in other parts contained in the uranium nucleus.1 Another legacy of uranium exploration, mining, and ore processing were

91

Microbial reduction of iron ore  

DOE Patents [OSTI]

A process is provided for reducing iron ore by treatment with microorganisms which comprises forming an aqueous mixture of iron ore, microorganisms operable for reducing the ferric iron of the iron ore to ferrous iron, and a substrate operable as an energy source for the microbial reduction; and maintaining the aqueous mixture for a period of time and under conditions operable to effect the reduction of the ore. Preferably the microorganism is Pseudomonas sp. 200 and the reduction conducted anaerobically with a domestic wastewater as the substrate. An aqueous solution containing soluble ferrous iron can be separated from the reacted mixture, treated with a base to precipitate ferrous hydroxide which can then be recovered as a concentrated slurry.

Hoffmann, Michael R. (Pasadena, CA); Arnold, Robert G. (Pasadena, CA); Stephanopoulos, Gregory (Pasadena, CA)

1989-01-01T23:59:59.000Z

92

Microbial reduction of iron ore  

DOE Patents [OSTI]

A process is provided for reducing iron ore by treatment with microorganisms which comprises forming an aqueous mixture of iron ore, microorganisms operable for reducing the ferric iron of the iron ore to ferrous iron, and a substrate operable as an energy source for the microbial reduction; and maintaining the aqueous mixture for a period of time and under conditions operable to effect the reduction of the ore. Preferably the microorganism is Pseudomonas sp. 200 and the reduction conducted anaerobically with a domestic wastewater as the substrate. An aqueous solution containing soluble ferrous iron can be separated from the reacted mixture, treated with a base to precipitate ferrous hydroxide which can then be recovered as a concentrated slurry. 11 figs.

Hoffmann, M.R.; Arnold, R.G.; Stephanopoulos, G.

1989-11-14T23:59:59.000Z

93

Isotopic Fractionation of Uranium in Sandstone  

Science Journals Connector (OSTI)

...Lake district 2.3 284270 Uraninite ore, Gambler Pit, Karnes County, Tex. + 1.8 246885 Drill-core sample, Palangana Salt dome, Duval County, Tex 3.3 APP-1/62 Uranium-bearing asphaltite from sandstone, Mine LaMotte, Madison...

John N. Rosholt; William R. Shields; Ernest L. Garner

1963-01-18T23:59:59.000Z

94

E-Print Network 3.0 - aqueuous uranium complexes Sample Search...  

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

12;Breccia complex deposits: This is a type of uranium formations that occur near... Uranium geology and mining Ranger ... Source: Uppsala Universitet, Department of...

95

In situ exploitation of deep set porphyry ores  

SciTech Connect (OSTI)

Disclosed is a method of economically exploiting deep set porphyry ore bodies of the type containing metal values such as sulfidic copper, nickel, or uranium minerals and minerals capable of absorbing copper, uranium, and nickel ions. The method involves establishing communication with the ore body through access and recovery wells and passing fluids sequentially therethrough. If necessary, thief zones of as low as 25 to 50 md in igneous rock of 1 to 5 md are prevented from distorting flow, by the injection of a polymeric solution of macromolecules with molecular weights of the order of 5 million along the entire wellbore, the higher permeability zones initially accepting the majority of the flow and being impaired at a much faster rate than the less permeable zones. In a first stage, the permeability of the leaching interval is stimulated as an ammoniated solution of sodium, potassium, or ammonium nitrate or chloride contacts calcium containing minerals to promote ion exchange, resulting in clay contraction or calcium carbonate dissolution. In a second stage, the leaching interval is primed as calcium ion is displaced with an aqueous solution of ammonium salt, a calcium sulfate scale inhibitor, and oxygen gas. In a third stage, a two-phase lixiviant comprising entrained oxygen containing bubbles and an ammoniacal leach liquor having a pH less than 10.5 and less than 1.0 mole/liter ammonia is passed through the leaching interval to solubilize copper, nickel, uranium, and other metal values.

Hard, R.A.; Harvey, W.W.; Lingane, P.J.; Park, W.C.; Redman, M.J.

1981-09-29T23:59:59.000Z

96

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

E-Print Network [OSTI]

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

97

Chapter 5. Conclusion Uranium, a naturally occurring element, contributes to low levels of natural background radiation in the  

E-Print Network [OSTI]

are extracted from the earth. Protore is mined uranium ore that is not rich enough to meet the market demand conventional open-pit and underground uranium mining include overburden (although most overburden is not necessarily enriched in uranium as is protore), unreclaimed protore, waste rock, evaporites from mine water

98

EA-1037: Uranium Lease Management Program, Grand Junction, Colorado |  

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

37: Uranium Lease Management Program, Grand Junction, Colorado 37: Uranium Lease Management Program, Grand Junction, Colorado EA-1037: Uranium Lease Management Program, Grand Junction, Colorado SUMMARY This EA evaluates the environmental impacts of the U.S. Department of Energy's Grand Junction Projects Office's proposal to maintain and preserve the nation's immediately accessible supply of domestic uranium and vanadium ores, to maintain a viable domestic mining and milling infrastructure required to produce and mill these ores, and to provide assurance of a fair monetary return to the U.S. Government. The Uranium Lease Management Program gives The Department of Energy the flexibility to continue leasing these lands. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 22, 1995

99

Abstract B41: Depleted uranium-induced oxidative stress in human bronchial epithelial cells  

Science Journals Connector (OSTI)

...Science of Cancer Health Disparities- Feb...AZ Abstract B41: Depleted uranium-induced oxidative...Science of Cancer Health Disparities- Feb...high deposits of uranium or tailings. There...occupational exposures to depleted uranium via military...

Monica Yellowhair; Leigh A. Henricksen; Aneesha Hossain; Kathleen Dixon; and R. Clark Lantz

2009-02-01T23:59:59.000Z

100

Abstract B41: Depleted uranium-induced oxidative stress in human bronchial epithelial cells  

Science Journals Connector (OSTI)

...Association for Cancer Research 1 February...The Science of Cancer Health Disparities...Abstract B41: Depleted uranium-induced oxidative...Carefree, AZ Cancer and mortality...deposits of uranium or tailings...exposures to depleted uranium via...

Monica Yellowhair; Leigh A. Henricksen; Aneesha Hossain; Kathleen Dixon; and R. Clark Lantz

2009-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

Platinum Metals Magmatic Sulfide Ores  

Science Journals Connector (OSTI)

...Stumpfl (36) has suggested that hydro-thermal solutions have upgraded the ores. Hiemstra...Silver and Gold (Mineral Bulletin MR 185, Energy, Mines and Resources Canada, Ot-tawa...individuals. Sup-port has been received from Energy, Mines and Resources Canada grant 222-4-78...

A. J. Naldrett; J. M. Duke

1980-06-27T23:59:59.000Z

102

Measurements of uranium in soils and small mammals  

SciTech Connect (OSTI)

The objective of this study was to evaluate the bioavailability of uranium to a single species of small mammal, Peromyscus maniculatus rufinus (Merriam), white-footed deer mouse, from two different source terms: a Los Alamos National Laboratory dynamic weapons testing site in north central New Mexico, where an estimated 70,000 kg of uranium have been expended over a 31-y period; and an inactive uranium mill tailings pile located in west central New Mexico near Grants, which received wastes over a 5-y period from the milling of 2.7 x 10/sup 9/ kg of uranium ore.

Miera, F.R. Jr.

1980-12-01T23:59:59.000Z

103

Uranium Leasing Program: Program Summary | Department of Energy  

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

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

104

Management Controls over the Department of Energy's Uranium Leasing  

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

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

105

Natural radioactivity measurements and dose calculations to the public: Case of the uranium-bearing region of Poli in Cameroon  

Science Journals Connector (OSTI)

The objective of this work is to carry out a baseline study of the uranium-bearing region of Poli in which lies the uranium deposit of Kitongo, prior to its impending exploitation. This study required sampling soil, water and foodstuffs representative of the radioactivity exposure and food consumption patterns of the population of Poli. After sampling and radioactivity measurements were taken, our results indicated that the activities of natural series in soil and water samples are low. However, high levels of 210Po and 210Pb in foodstuffs (vegetables) were discovered and elevated activities of 40K were observed in some soil samples. All components of the total dose were assessed and lead to an average value of 5.2 mSv/year, slightly higher than the average worldwide value of 2.4 mSv/year. Most of this dose is attributable to the ingestion dose caused by the high levels of 210Po and 210Pb contained in vegetables, food items which constitute an important part of the diet in Northern Cameroon. Consequently, bringing uranium ore from underground to the surface might lead to an increased dose for the population of Poli through a higher deposition of 222Rn decay products on leafy vegetables.

Saïdou; François O. Bochud; Sébastien Baechler; Kwato Njock Moïse; Ngachin Merlin; Pascal Froidevaux

2011-01-01T23:59:59.000Z

106

Novel Binders and Methods for Agglomeration of Ore  

SciTech Connect (OSTI)

Heap leaching is one of the methods being used to recover metal from low grade ore deposits. The main problem faced during heap leaching is the migration of fine grained particles through the heap, forming impermeable beds which result in poor solution flow. The poor solution flow leads to less contact between the leach solution and the ore, resulting in low recovery rates. Agglomeration of ore into coarse, porous masses prevents fine particles from migrating and clogging the spaces and channels between the larger ore particles. Currently, there is one facility in the United States which uses agglomeration. This operation agglomerates their ore using leach solution (raffinate), but is still experiencing undesirable metal recovery from the heaps due to agglomerate breakdown. The use of a binder, in addition to the leach solution, during agglomeration would help to produce stronger agglomerates that did not break down during processing. However, there are no known binders that will work satisfactorily in the acidic environment of a heap, at a reasonable cost. As a result, operators of many facilities see a large loss of process efficiency due to their inability to take advantage of agglomeration. Increasing copper recovery in heap leaching by the use of binders and agglomeration would result in a significant decrease in the amount of energy consumed. Assuming that 70% of all the leaching heaps would convert to using agglomeration technology, as much as 1.64*10{sup 12} BTU per year would be able to be saved if a 25% increase in copper recovery was experienced, which is equivalent to saving approximately 18% of the energy currently being used in leaching heaps. For every week a leach cycle was decreased, a savings of as much as 1.23*10{sup 11} BTU per week would result. This project has identified several acid-resistant binders and agglomeration procedures. These binders and experimental procedures will be able to be used for use in improving the energy efficiency of heap leaching.

S. K. Kawatra; T. C. Eisele; K. A. Lewandowski; J. A. Gurtler

2006-09-30T23:59:59.000Z

107

National Uranium Resource Evaluation, Tonopah quadrangle, Nevada  

SciTech Connect (OSTI)

The Tonopah Quadrangle, Nevada, was evaluated using National Uranium Resource Evaluation criteria to identify and delineate areas favorable for uranium deposits. Investigations included reconnaissance and detailed surface geologic and radiometric studies, geochemical sampling and evaluation, analysis and ground-truth followup of aerial radiometric and hydrogeochemical and stream-sediment reconnaissance data, and subsurface data evaluation. The results of these investigations indicate environments favorable for hydroallogenic uranium deposits in Miocene lacustrine sediments of the Big Smoky Valley west of Tonopah. The northern portion of the Toquima granitic pluton is favorable for authigenic uranium deposits. Environments considered unfavorable for uranium deposits include Quaternary sediments; intermediate and mafic volcanic and metavolcanic rocks; Mesozoic, Paleozoic, and Precambrian sedimentary and metasedimentary rocks; those plutonic rocks not included within favorable areas; and those felsic volcanic rocks not within the Northumberland and Mount Jefferson calderas.

Hurley, B W; Parker, D P

1982-04-01T23:59:59.000Z

108

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

Office of Scientific and Technical Information (OSTI)

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

109

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

E-Print Network [OSTI]

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

110

Defense?Related Uranium Mines Report to Congress (August 2014)  

Broader source: Energy.gov [DOE]

Section 3151 of the National Defense Authorization Act for Fiscal Year 2013 directed the Secretary of Energy, in consultation with the Secretary of the Interior and the Administrator of the U.S. Environmental Protection Agency (EPA), to undertake a review of, and prepare a report on, abandoned uranium mines in the United States that provided uranium ore for atomic energy defense activities of the United States (the mines).

111

Distribution and a possible mechanism of uranium accumulation in the Catahoula Tuff, Live Oak County, Texas  

E-Print Network [OSTI]

- and micro-scopic distribution of' uranium within the Catahoula Tuff. METHODS A uranium ore body exposed in the Pant Tuff' Member of the Catahoula Tuff and exposed by open-pit mining was inves- tigated in this study. The distribution of the uranium... by oil and mining companies and the United States Geological Survey found numerous radiometric anomalies, In 1959, the San Antonio Mine Company began open pit mining of several small, shallow (less than 15 meters deep) . oxidized ore bodies in Karnes...

Parks, Steven Louis

1979-01-01T23:59:59.000Z

112

3rd Quarter 2013 Domestic Uranium Production Report  

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

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

113

Subsurface transformations of depleted uranium at Aberdeen Proving Ground, Maryland.  

E-Print Network [OSTI]

?? Approximately 130,000 kg of depleted uranium (DU) from ammunition testing have been deposited in soils since 1974 and remain in the environment at Aberdeen… (more)

Oxenberg, Tanya Palmateer

2007-01-01T23:59:59.000Z

114

The End of Cheap Uranium  

E-Print Network [OSTI]

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

Michael Dittmar

2011-06-21T23:59:59.000Z

115

1. Department, Course Number, Title ORE 678, Marine Mineral Resources Engineering  

E-Print Network [OSTI]

Nodules and Marine Mining · Deep Sea Mining Technology · Minerals Processing · Offshore Oil and Gas · Oil · Formation Processes of Polymetallic Sulfides (PMS) on the Ocean Floor: Geology of the Smoker and PMS · Chemistry of Hydrothermal Vents and Polymetallic Sulfides · PMS Deposits: From Smoker to an Ore Body · Case

Frandsen, Jannette B.

116

Uranium industry annual 1997  

SciTech Connect (OSTI)

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

117

URANIUM IN ALKALINE ROCKS  

E-Print Network [OSTI]

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

Murphy, M.

2011-01-01T23:59:59.000Z

118

3rd Quarter 2013 Domestic Uranium Production Report  

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

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

119

Long-term evaluation of fluoroelastomer O-rings in UF/sub 6/  

SciTech Connect (OSTI)

A major component in the gaseous centrifuge enrichment plant (GCEP) was fluoroelastomer O-rings, which were used to seal the uranium hexafluoride (UF/sub 6/) gas system. A program utilizing accelerated test conditions was used to help identify the best material out of four selected candidates and to predict the service life of these materials at GCEP conditions. The tests included accelerated temperatures, mechanical stress, and UF/sub 6/ exposure. Data were evaluated using the Newman--Keuls/sup 1/ ranking system to identify the best material and a zero-order reaction rate equation to help predict service life. This presentation includes a description of the test facility, the materials tested, the types of tests, objectives of the study, service life predictions, and conclusions. The O-rings are predicted to last approx. 30 years, and a high-molecular-weight polymer had the best performance ranking.

Russell, R.G.; Otey, M.G.; Dippo, G.L.

1986-05-01T23:59:59.000Z

120

Depleted uranium  

Science Journals Connector (OSTI)

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

Richard Wakeford

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

Radiological aspects of in situ uranium recovery  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

122

What is Depleted Uranium?  

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

123

Mathematical Geology, Vol. 33, No. 1, 2001 Modeling Uranium Transport in Koongarra,  

E-Print Network [OSTI]

Mathematical Geology, Vol. 33, No. 1, 2001 Modeling Uranium Transport in Koongarra, Australia waste disposal safety assessment studies. The Koongarra uranium deposit in the Alligator Rivers region weathering over several million years, during which many climatological, hydrological, and geological changes

Hassanizadeh, S. Majid

124

Osmium isotope systematics in Witwatersrand and Bushveld ore deposits  

Science Journals Connector (OSTI)

...isotopes Klipfontein Concentrator laurite Loraine Mine mass spectra Merensky Reef metal...mineral concentrateswere obtainedfrom the Loraine,PresidentBrand,andPresidentSteyn goldmines...outsidethe generalpopulation(1.371, Loraine; 0.996, PresidentBrand);18 additionalgrainsfrom...

S. R. Hart; E. D. Kinloch

125

Anomalously Metal-Rich Fluids Form Hydrothermal Ore Deposits  

Science Journals Connector (OSTI)

...Ireland were collected from historic mine exposures and drill core...empirical covariation in modern basin brines (4, 6, 24–26) and...S. mid-continent in the Permian via sulfide oxidation (27...heterogeneity in modern sedimentary basins (6) imply inefficiency of...

Jamie J. Wilkinson; Barry Stoffell; Clara C. Wilkinson; Teresa E. Jeffries; Martin S. Appold

2009-02-06T23:59:59.000Z

126

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

127

Legacy Management Work Progresses on Defense-Related Uranium Mines Report  

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

Legacy Management Work Progresses on Defense-Related Uranium Mines 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 23, 2013 - 1:35pm Addthis What does this project do? Goal 4. Optimize the use of land and assets The U.S. Department of Energy Office of Legacy Management (LM) continues to work on a report to Congress regarding defense-related legacy uranium mines. LM was directed by the U.S. Congress in the National Defense Authorization Act for Fiscal Year 2013 to undertake a review of, and prepare a report on, abandoned uranium mines in the United States that provided uranium ore for atomic energy defense activities. The report is due to Congress by July 2014. LM is compiling uranium mine data from federal, state, and tribal agencies

128

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

SciTech Connect (OSTI)

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

129

Development of Novel Sorbents for Uranium Extraction from Seawater  

SciTech Connect (OSTI)

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

Lin, Wenbin; Taylor-Pashow, Kathryn

2014-01-08T23:59:59.000Z

130

Plutonium recovery from spent reactor fuel by uranium displacement  

DOE Patents [OSTI]

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

Ackerman, J.P.

1992-03-17T23:59:59.000Z

131

Depleted Uranium Health Effects  

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

132

Uranium industry annual 1996  

SciTech Connect (OSTI)

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

133

Lung cancer in uranium miners and the implications of the U/V ratio in uranium-bearing particles  

SciTech Connect (OSTI)

Several geological formations mined for uranium ore during and after the second World War had been mined earlier for vanadium. Most miners and millers from the Utah-Colorado mining region worked with this ore or its tailings at one time or another. Preliminary investigation to determine the size and location of uranium-bearing particles retained in the lungs of a former uranium miner and miller from this region, who died of lung cancer (mesothelioma), showed a high nonuniform distribution of vanadium. This observation leads to the hypothesis that the vanadium content in that lung could be associated with inhaled particles. Further examination of spectra of characteristic x-rays obtained by scanning microPIXE (particle induced x-ray emission) of an autopsy sample of this lung indicated that vanadium was indeed present in localized sites within the 20 ..mu..m spatial resolution of the proton beam. This work points out that the vanadium found in the lungs of this former miner and miller is nonuniformly distributed, and can be used for site localization and size determination of inhaled particles retained in the lungs. The meaning of U/V ratios in dust particles and in lungs is discussed. Further studies are in progress to: (1) locate uranium-bearing particles in lung tissues of former uranium miners and millers; and (2) evaluate the local alpha doses received from these particles. 11 refs., 3 figs., 1 tab.

Paschoa, A.S.; Wrenn, M.E.; Singh, N.P.; Bruenger, F.W.; Miller, S.C.; Cholewa, M.; Jones, K.W.

1985-01-01T23:59:59.000Z

134

LM Progressing with Uranium Mines Report to Congress | Department of Energy  

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

Progressing with Uranium Mines Report to Congress Progressing with Uranium Mines Report to Congress LM Progressing with Uranium Mines Report to Congress July 12, 2013 - 10:50am Addthis As reported in an earlier Program Update newsletter, the U.S. Department of Energy (DOE) Office of Legacy Management (LM) is compiling data for a Report to Congress on defense-related uranium mines. DOE was directed by the U.S. Congress in this year's National Defense Authorization Act to undertake a review of, and prepare a report on, abandoned uranium mines (AUM) in the U.S. that provided ore for atomic energy defense activities. The report must be completed by July 2014. The article, "Abandoned Uranium Mines Report to Congress: LM Wants Your Input" from the January-March 2013 issue of the LM Program Update provides additional

135

Microbiological and Geochemical Characterization of Fluvially Deposited Sulfidic Mine Tailings  

Science Journals Connector (OSTI)

...NO3 , and Mn(IV) are depleted. However, it has been...REFERENCES American Public Health Association Phenanthroline...microorganisms inhabiting uranium mill tailings. . Moore...Microbial diversity in uranium mine waste heaps...bacteria in the Nordic Uranium tailings deposit, Elliot...

Bruce Wielinga; Juliette K. Lucy; Johnnie N. Moore; October F. Seastone; James E. Gannon

1999-04-01T23:59:59.000Z

136

Ore-magmatic systems of the Noril’sk ore field  

Science Journals Connector (OSTI)

Plutonogenic ore-magmatic systems of the Noril’sk ore field are unique constituents of the P2–T1 trap formation in the East Siberian Platform. We consider the formation of ore-bearing intrusions, evolution of Cr-spinels in intrusive magmatites, possible mechanisms of formation of massive, disseminated, and impregnated magmatic sulfide ores, possible reasons for the abundance of sulfide melts, quasi-anhydrite isotopic composition of sulfur of sulfide ores, and products of interaction of sulfide melts with ore-hosting basites. The unique contents of PGE, Ag, and Au in ores (eutectic Iss–PbSss intergrowths, crystallization products of low-temperature Ni-Fe-Cu-Pb-S melts) have been estimated for the first time. We have established that pneumatolytic Ag-Au-Pt-Pd mineralization is intimately related to the fluid aureoles near magmatic sulfide bodies. Pneumatolytic PGM are subdivided into early (tetraferroplatinum with lamellae atokite, paolovite with lamellae of insizwaite-geversite and niggliite, etc.), middle (rustenburgite-atokite-zvyagintsevite, mayakite, stannopalladinite, polarite, plumbopalladinite, maslovite, tatiyanite-taimyrite, Pd-Pt-containing tetraauricupride, etc.), late (sobolevskite, froodite, hessite, michenerite, cabriite, minerals of Au-Ag series, etc.), and the latest (sperrylite). The direct, reverse, oscillation, and complex zoning of gold particles is much due to variations in the Te activity in the fluids. Pneumatolytic noble-metal minerals were produced at <490 ºC in strongly reducing conditions with extremely low S2 fugacity. The Pb isotope composition evidences that all systems of the trap formation in the Noril’sk region had the same mantle source. The Pb isotope compositions of ore-bearing intrusions, magmatic sulfide ores, PbSss, and Pd-Pt intermetallides in the Noril’sk and Talnakh ore clusters differ significantly: Lead in the Talnakh cluster is more radiogenic. This evidences genetic relations between sulfide ores and particular intrusions as well as different intermediate magma chambers in the Noril’sk and Talnakh clusters, and a higher degree of contamination of mantle magmas in the Talnakh cluster, which might be the explanation of its giant area.

E.M. Spiridonov

2010-01-01T23:59:59.000Z

137

Neurotoxicity of depleted uranium  

Science Journals Connector (OSTI)

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

George C. -T. Jiang; Michael Aschiner

2006-04-01T23:59:59.000Z

138

Excess Uranium Management  

Broader source: Energy.gov [DOE]

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

139

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

140

Uranium Industry Annual, 1992  

SciTech Connect (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

Note: This page contains sample records for the topic "uranium ore deposits" 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

TOTAL ORE PROCESSING INTEGRATION AND MANAGEMENT  

SciTech Connect (OSTI)

The lessons learned from ore segregation test No.3 were presented to Minntac Mine personnel during the reporting period. Ore was segregated by A-Factor, with low values going to Step 1/2 and high values going to Step 3. During the test, the mine maintained the best split possible for the given production and location constraints. During the test, Step 1&2 A-Factor was lowered more than Step 3 was raised. All other ore quality changes were not manipulated, but the segregation by A-Factor affected most of the other qualities. Magnetic iron, coarse tails, fine tails, silica, and grind changed in response to the split. Segregation was achieved by adding ore from HIS to the Step 3 blend and lowering the amount of LC 1&2 and somewhat lowering the amount of LC 3&4. Conversely, Step 1&2 received less HIS with a corresponding increase in LC 1&2. The amount of IBC was increased to both Steps about one-third of the way into the test. For about the center half of the test, LC 3&4 was reduced to both Steps. The most noticeable layer changes were, then: an increase in the HIS split; a decrease in the LC 1&2 split; adding IBC to both Steps; and lowering LC 3&4 to both Steps. Statistical analysis of the dataset collected during ordinary, non-segregated operation of the mine and mill is continuing. Graphical analysis of blast patterns according to drill monitor data was slowed by student classwork. It is expected to resume after the semester ends in May.

Leslie Gertsch; Richard Gertsch

2005-05-16T23:59:59.000Z

142

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

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

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

143

Isotopic investigation of the colloidal mobility of depleted uranium in a podzolic soil  

Science Journals Connector (OSTI)

Abstract The mobility and colloidal migration of uranium were investigated in a soil where limited amounts of anthropogenic uranium (depleted in the 235U isotope) were deposited, adding to the naturally occurring uranium. The colloidal fraction was assumed to correspond to the operational fraction between 10 kDa and 1.2 ?m after (ultra)filtration. Experimental leaching tests indicate that approximately 8–15% of uranium is desorbed from the soil. Significant enrichment of the leachate in the depleted uranium (DU) content indicates that uranium from recent anthropogenic DU deposit is weakly bound to soil aggregates and more mobile than geologically occurring natural uranium (NU). Moreover, 80% of uranium in leachates was located in the colloidal fractions. Nevertheless, the percentage of DU in the colloidal and dissolved fractions suggests that NU is mainly associated with the non-mobile coarser fractions of the soil. A field investigation revealed that the calculated percentages of DU in soil and groundwater samples result in the enhanced mobility of uranium downstream from the deposit area. Colloidal uranium represents between 10% and 32% of uranium in surface water and between 68% and 90% of uranium in groundwater where physicochemical parameters are similar to those of the leachates. Finally, as observed in batch leaching tests, the colloidal fractions of groundwater contain slightly less DU than the dissolved fraction, indicating that DU is primarily associated with macromolecules in dissolved fraction.

S. Harguindeguy; P. Crançon; F. Pointurier; M. Potin-Gautier; G. Lespes

2014-01-01T23:59:59.000Z

144

8 - Uranium  

Science Journals Connector (OSTI)

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

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

2011-01-01T23:59:59.000Z

145

Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels  

DOE Patents [OSTI]

An electrorefining process and apparatus for the recovery of uranium and a mixture of uranium and plutonium from spent fuels is disclosed using an electrolytic cell having a lower molten cadmium pool containing spent nuclear fuel, an intermediate electrolyte pool, an anode basket containing spent fuels, two cathodes and electrical power means connected to the anode basket, cathodes and lower molten cadmium pool for providing electrical power to the cell. Using this cell, additional amounts of uranium and plutonium from the anode basket are dissolved in the lower molten cadmium pool, and then purified uranium is electrolytically transported and deposited on a first molten cadmium cathode. Subsequently, a mixture of uranium and plutonium is electrotransported and deposited on a second cathode. 3 figs.

Ackerman, J.P.; Miller, W.E.

1987-11-05T23:59:59.000Z

146

Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels  

DOE Patents [OSTI]

An electrorefining process and apparatus for the recovery of uranium and a mixture of uranium and plutonium from spent fuel using an electrolytic cell having a lower molten cadmium pool containing spent nuclear fuel, an intermediate electrolyte pool, an anode basket containing spent fuel, and two cathodes, the first cathode composed of either a solid alloy or molten cadmium and the second cathode composed of molten cadmium. Using this cell, additional amounts of uranium and plutonium from the anode basket are dissolved in the lower molten cadmium pool, and then substantially pure uranium is electrolytically transported and deposited on the first alloy or molten cadmium cathode. Subsequently, a mixture of uranium and plutonium is electrotransported and deposited on the second molten cadmium cathode.

Ackerman, John P. (Downers Grove, IL); Miller, William E. (Naperville, IL)

1989-01-01T23:59:59.000Z

147

Uranium Hexafluoride (UF6)  

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

148

Uranium industry annual 1998  

SciTech Connect (OSTI)

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

149

Uranium industry annual 1994  

SciTech Connect (OSTI)

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

150

Chemical enhancement of surface deposition  

DOE Patents [OSTI]

A method and apparatus for increasing the deposition of ions onto a surface, such as the adsorption of uranium ions on the detecting surface of a radionuclide detector. The method includes the step of exposing the surface to a complexing agent, such as a phosphate ion solution, which has an affinity for the dissolved species to be deposited on the surface. This provides, for example, enhanced sensitivity of the radionuclide detector.

Patch, Keith D. (Lexington, MA); Morgan, Dean T. (Sudbury, MA)

1997-07-29T23:59:59.000Z

151

Chemical enhancement of surface deposition  

DOE Patents [OSTI]

A method and apparatus are disclosed for increasing the deposition of ions onto a surface, such as the adsorption of uranium ions on the detecting surface of a radionuclide detector. The method includes the step of exposing the surface to a complexing agent, such as a phosphate ion solution, which has an affinity for the dissolved species to be deposited on the surface. This provides, for example, enhanced sensitivity of the radionuclide detector. 16 figs.

Patch, K.D.; Morgan, D.T.

1997-07-29T23:59:59.000Z

152

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

Science Journals Connector (OSTI)

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

Michel Lung; Abdelaali Kossir; Driss Msatef

2005-01-01T23:59:59.000Z

153

Uranium industry annual 1995  

SciTech Connect (OSTI)

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

154

Disposition of DOE Excess Depleted Uranium, Natural Uranium, and  

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

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

155

Depleted Uranium Technical Brief  

E-Print Network [OSTI]

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

156

Rujevac Sb-Pb-Zn-As polymetallic deposit, Boranja orefield, Western Serbia: native arsenic and arsenic mineralization  

Science Journals Connector (OSTI)

Rujevac is a low-temperature hydrothermal polymetallic Sb-Pb-Zn-As vein-type ore deposit, hosted within a volcanogenic-sedimentary zone situated in the Rujevac-Crvene Stene-Brezovica Diabase-Chert Formation (D...

Slobodan A. Radosavljevi?; Jovica N. Stojanovi?…

2014-02-01T23:59:59.000Z

157

Fabrication and Characterization of Uranium-based High Temperature Reactor  

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

Fabrication and Characterization of Uranium-based High Temperature Reactor Fabrication and Characterization of Uranium-based High Temperature Reactor Fuel June 01, 2013 The Uranium Fuel Development Laboratory is a modern R&D scale lab for the fabrication and characterization of uranium-based high temperature reactor fuel. A laboratory-scale coater manufactures tri-isotropic (TRISO) coated fuel particles (CFPs), state-of-the-art materials property characterization is performed, and the CFPs are then pressed into fuel compacts for irradiation testing, all under a NQA-1 compliant Quality Assurance Program. After fuel kernel size and shape are measured by optical shadow imaging, the TRISO coatings are deposited via fluidized bed chemical vapor deposition in a 50-mm diameter conical chamber within the coating furnace. Computer control of temperature and gas composition ensures reproducibility

158

Population doses from terrestrial exposure in the vicinity of abandoned uranium mines in Serbia  

Science Journals Connector (OSTI)

A uranium mineralized area of Stara Planina Mt., Serbia, where uranium ore was exploited for seven years was characterized radiologically. Results were compared with those for an area of background radiation in the northern part of the mountain. The terrestrial gamma dose rate due to 238U, 232Th and 40K in the area affected by mining activities was twofold higher than that of background area. The radiological situation of the affected area is not of immediate concern, except one location with elevated external hazard index where remediative measures taking into account site-specific ecological characteristics should be planned and implemented.

M. Mom?ilovi?; J. Kova?evi?; S. Dragovi?

2010-01-01T23:59:59.000Z

159

Welding of uranium and uranium alloys  

SciTech Connect (OSTI)

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

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

1982-03-26T23:59:59.000Z

160

Spatial analysis techniques applied to uranium prospecting in Chihuahua State, Mexico  

Science Journals Connector (OSTI)

To estimate the distribution of uranium minerals in Chihuahua the advanced statistical model "Maximun Entropy Method" (MaxEnt) was applied. A distinguishing feature of this method is that it can fit more complex models in case of small datasets (x and y data) as is the location of uranium ores in the State of Chihuahua. For georeferencing uranium ores a database from the United States Geological Survey and workgroup of experts in Mexico was used. The main contribution of this paper is the proposal of maximum entropy techniques to obtain the mineral's potential distribution. For this model were used 24 environmental layers like topography gravimetry climate (worldclim) soil properties and others that were useful to project the uranium's distribution across the study area. For the validation of the places predicted by the model comparisons were done with other research of the Mexican Service of Geological Survey with direct exploration of specific areas and by talks with former exploration workers of the enterprise "Uranio de Mexico". Results. New uranium areas predicted by the model were validated finding some relationship between the model predictions and geological faults. Conclusions. Modeling by spatial analysis provides additional information to the energy and mineral resources sectors.

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

FAQ 1-What is uranium?  

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

162

Uranium hexafluoride public risk  

SciTech Connect (OSTI)

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

163

Total production of uranium concentrate in the United States  

Gasoline and Diesel Fuel Update (EIA)

3. U.S. uranium mills and heap leach facilities by owner, location, capacity, and operating status 3. U.S. uranium mills and heap leach facilities by owner, location, capacity, and operating status Operating Status at the End of Owner Mill and Heap Leach1 Facility Name County, State (existing and planned locations) Capacity (short tons of ore per day) 2012 1st Quarter 2013 2nd Quarter 2013 3rd Quarter 2013 EFR White Mesa LLC White Mesa Mill San Juan, Utah 2,000 Operating Operating Operating Operating-Processing Alternate Feed Energy Fuels Resources Corporation Piñon Ridge Mill Montrose, Colorado 500 Partially Permitted And Licensed Partially Permitted And Licensed Partially Permitted And Licensed Permitted and Licensed Energy Fuels Wyoming Inc Sheep Mountain Fremont, Wyoming 725 - Undeveloped Undeveloped Undeveloped

164

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.

165

Uranium purchases report 1992  

SciTech Connect (OSTI)

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

Not Available

1993-08-19T23:59:59.000Z

166

Natural Ores as Oxygen Carriers in Chemical Looping Combustion  

Science Journals Connector (OSTI)

Natural Ores as Oxygen Carriers in Chemical Looping Combustion ... Chemical looping combustion (CLC) is a combustion technology that utilizes oxygen from oxygen carriers (OC), such as metal oxides, instead of air to combust fuels. ...

Hanjing Tian; Ranjani Siriwardane; Thomas Simonyi; James Poston

2013-01-02T23:59:59.000Z

167

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

168

Uranium from Seawater Program Review; Fuel Resources Uranium from Seawater Program DOE Office of Nuclear Energy  

SciTech Connect (OSTI)

For nuclear energy to remain sustainable in the United States, economically viable sources of uranium beyond terrestrial ores must be developed. The goal of this program is to develop advanced adsorbents that can extract uranium from seawater at twice the capacity of the best adsorbent developed by researchers at the Japan Atomic Energy Agency (JAEA), 1.5 mg U/g adsorbent. A multidisciplinary team from Oak Ridge National Laboratory, Lawrence Berkeley National Laboratory, Pacific Northwest National Laboratory, and the University of Texas at Austin was assembled to address this challenging problem. Polymeric adsorbents, based on the radiation grafting of acrylonitrile and methacrylic acid onto high surface-area polyethylene fibers followed by conversion of the nitriles to amidoximes, have been developed. These poly(acrylamidoxime-co-methacrylic acid) fibers showed uranium adsorption capacities for the extraction of uranium from seawater that exceed 3 mg U/g adsorbent in testing at the Pacific Northwest National Laboratory Marine Sciences Laboratory. The essence of this novel technology lies in the unique high surface-area trunk material that considerably increases the grafting yield of functional groups without compromising its mechanical properties. This technology received an R&D100 Award in 2012. In addition, high surface area nanomaterial adsorbents are under development with the goal of increasing uranium adsorption capacity by taking advantage of the high surface areas and tunable porosity of carbon-based nanomaterials. Simultaneously, de novo structure-based computational design methods are being used to design more selective and stable ligands and the most promising candidates are being synthesized, tested and evaluated for incorporation onto a support matrix. Fundamental thermodynamic and kinetic studies are being carried out to improve the adsorption efficiency, the selectivity of uranium over other metals, and the stability of the adsorbents. Understanding the rate-limiting step of uranium uptake from seawater is also essential in designing an effective uranium recovery system. Finally, economic analyses have been used to guide these studies and highlight what parameters, such as capacity, recyclability, and stability, have the largest impact on the cost of extraction of uranium from seawater. Initially, the cost estimates by the JAEA for extraction of uranium from seawater with braided polymeric fibers functionalized with amidoxime ligands were evaluated and updated. The economic analyses were subsequently updated to reflect the results of this project while providing insight for cost reductions in the adsorbent development through “cradle-to-grave” case studies for the extraction process. This report highlights the progress made over the last three years on the design, synthesis, and testing of new materials to extract uranium for seawater. This report is organized into sections that highlight the major research activities in this project: (1) Chelate Design and Modeling, (2) Thermodynamics, Kinetics and Structure, (3) Advanced Polymeric Adsorbents by Radiation Induced Grafting, (4) Advanced Nanomaterial Adsorbents, (5) Adsorbent Screening and Modeling, (6) Marine Testing, and (7) Cost and Energy Assessment. At the end of each section, future research directions are briefly discussed to highlight the challenges that still remain to reduce the cost of extractions of uranium for seawater. Finally, contributions from the Nuclear Energy University Programs (NEUP), which complement this research program, are included at the end of this report.

none,

2013-07-01T23:59:59.000Z

169

Uranium isotopes in ground water as a prospecting technique  

SciTech Connect (OSTI)

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

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

1980-02-01T23:59:59.000Z

170

IN-SITU MINING OF PHOSPHATE ORES  

SciTech Connect (OSTI)

Presently the mining of Florida phosphate requires the movement of over a 100-ton of materials (overburden, sand, clay) for every ton of phosphate concentrate recovered. Not only is this energy intensive, but it also causes significant stress on the environment. In 2003, the Department of Energy solicited ideas for innovative mining ideas that could significantly improve the efficiency of mining. An award was made to the University of Florida Engineering Research Center to evaluate the in situ mining of phosphates using an aqueous CO{sub 2} solution. Tests were carried out in a 15.2 cm (6-inch) diameter column, 1.83 meter (6 feet) long at pressures up to 117.2 kg/cm{sup 2} (40 psi). Results to date demonstrate that initially the MgO is leached from the ore and then the phosphate. While the tests are continuing, so far they have not demonstrated P{sub 2}O{sub 5} concentrations that are economically attractive.

H. El-Shall; R. Stana; A. El-Midany; S. Malekzadah

2004-12-17T23:59:59.000Z

171

2013 Uranium Marketing Annual Survey  

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

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

172

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

E-Print Network [OSTI]

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

Winfree, Erik

173

Assessment of age-dependent uranium intake due to drinking water in Hyderabad, India  

Science Journals Connector (OSTI)

......leaching from natural deposits, combustion of coal and other fuels and the use of...species of radio elements from coal-fired plants. Health Phys. (1986...Ultraviolet Rays Uranium analysis Water chemistry Water Pollutants, Radioactive......

A. Y. Balbudhe; S. K. Srivastava; K. Vishwaprasad; G. K. Srivastava; R. M. Tripathi; V. D. Puranik

2012-03-01T23:59:59.000Z

174

Alternative Energy Development and China's Energy Future  

E-Print Network [OSTI]

Beerten et al. 2009. Uranium Conversion After the uraniummilling of the uranium ore; conversion of the uranium oreMining and Milling Uranium ore Conversion Enrichment Fuel

Zheng, Nina

2012-01-01T23:59:59.000Z

175

Domestic Uranium Production Report  

Gasoline and Diesel Fuel Update (EIA)

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

176

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,

177

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),

178

Uranium and Thorium Ores Price List | U.S. DOE Office of Science...  

Office of Science (SC) Website

Determinations News Contact Information New Brunswick Laboratory U.S. Department of Energy Building 350 9800 South Cass Avenue Argonne, IL 60439-4899 P: (630) 252-2442 (NBL)...

179

Pressurized chemical-looping combustion of coal with an iron ore-based oxygen carrier  

SciTech Connect (OSTI)

Chemical-looping combustion (CLC) is a new combustion technology with inherent separation of CO{sub 2}. Most of the previous investigations on CLC of solid fuels were conducted under atmospheric pressure. A pressurized CLC combined cycle (PCLC-CC) system is proposed as a promising coal combustion technology with potential higher system efficiency, higher fuel conversion, and lower cost for CO{sub 2} sequestration. In this study pressurized CLC of coal with Companhia Valedo Rio Doce (CVRD) iron ore was investigated in a laboratory fixed bed reactor. CVRD iron ore particles were exposed alternately to reduction by 0.4 g of Chinese Xuzhou bituminous coal gasified with 87.2% steam/N{sub 2} mixture and oxidation with 5% O{sub 2} in N{sub 2} at 970 C. The operating pressure was varied between 0.1 MPa and 0.6 MPa. First, control experiments of steam coal gasification over quartz sand were performed. H{sub 2} and CO{sub 2} are the major components of the gasification products, and the operating pressure influences the gas composition. Higher concentrations of CO{sub 2} and lower fractions of CO, CH{sub 4}, and H{sub 2} during the reduction process with CVRD iron ore was achieved under higher pressures. The effects of pressure on the coal gasification rate in the presence of the oxygen carrier were different for pyrolysis and char gasification. The pressurized condition suppresses the initial coal pyrolysis process while it also enhances coal char gasification and reduction with iron ore in steam, and thus improves the overall reaction rate of CLC. The oxidation rates and variation of oxygen carrier conversion are higher at elevated pressures reflecting higher reduction level in the previous reduction period. Scanning electron microscope and energy-dispersive X-ray spectroscopy (SEM-EDX) analyses show that particles become porous after experiments but maintain structure and size after several cycles. Agglomeration was not observed in this study. An EDX analysis demonstrates that there is very little coal ash deposited on the oxygen carrier particles but no appreciable crystalline phases change as verified by X-ray diffraction (XRD) analysis. Overall, the limited pressurized CLC experiments carried out in the present work suggest that PCLC of coal is promising and further investigations are necessary. (author)

Xiao, Rui; Song, Min; Zhang, Shuai; Shen, Laihong [School of Energy and Environment, Southeast University, Sipailou No. 2, Nanjing 210096 (China); Song, Qilei [School of Energy and Environment, Southeast University, Sipailou No. 2, Nanjing 210096 (China); Department of Chemical Engineering and Biotechnology, University of Cambridge, Pembroke Street, Cambridge CB2 3RA (United Kingdom); Lu, Zuoji [School of Energy and Environment, Southeast University, Sipailou No. 2, Nanjing 210096 (China); GCL Engineering Limited, Zhujiang No. 1, Nanjing 210008 (China)

2010-06-15T23:59:59.000Z

180

SRP Scientific Meeting: Depleted Uranium  

Science Journals Connector (OSTI)

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

David Kestell

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

Depleted uranium management alternatives  

SciTech Connect (OSTI)

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

182

Designation Survey - Palmerton, Pa. Ore Storage Site William Bibb  

Office of Legacy Management (LM)

Designation Survey - Palmerton, Pa. Ore Storage Site Designation Survey - Palmerton, Pa. Ore Storage Site William Bibb Oak Ridge Operations Office Based on the information furnished in Aerospace's Review of the.subject site (Attachment 1) and the ORKL/RASA (Attachment 2), it Is requested that designation survey of the Palmerton Ore Storage Pennsylvania. The survey should be detailed to and subsurface data to make up for the lack of the previous AEC surveys and in keeping with ORNL/RASA group should furnish a draft survey approval prior to conducting any survey activities. If there are any questions, please call Edward DeLaney 04 FTS 253-4716. Arthur J. Whitman / '/ Division of Facility and Site ' Deconrnissioning P,rojects Office of Nuclear Energy : 2 Attachments I bee: I E. Keller, OR, w/attachs:

183

Uranium minerals from the San Marcos District, Chihuahua, Mexico  

Science Journals Connector (OSTI)

The mineralogy of the two uranium deposits (Victorino and San Marcos I) of Sierra San Marcos, located 30 km northwest of Chihuahua City, Mexico, was studied by optical...2)2Si2O7·6(H2O) (the dominant mineral at b...

Manuel Reyes-Cortés; Luis Fuentes-Cobas; Enrique Torres-Moye…

2010-05-01T23:59:59.000Z

184

Radon-222 Daughter Concentrations in Uranium Mine Atmospheres  

Science Journals Connector (OSTI)

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

RICHARD L. BLANCHARD

1969-07-19T23:59:59.000Z

185

Fault tree analysis of spontaneous combustion of sulphide ores and its risk assessment  

Science Journals Connector (OSTI)

A logic fault tree of mine spontaneous combustion of sulphide ores was built by the fault tree analysis (FTA) based on a lot of mechanism investigation of sulphide ore spontaneous combustion in more than ten m...

Chao Wu

1995-11-01T23:59:59.000Z

186

Domestic Uranium Production Report  

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

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

187

Uranium Marketing Annual Report -  

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

1. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2009-13 thousands pounds U3O8...

188

Uranium Marketing Annual Report  

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

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

189

Uranium Marketing Annual Report -  

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

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

190

Uranium purchases report 1993  

SciTech Connect (OSTI)

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

Not Available

1994-08-10T23:59:59.000Z

191

Uranium Oxide Aerosol Transport in Porous Graphite  

SciTech Connect (OSTI)

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

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

2012-01-23T23:59:59.000Z

192

Uranium purchases report 1994  

SciTech Connect (OSTI)

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

NONE

1995-07-01T23:59:59.000Z

193

Final environmental statement related to the Western Nuclear, Inc. , Split Rock Uranium Mill (Fremont County, Wyoming)  

SciTech Connect (OSTI)

The proposed action is the renewal of Source Material License SUA-56 (with amendments) issued to Western Nuclear, Inc. (WNI), for the operation of the Split Rock Uranium Mill near Jeffrey City and the Green Mountain Ion-Exchange Facility, both in Fremont County, Wyoming. The license also permits possession of material from past operations at four ancillary facilities in the Gas Hills mining area - the Bullrush, Day-Loma, Frazier-Lamac, and Rox sites (Docket No. 40-1162). However, although heap leaching operations were previously authorized at Frazier-Lamac, there has never been any processing of material at this site. The Split Rock mill is an acid-leach, ion-exchange and solvent-extraction uranium-ore processing mill with a design capacity of 1540 MT (1700 tons) of ore per day. WNI has proposed by license amendment request to increase the storage capacity of the tailings ponds in order to permit the continuation of present production rates of U/sub 3/O/sub 8/ through 1996 using lower-grade ores.

Not Available

1980-02-01T23:59:59.000Z

194

Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte  

DOE Patents [OSTI]

An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.

Willit, James L. (Ratavia, IL)

2007-09-11T23:59:59.000Z

195

Porous membrane electrochemical cell for uranium and transuranic recovery from molten salt electrolyte  

DOE Patents [OSTI]

An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.

Willit, James L. (Batavia, IL)

2010-09-21T23:59:59.000Z

196

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.

197

FAQ 5-Is uranium radioactive?  

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

198

POMERIGGIO -GREEN WORKSHOP Ore 17:00 La riqualificazione edilizia in chiave green.  

E-Print Network [OSTI]

POMERIGGIO - GREEN WORKSHOP Ore 17:00 La riqualificazione edilizia in chiave green. Rifiuti urbani - SPETTACOLO Ore 22:00 Proiezione del docufilm "Green Generation", prodotto da Maiora Film in collaborazione con Rai Cinema. POMERIGGIO - GREEN WORKSHOP Ore 17:00 Mobilit� sostenibile e Smart City. Soluzioni tra

Di Pillo, Gianni

199

Methods of minimizing ground-water contamination from in situ leach uranium mining. Final report  

SciTech Connect (OSTI)

This is the final report of a research project designed to study methods of minimizing ground-water contamination from in situ leach uranium mining. Fieldwork and laboratory experiments were conducted to identify excursion indicators for monitoring purposes during mining, and to evaluate effective aquifer restoration techniques following mining. Many of the solution constituents were found to be too reactive with the aquifer sediments to reliably indicate excursion of leaching solution from the ore zone; however, in many cases, the concentrations of chloride and sulfate and the total dissolved solids level of the solution were found to be good excursion indicators. Aquifer restoration by ground-water sweeping consumed large quantities of ground water and was not effective for the redox-sensitive contaminants often present in the ore zone. Surface treatment methods such as reverse osmosis and electrodialysis were effective in reducing the amount of water used, but also had the potential for creating conditions in the aquifer under which the redox-sensitive contaminants would be mobile. In situ restoration by chemical reduction, in which a reducing agent is added to the solution recirculated through the ore zone during restoration, can restore the ore-zone sediment as well as the ground water. This method could lead to a stable chemical condition in the aquifer similar to conditions before mining. 41 figures.

Deutsch, W.J.; Martin, W.J.; Eary, L.E.; Serne, R.J.

1985-03-01T23:59:59.000Z

200

Natural Ores as Oxygen Carriers in Chemical Looping Combustion  

SciTech Connect (OSTI)

Chemical looping combustion (CLC) is a combustion technology that utilizes oxygen from oxygen carriers (OC), such as metal oxides, instead of air to combust fuels. The use of natural minerals as oxygen carriers has advantages, such as lower cost and availability. Eight materials, based on copper or iron oxides, were selected for screening tests of CLC processes using coal and methane as fuels. Thermogravimetric experiments and bench-scale fixed-bed reactor tests were conducted to investigate the oxygen transfer capacity, reaction kinetics, and stability during cyclic reduction/oxidation reaction. Most natural minerals showed lower combustion capacity than pure CuO/Fe{sub 2}O{sub 3} due to low-concentrations of active oxide species in minerals. In coal CLC, chryscolla (Cu-based), magnetite, and limonite (Fe-based) demonstrated better reaction performances than other materials. The addition of steam improved the coal CLC performance when using natural ores because of the steam gasification of coal and the subsequent reaction of gaseous fuels with active oxide species in the natural ores. In methane CLC, chryscolla, hematite, and limonite demonstrated excellent reactivity and stability in 50-cycle thermogravimetric analysis tests. Fe{sub 2}O{sub 3}-based ores possess greater oxygen utilization but require an activation period before achieving full performance in methane CLC. Particle agglomeration issues associated with the application of natural ores in CLC processes were also studied by scanning electron microscopy (SEM).

Tian, Hanjing; Siriwardane, Ranjani; Simonyi, Thomas; Poston, James

2013-08-01T23:59:59.000Z

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


201

Controlling uranium reactivity March 18, 2008  

E-Print Network [OSTI]

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

Meyer, Karsten

202

Influence of uranium hydride oxidation on uranium metal behaviour  

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

203

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

204

Assessment of the radiological impact of the inactive uranium-mill tailings at Mexican Hat, Utah  

SciTech Connect (OSTI)

High surface soil concentrations of /sup 226/Ra and high above-ground measurements of gamma-ray intensity in the vicinity of the inactive uranium-mill tailings at Mexican Hat show both wind and water erosion of the tailings. The former mill area, occupied by a trade school at the time of this survey, shows a comparatively high level of contamination, probably from unprocessed ore on the surface of the ore storage area near the location of the former mill buildings. However, the estimated health effect of exposure to gamma rays during a 2000-hr work year in the area represents an increase of 0.1% in the risk of death from cancer. Exposure of less than 600 persons within 1.6 km of the tailings to radon daughters results in an estimated 0.2%/year increase in risk of lung cancer.

Haywood, F.F.; Goldsmith, W.A.; Ellis, B.S.; Hubbard, H.M. Jr.; Fox, W.F.; Shinpaugh, W.H.

1980-03-01T23:59:59.000Z

205

Uranium hexafluoride handling. Proceedings  

SciTech Connect (OSTI)

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

206

2013 Uranium Marketing Annual Report  

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

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

207

Mixed sulphide–oxide lead and zinc ores: Problems and solutions  

Science Journals Connector (OSTI)

Mixed sulphide–oxide lead and zinc ores are most often found in the transition, and occasionally in the oxidised, zones of lead–zinc ore-bodies. They are of great importance because there are numerous unexploited or abandoned reserves of these ores in the world. However they present difficulties for conventional mineral processing due to complex mineralogy. In this paper, the specific problems associated with these types of ores are described and methods for solving these problems, combining economic and technical considerations, are discussed. The results of experiments carried out at laboratory scale are presented, in which the dissolution of mixed ore in sulphuric acid without oxidising agents was investigated. The results show the feasibility of zinc recovery from mixed sulphide–oxide lead and zinc ores, which underlines the potential of this approach. We also propose a conceptual flow diagram for the hydrometallurgical processing of these ores.

S. Moradi; A.J. Monhemius

2011-01-01T23:59:59.000Z

208

Corrosion-resistant uranium  

DOE Patents [OSTI]

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

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

1983-01-01T23:59:59.000Z

209

Corrosion-resistant uranium  

DOE Patents [OSTI]

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

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

1981-10-21T23:59:59.000Z

210

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado: Revision 5  

SciTech Connect (OSTI)

Title 1 of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the inactive Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. Title 2 of the UMTRCA authorized the US Nuclear Regulatory Commission (NRC) or agreement state to regulate the operation and eventual reclamation of active uranium processing sites. The uranium mill tailings at the site were removed and reprocessed from 1977 to 1979. The contaminated areas include the former tailings area, the mill yard, the former ore storage area, and adjacent areas that were contaminated by uranium processing activities and wind and water erosion. The Naturita remedial action would result in the loss of 133 acres (ac) of contaminated soils at the processing site. If supplemental standards are approved by the NRC and the state of Colorado, approximately 112 ac of steeply sloped contaminated soils adjacent to the processing site would not be cleaned up. Cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers.

Not Available

1994-10-01T23:59:59.000Z

211

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

SciTech Connect (OSTI)

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

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

2009-03-01T23:59:59.000Z

212

Method of winning aluminum metal from aluminous ore  

DOE Patents [OSTI]

Aluminous ore such as bauxite containing alumina is blended with coke or other suitable form of carbon and reacted with sulfur gas at an elevated temperature. For handling, the ore and coke can be extruded into conveniently sized pellets. The reaction with sulfur gas produces molten aluminum sulfide which is separated from residual solid reactants and impurities. The aluminum sulfide is further increased in temperature to cause its decomposition or sublimation, yielding aluminum subsulfide liquid (AlS) and sulfur gas that is recycled. The aluminum monosulfide is then cooled to below its disproportionation temperature to again form molten aluminum sulfide and aluminum metal. A liquid-liquid or liquid-solid separation, depending on the separation temperature, provides product aluminum and aluminum sulfide for recycle to the disproportionation step.

Loutfy, Raouf O. (Naperville, IL); Keller, Rudolf (Naperville, IL); Yao, Neng-Ping (Clarendon Hills, IL)

1981-01-01T23:59:59.000Z

213

REMNANT COLLOFORM PYRITE AT THE HAILE GOLD DEPOSIT, SOUTH CAROLINA: A TEXTURAL KEY TO GENESIS  

Science Journals Connector (OSTI)

...to100-mum-wide) late gold having a composition of Au0.8-0.9Ag0.2-0...this type and mineralogical and agrochemical evidence thatprovides compelling...metal ores metamorphism mineral composition mineral deposits, genesis mineralization...

Nora Foley; Robert A. Ayuso; Robert Seal II

214

Method for providing uranium with a protective copper coating  

DOE Patents [OSTI]

The present invention is directed to a method for providing uranium metal with a protective coating of copper. Uranium metal is subjected to a conventional cleaning operation wherein oxides and other surface contaminants are removed, followed by etching and pickling operations. The copper coating is provided by first electrodepositing a thin and relatively porous flash layer of copper on the uranium in a copper cyanide bath. The resulting copper-layered article is then heated in an air or inert atmosphere to volatilize and drive off the volatile material underlying the copper flash layer. After the heating step an adherent and essentially non-porous layer of copper is electro-deposited on the flash layer of copper to provide an adherent, multi-layer copper coating which is essentially impervious to corrosion by most gases.

Waldrop, Forrest B. (Powell, TN); Jones, Edward (Knoxville, TN)

1981-01-01T23:59:59.000Z

215

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

Science Journals Connector (OSTI)

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

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

2009-05-01T23:59:59.000Z

216

Baseline risk assessment of ground water contamination at the Monument Valley uranium mill tailings site Cane Valley, Arizona  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the Monument Valley UMTRA Project site near Cane Valley, Arizona, was completed in 1994. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Adverse ecological and agricultural effects may also result from exposure to contaminated ground water. For example, livestock should not be watered with contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site investigations will be used to determine a compliance strategy to comply with the UMTRA ground water standards.

NONE

1996-03-01T23:59:59.000Z

217

The role of magmas in the formation of hydrothermal ore deposits  

Science Journals Connector (OSTI)

... their active equivalents-such as volcanic systems with high-temperature fumaroles and acidic springs, and geothermal systems with neutral-pH hot springs and geysers-are known, and have thus been ... -2 km\tVery low salinity, gas-rich, neutral pH\tAu(Ag, Pb-Zn) Geothermal systems with neutral-pH hot springs, mud pools Distant (?) from magmatic heat ...

Jeffrey W. Hedenquist; Jacob B. Lowenstern

1994-08-18T23:59:59.000Z

218

Physicochemical properties of talc ore from Pout-Kelle and Memel deposits (central Cameroon)  

Science Journals Connector (OSTI)

...L., Leroy E. Lopez-Cuesta J.M. (2005) Influence of talc physical properties on the fire retarding behaviour of (Etylene-vinyl acetate copolymer/magnesium hydroxide/talc) composites. Polymer Degradation and Stability , 88 , 504-511...

C. NKOUMBOU; F. VILLIERAS; O. BARRES; I. BIHANNIC; M. PELLETIER; A. RAZAFITIANAMAHARAVO; V. METANG; C. YONTA NGOUNE; D. NJOPWOUO; J. YVON

219

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

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

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

220

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

Note: This page contains sample records for the topic "uranium ore deposits" 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

The conceptual design of an integrated energy efficient ore reduction plant / Albertus André du Toit.  

E-Print Network [OSTI]

??This study explores ways to determine the energy efficiency of a pyrometallurgical ore reduction plant and measures to improve it. The feasibility of building a… (more)

Du Toit, Albertus André

2014-01-01T23:59:59.000Z

222

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

223

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.

224

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

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

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

2003-07-01T23:59:59.000Z

225

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

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

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

2003-07-01T23:59:59.000Z

226

2013 Uranium Marketing Annual Report  

Gasoline and Diesel Fuel Update (EIA)

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

227

U.S.Uranium Reserves  

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

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

228

2013 Uranium Marketing Annual Report  

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

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

229

2013 Uranium Marketing Annual Report  

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

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

230

Marathon/Vitro to seek uranium  

Science Journals Connector (OSTI)

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

1967-03-13T23:59:59.000Z

231

Final Uranium Leasing Program Programmatic Environmental Impact...  

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

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...

232

FIFTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{reg_sign} GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200-350 F. Room temperature leak test failures have been experienced in 6 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30-48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the Orings displayed a compression set ranging from 51-95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350-400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests the CSR model predictions provide a conservative prediction of service life relative to the leak rate criterion. Failure data at lower temperatures are needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.; Hoffman, E.

2011-04-11T23:59:59.000Z

233

FIFTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{sup reg.} GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200--350 F. Room temperature leak test failures have been experienced in 5 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30--48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200--300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the O-rings displayed a compression set ranging from 51--95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350--400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests that CSR model predictions provide a conservative prediction of service life relative to the leak rate criterion. Failure data at lower temperatures is needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.; Hoffman, E.

2010-11-01T23:59:59.000Z

234

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

235

Radon releases from Australian uranium mining and milling projects: assessing the UNSCEAR approach  

Science Journals Connector (OSTI)

The release of radon gas and progeny from the mining and milling of uranium-bearing ores has long been recognised as a potential radiological health hazard. The standards for exposure to radon and progeny have decreased over time as the understanding of their health risk has improved. In recent years there has been debate on the long-term releases (10,000 years) of radon from uranium mining and milling sites, focusing on abandoned, operational and rehabilitated sites. The primary purpose has been estimates of the radiation exposure of both local and global populations. Although there has been an increasing number of radon release studies over recent years in the USA, Australia, Canada and elsewhere, a systematic evaluation of this work has yet to be published in the international literature. This paper presents a detailed compilation and analysis of Australian studies. In order to quantify radon sources, a review of data on uranium mining and milling wastes in Australia, as they influence radon releases, is presented. An extensive compilation of the available radon release data is then assembled for the various projects, including a comparison to predictions of radon behaviour where available. An analysis of cumulative radon releases is then developed and compared to the UNSCEAR approach. The implications for the various assessments of long-term releases of radon are discussed, including aspects such as the need for ongoing monitoring of rehabilitation at uranium mining and milling sites and life-cycle accounting.

Gavin M. Mudd

2008-01-01T23:59:59.000Z

236

Convergence of a MFEFV method for two phase flow with applications to heap leaching of copper ores  

E-Print Network [OSTI]

Convergence of a MFE­FV method for two phase flow with applications to heap leaching of copper ores in porous media, with applications to heap leaching of copper ores. These approximations are based on mixed

Sepúlveda, Mauricio

237

Butyl rubber O-ring seals: Revision of test procedures for stockpile materials  

SciTech Connect (OSTI)

Extensive testing showed little correlation between test slab and O-ring performance. New procedures, comparable to those used with the traditional test slabs, were defined for hardness, compression set, and tensile property testing on sacrificial O-ring specimens. Changes in target performance values were made as needed and were, in one case, tightened to reflect the O-ring performance data. An additional study was carried out on O-ring and slab performance vs cure cycle and showed little sensitivity of material performance to large changes in curing time. Aging and spectra of certain materials indicated that two sets of test slabs from current vendor were accidently made from EPDM rather than butyl rubber. Random testing found no O-rings made from EPDM. As a result, and additional spectroscope test will be added to the product acceptance procedures to verify the type of rubber compound used.

Domeier, L.A.; Wagter, K.R.

1996-12-01T23:59:59.000Z

238

Deposition Process  

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

Pulsed Plasma Processing Pulsed Plasma Processing NEW: Downloadable: Invited Talk "Pulsed Metal Plasmas," presented at the 2006 AVS Meeting, San Francisco, California, November 15, 2006. (PDF, file size 8 MB). Plasma Sources for Window Coatings Deposition processes for low-emittance and solar control coatings can be improved through the use of advanced plasma technology developed at LBNL. A new type of constricted glow-discharge plasma source was selected for the 1997 R&D 100 Award. Invented by LBNL researchers Andre Anders, Mike Rubin, and Mike Dickinson, the source was designed to be compatible with industrial vacuum deposition equipment and practice. Construction is simple, rugged and inexpensive. It can operate indefinitely over a wide range of chamber pressure without any consumable parts such as filaments or grids. Several different gases including Argon, Oxygen and Nitrogen have been tested successfully.

239

Geophysical modeling of two willemite deposits, Vazante (Brazil) and Beltana (Australia) Richard A. Krahenbuhl* and Murray Hitzman  

E-Print Network [OSTI]

of ore bodies or through imaging of associated hydrothermal alteration. Introduction Due to recent technological advances in developing solvent-extraction and electro-winning processes for treatment of zinc by conventional processing techniques and geophysical inversion. Vazante deposit in Brazil The Vazante willemite

240

Pulsed Laser Deposition | EMSL  

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

Pulsed Laser Deposition Pulsed Laser Deposition EMSL's pulsed laser deposition (PLD) system is designed for epitaxial growth of oxide, ceramic, or synthetic mineral thin films and...

Note: This page contains sample records for the topic "uranium ore deposits" 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

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

242

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

243

FAQ 7-How is depleted uranium produced?  

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

244

Uranyl Protoporphyrin: a New Uranium Complex  

Science Journals Connector (OSTI)

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

ROBERT E. BASES

1957-07-26T23:59:59.000Z

245

Uranium: Environmental Pollution and Health Effects  

Science Journals Connector (OSTI)

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

D. Melo; W. Burkart

2011-01-01T23:59:59.000Z

246

Safe Operating Procedure SAFETY PROTOCOL: URANIUM  

E-Print Network [OSTI]

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

Farritor, Shane

247

A review of uranium economics  

Science Journals Connector (OSTI)

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

A.K. Mazher

2009-01-01T23:59:59.000Z

248

Uranium Mining Life-Cycle Energy Cost vs. Uranium Resources  

Science Journals Connector (OSTI)

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

W. Eberhard Falck

2012-01-01T23:59:59.000Z

249

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

Science Journals Connector (OSTI)

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

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

2009-05-01T23:59:59.000Z

250

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

Science Journals Connector (OSTI)

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

J F Hainfeld

1992-01-01T23:59:59.000Z

251

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

Science Journals Connector (OSTI)

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

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

2013-04-01T23:59:59.000Z

252

Depleted Uranium Hexafluoride Management  

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

253

Disposition of uranium-233  

SciTech Connect (OSTI)

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

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

1997-10-16T23:59:59.000Z

254

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,

255

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

256

Uranium Enrichment's $7-Billion Uncertainty  

Science Journals Connector (OSTI)

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

COLIN NORMAN

1986-04-18T23:59:59.000Z

257

2013 Uranium Marketing Annual Report  

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

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

258

2013 Uranium Marketing Annual Report  

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

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

259

2013 Uranium Marketing Annual Report  

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

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

260

2013 Uranium Marketing Annual Report  

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

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

Note: This page contains sample records for the topic "uranium ore deposits" 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

2013 Domestic Uranium Production Report  

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

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

262

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

263

Inositol hexaphosphate: a potential chelating agent for uranium  

Science Journals Connector (OSTI)

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

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

2007-11-01T23:59:59.000Z

264

An Approach to Overseas Iron Ore Investment Risk Assessment Based on Fuzzy Neural Network  

Science Journals Connector (OSTI)

The iron ore investment overseas influenced by a variety of risk factors including geological reserves risk, market risk, the risk of the investment environment, political and legal risks, and etc. Based on the t...

Li Guo; Caiwu Lu; Zhen Yang

2011-01-01T23:59:59.000Z

265

Iron ore and coal: pricing and volume up for these key export commodities  

SciTech Connect (OSTI)

Australia's huge coal and iron ore industries are booming. Up until now, the majors have benefited handsomely, but smaller players are beginning to muscle in. The article discusses development in both industries. 1 fig., 4 photos.

NONE

2006-01-15T23:59:59.000Z

266

Aging of Weapon Seals – An Update on Butyl O-ring Issues  

SciTech Connect (OSTI)

During testing under the Enhanced Surveillance Campaign in 2001, preliminary data detected a previously unknown and potentially serious concern with recently procured butyl o-rings on several programs. All butyl o-rings molded from a proprietary formulation throughout the period circa 1999 through 2001 had less than a full cure. Engineering judgment was that under curing is detrimental and could possibly lead to sub-optimum performance or, in the worst case, premature seal failure. An aging study was undertaken to ensure that suspect o-rings installed in the stockpile will retain sufficient sealing force for a minimum ten-year service life. A new prediction model developed for this study indicates suspect o-rings do not need to be replaced before the ten-year service life. Long-term testing results are reported on a yearly basis to validate the prediction model. This report documents the aging results for the period September 2002 to January 2011.

Wilson, Mark H.

2011-07-13T23:59:59.000Z

267

Evaluation of ettringite-related swelling mechanisms for treated chromite ore processing residue  

Science Journals Connector (OSTI)

Accelerated one-dimensional unconfined swell tests were conducted for ferrous sulfate chromite ore processing residue (COPR) field-treated samples. The field-treated samples were subjected to wet and dry cycle...

Deok Hyun Moon; Mahmoud Wazne…

2014-09-01T23:59:59.000Z

268

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

Science Journals Connector (OSTI)

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

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

2001-12-01T23:59:59.000Z

269

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

Science Journals Connector (OSTI)

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

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

2009-01-01T23:59:59.000Z

270

NO release during chemical looping combustion with iron ore as an oxygen carrier  

Science Journals Connector (OSTI)

Abstract Chemical looping combustion (CLC) is one of the promising technologies to capture CO2 with low cost. Owing to the existence of nitrogen in fuel, the emission of fuel-NOx is a significant concern during the CLC process. This work evaluated NO release in the CLC process of bituminous coal and petcoke using iron ore as an oxygen carrier in a fluidized bed. The effect of several factors was evaluated, including bed material, fuel type, temperature and gasification medium. The results indicate that in the fuel reactor (FR), fuel-NOx due to the reaction between NH3/HCN and iron ore was supported only when the iron ore was reduced from Fe2O3 to Fe3O4. Compared with the case of an inert bed material, NO yield during the gasification in an iron ore bed material was relatively higher due to the enhanced char-gasification and the oxidization effect of iron ore. For the bituminous coal, NO release in FR was mainly due to the volatile release and subsequent oxidation by iron ore. For the petcoke process, NO release in FR could mainly be ascribed to the char-gasification and subsequent oxidization of NOx-precursors by iron ore. The elevated temperature and the use of H2O/N2 in comparison to CO2 could efficiently enhance the fuel conversion and \\{NOx\\} precursors release in FR. Thus, NO yield in FR increased, whereas that in AR correspondingly decreased. Furthermore, the NO release during continuous coal CLC was investigated in a 1 kWth CLC prototype based on the iron ore oxygen carrier. Overall, the elevated fuel reactor temperature and the use of H2O as gasification medium are beneficial to reduce NO release in the CLC system.

Haiming Gu; Laihong Shen; Zhaoping Zhong; Xin Niu; Huijun Ge; Yufei Zhou; Shen Xiao; Shouxi Jiang

2014-01-01T23:59:59.000Z

271

Polyethylene Encapsulated Depleted Uranium  

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

272

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

Science Journals Connector (OSTI)

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

Allan R. Eberle; Morris W. Lerner

1967-01-01T23:59:59.000Z

273

NINTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton® GLT O-rings used in the Model 9975 package has been ongoing since 2004 at the Savannah River National Laboratory. One approach has been to periodically evaluate the leak performance of O-rings being aged in mock-up 9975 Primary Containment Vessels (PCVs) at elevated temperatures. Other methods such as compression-stress relaxation (CSR) tests and field surveillance are also on-going to evaluate O-ring behavior. Seventy tests using PCV mock-ups were assembled and heated to temperatures ranging from 200 to 450 ºF. They were leak-tested initially and have been tested periodically to determine if they continue to meet the leak-tightness criterion defined in ANSI standard N14.5-97. Due to material substitution, fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 ºF. High temperature aging continues for 23 GLT O-ring fixtures at 200 – 270 ºF. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 ºF and higher temperatures, and in 8 fixtures aging at 300 ºF. The earliest 300 °F GLT O-ring fixture failure was observed at 34 months. The remaining GLT O-ring fixtures aging at 300 ºF have been retired from testing following more than 5 years at temperature without failure. No failures have yet been observed in GLT O-ring fixtures aging at 200 ºF for 72 - 96 months, which bounds O-ring temperatures anticipated during storage in K-Area Complex (KAC). Based on expectations that the 200 ºF fixtures will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging in 2011 at 270 ºF, with hopes that they may reach a failure condition before the 200 ºF fixtures, thus providing additional time to failure data. High temperature aging continues for 6 GLT-S O-ring fixtures at 200 – 300 ºF. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 ºF. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 - 300 ºF for 54 - 57 months. No additional O-ring failures have been observed since the last interim report was issued. Aging and periodic leak testing will continue for the remaining PCV fixtures. Additional irradiation of several fixtures is recommended to maintain a balance between thermal and radiation exposures similar to that experienced in storage, and to show the degree of consistency of radiation response between GLT and GLT-S O-rings.

Daugherty, W.

2014-08-06T23:59:59.000Z

274

Derivation of residual radioactive material guidelines for uranium in soil at the Middlesex Sampling Plant Site, Middlesex, New Jersey  

SciTech Connect (OSTI)

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed.

Dunning, D.E. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-02-01T23:59:59.000Z

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 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

276

Uranium Metal: Potential for Discovering Commercial Uses  

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

277

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

278

Polyethylene Encapsulation of Depleted Uranium Trioxide  

Science Journals Connector (OSTI)

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

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

2002-01-01T23:59:59.000Z

279

Statistical data of the uranium industry  

SciTech Connect (OSTI)

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

none,

1981-01-01T23:59:59.000Z

280

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

Note: This page contains sample records for the topic "uranium ore deposits" 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

Y-12 Uranium Exposure Study  

SciTech Connect (OSTI)

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

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

1999-08-05T23:59:59.000Z

282

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

283

The Uranium Institute 24th Annual Symposium  

E-Print Network [OSTI]

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

Laughlin, Robert B.

284

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

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

Richard Stone

2002-09-13T23:59:59.000Z

285

D Riso-R-429 Automated Uranium  

E-Print Network [OSTI]

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

286

THE PRESENT SITUATION IN THE RADIUM INDUSTRY  

Science Journals Connector (OSTI)

...running about 2 per cent. uranium oxide content. The deposits...disintegra-tioll product of uranium, there being only one...200,000 parts of uranium in ainy ore. Never a...and commercial staff depleted. In addition, it was...needs radium to combat cancer and it, was recognized...

H. E. Bishop

1923-03-23T23:59:59.000Z

287

THE PRESENT SITUATION IN THE RADIUM INDUSTRY  

Science Journals Connector (OSTI)

...running about 2 per cent. uranium oxide content. The deposits...disintegra-tioll product of uranium, there being only one...200,000 parts of uranium in ainy ore. Never a...and commercial staff depleted. In addition, it was...If the employee's health has become impaired...

H. E. Bishop

1923-03-23T23:59:59.000Z

288

SIXTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE  

SciTech Connect (OSTI)

A series of experiments to monitor the aging performance of Viton{reg_sign} GLT O-rings used in the Model 9975 package has been ongoing for seven years at the Savannah River National Laboratory. Seventy tests using mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested periodically to determine if they meet the criterion of leak-tightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 33 GLT O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 F and higher temperatures, and in 7 fixtures aging at 300 F. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 41-60 months, which is still bounding to O-ring temperatures during storage in K-Area Complex (KAC). Based on expectations that the fixtures aging at 200 F will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging within the past year at an intermediate temperature of 270 F, with hopes that they may leak before the 200 F fixtures. High temperature aging continues for 6 GLT-S O-ring fixtures at 200-300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200-300 F for up to 26 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the Orings displayed a compression set ranging from 51-96%. This is greater than seen to date for packages inspected during KAC field surveillance (24% average). For GLT O-rings, separate service life estimates have been made based on the O-ring fixture leak test data and based on compression stress relaxation (CSR) data. These two predictive models show reasonable agreement at higher temperatures (350-400 F). However, at 300 F, the room temperature leak test failures to date experienced longer aging times than predicted by the CSR-based model. This suggests that extrapolations of the CSR model predictions to temperatures below 300 F will provide a conservative prediction of service life relative to the leak rate criterion. Leak test failure data at lower temperatures are needed to verify this apparent trend. Insufficient failure data exist currently to perform a similar comparison for GLT-S O-rings. Aging and periodic leak testing will continue for the remaining fixtures.

Daugherty, W.

2011-08-31T23:59:59.000Z

289

Mobility of uranium, thorium and lanthanides around the Bangombe natural nuclear reactor (Gabon)  

SciTech Connect (OSTI)

New mineralogical and isotopic studies were carried out on samples form the Bangombe natural nuclear reactor. This reactor is located at shallow depth in the weathering profile and has been subjected to severe supergene alteration. Textural evidence indicates partial dissolution of uraninite in the Bangombe ore related to precipitation of Fe-Ti oxyhydroxides and clay minerals (kaolinite and metahalloysite). As a consequence of the alteration of the uraninite, uranium and fissiogenic rare earth elements were released in the clayey border of the reactor, whereas radiogenic {sup 232}Th remained confined in the close vicinity of the core. A retention effect is also evidenced, under reducing conditions, in the black shales located above the reactor.

Bros, R. [CEA CEN Cadarache, Saint Paul-lez-Durance (France); Gauthier-Lafaye, F.; Larque, P.; Samual, J.; Stille, P. [CNRS, Strasbourg (France)

1995-12-31T23:59:59.000Z

290

Aluminum-Containing Phases in Tank Waste: Precipitation and Deposition of Aluminum-Containing Phases  

SciTech Connect (OSTI)

Aluminosilicate deposit buildup experienced during the tank waste volume-reduction process at the Savannah River Site (SRS) required an evaporator to be shut down in October 1999. Recent investigations illustrated the accumulation 7 wt% uranium, 3% was 235U and absent of neutron poisons, within these deposits and presented a criticality concern. The Waste Processing Technology Section of Westinghouse Savannah River Company at SRS is now collaborating with a team from Pacific Northwest National Laboratory in efforts to identify the phases controlling uranium solubility and understand the conditions under which they precipitate.

Shas Mattigod; D.T. Hobbs; D. M. Wellman; I. Aksay; D. M. Dabbs

2006-06-01T23:59:59.000Z

291

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

SciTech Connect (OSTI)

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

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

2013-01-01T23:59:59.000Z

292

Uranium 2014 resources, production and demand  

E-Print Network [OSTI]

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

Organisation for Economic Cooperation and Development. Paris

2014-01-01T23:59:59.000Z

293

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"

294

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-

295

Uranium: Prices, rise, then fall  

SciTech Connect (OSTI)

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

296

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

297

Interactions of Jet Fuels with Nitrile O-Rings: Petroleum-Derived versus Synthetic Fuels  

SciTech Connect (OSTI)

A transition from petroleum-derived jet fuels to blends with Fischer-Tropsch (F-T) fuels, and ultimately fully synthetic hydro-isomerized F-T fuels has raised concern about the fate of plasticizers in nitrile-butadiene rubber o-rings that are contacted by the fuels as this transition occurs. The partitioning of plasticizers and fuel molecules between nitrile o-rings and petroleum-derived, synthetic, and additized-synthetic jet fuels has been measured. Thermal desorption of o-rings soaked in the various jet fuels followed by gas chromatographic analysis with a mass spectrometric detector showed many of the plasticizer and stabilizer compounds were removed from the o-rings regardless of the contact fuel. Fuel molecules were observed to migrate into the o-rings for the petroleum-derived fuel as did both the fuel and additive for a synthetic F-T jet fuel additized with benzyl alcohol, but less for the unadditized synthetic fuel. The specific compounds or classes of compounds involved in the partitioning were identified and a semiquantitative comparison of relative partitioning of the compounds of interest was made. The results provide another step forward in improving the confidence level of using additized, fuIly synthetic jet fuel in the place of petroleum-derived fueL

Gormley, R.J.; Link, D.D.; Baltrus, J.P.; Zandhuis, P.H.

2008-01-01T23:59:59.000Z

298

Physicochemical characterisation of depleted uranium (DU) particles at a UK firing test range  

Science Journals Connector (OSTI)

Depleted uranium (DU) particles were isolated from soils at Eskmeals, UK, where DU munitions have been tested against hard targets and unfired DU buried in soils for corrosion studies. Using electron microscopy and X-ray analyses, three classes of particles were identified: (1) DU aerosols and fragments, typically 1–20 ?m diameter, composed mainly of uranium as UO2 and U3O8, (2) solidified molten particles, typically 200–500 ?m diameter, composed of U, mixed with Fe from target materials and (3) deposits and coatings, often of metaschoepite on sand grains up to 500 ?m diameter. The first two particle types are derived from firing impacts, the last from corrosion of buried uranium metal. Alpha and mass spectrometry allowed quantitative elemental and isotopic characterisation of DU-containing particulate environmental samples.

Mustafa Sajih; Francis R. Livens; Rebeca Alvarez; Mathew Morgan

2010-01-01T23:59:59.000Z

299

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

SciTech Connect (OSTI)

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

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

1981-12-01T23:59:59.000Z

300

Finding a Link between Microbes and Mineral Deposits  

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

Finding a Link between Microbes and Mineral Deposits Finding a Link between Microbes and Mineral Deposits Contamination around mining sites is a significant problem worldwide. Acid mine drainage, for example, is a threat to surface and groundwater near mines. It occurs when metal-sulfide ores are exposed to air and water and the sulfide is transformed to sulfuric acid. Moreover, metals such as zinc are toxic and can leach into groundwater and contaminate wells and other drinking water supplies. Results of EDX (bottom left) and x-ray microprobe fluorescence (top right) analysis of specific biomineralized zinc sulfide precipitates. The sensitivity of the x-ray microprobe enables identification of arsenic and selenium constituents in the zinc sulfide precipitate. Above: Results of EDX (bottom left) and x-ray microprobe fluorescence (top

Note: This page contains sample records for the topic "uranium ore deposits" 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

In situ LA–MC–ICP–MS boron isotope and zircon U–Pb age determinations of Paleoproterozoic borate deposits in Liaoning Province, northeastern China  

Science Journals Connector (OSTI)

Abstract A large number of Paleoproterozoic borate deposits are hosted by the lower units of a volcanic-sedimentary sequence in Liaoning Province, northeastern China, and are a major source of boron in China. The ore-bearing wall rocks in the deposits are serpentinized ultrabasic rocks and carbonates, with layered leptynites, leptites, amphibolites, and migmatites adjacent to the ore. Both the borate ores and country rocks contain tourmaline, although the country rocks have much lower abundances of the mineral. Based on in situ boron isotope measurements using laser ablation–multi-collector–inductively coupled plasma–mass spectrometry (LA–MC–ICP–MS), boron isotope data show that: (1) ?11B values of borate ores range from + 6.8‰ to + 13.9‰ (mean + 10.8‰); (2) tourmalines from the borate ores have ?11B values from + 9.5‰ to + 12.7‰; and (3) the wall rocks within the borate ores yield slightly lower ?11B values ranging from + 5.7‰ to + 7.6‰, and those outside the deposits from ? 9.9‰ to ? 5.9‰. Positive ?11B values in borates as well as in tourmalines inside the mining area indicate that boron in these Paleoproterozoic borate deposits was derived from marine evaporites. ?34SV-CDT (where V-CDT is Vienna Canyon Diablo Troilite) values of borate ores, serpentinized marbles, and anhydrites range from + 16.1‰ to + 24.7‰, whereas ?13CV-PDB (where V-PDB is Vienna Pee Dee Belemnite) values of marbles range from + 3.2‰ to + 5.9‰. These isotopic characteristics are interpreted to reflect formation in a marine evaporative environment. LA–MC–ICP–MS zircon weighted207Pb/206Pb ages of leptite and serpentinized olivine basalt from the hanging wall of the borate deposits are 2139 ± 13 Ma and 2130 ± 19 Ma, respectively. Therefore, the (~ 2.2 Ga) borate deposits may have originated from marine evaporative boron-bearing sediments, which were interbedded within bimodal volcanic rocks during the early stages of development of the Liaoji rift.

Guyue Hu; Yanhe Li; Changfu Fan; Kejun Hou; Yue Zhao; Lingsen Zeng

2014-01-01T23:59:59.000Z

302

Evaluation of Reagent Emplacement Techniques for Phosphate-based Treatment of the Uranium Contamination Source in the 300 Area White Paper  

SciTech Connect (OSTI)

Persistent uranium contamination of groundwater under the 300 Area of the Hanford Site has been observed. The source of the uranium contamination resides in uranium deposits on sediments at the groundwater interface, and the contamination is mobilized when periodically wetted by fluctuations of Columbia River levels. Treatability work is ongoing to develop and apply phosphate-containing reagents to promote the formation of stable and insoluble uranium phosphate minerals (i.e., autunite) and other phosphate precipitates (di-calcium phosphate, apatite) to stabilize the uranium source. Technologies for applying phosphate-containing reagents by vertical percolation and lateral injection into sediments of the periodically wetted groundwater interface are being investigated. This report is a preliminary evaluation of technologies for lateral injection.

Nimmons, Michael J.

2010-06-04T23:59:59.000Z

303

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 (OSTI)

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

304

GRR/Section 14-OR-e - Water Pollution Control Facility Permit | Open Energy  

Open Energy Info (EERE)

GRR/Section 14-OR-e - Water Pollution Control Facility Permit GRR/Section 14-OR-e - Water Pollution Control Facility Permit < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 14-OR-e - Water Pollution Control Facility Permit 14OREWaterPollutionControlFacilityPermit.pdf Click to View Fullscreen Contact Agencies Oregon Department of Environmental Quality Regulations & Policies OAR Division 45 Regulations Pertaining to NPDES and WPCF Permits Triggers None specified Click "Edit With Form" above to add content 14OREWaterPollutionControlFacilityPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Oregon Department of Environmental Quality (ODEQ) issues Water

305

GRR/Section 3-OR-e - Noncompetitive Geothermal Lease | Open Energy  

Open Energy Info (EERE)

3-OR-e - Noncompetitive Geothermal Lease 3-OR-e - Noncompetitive Geothermal Lease < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 3-OR-e - Noncompetitive Geothermal Lease 03ORENoncompetitiveGeothermalLease.pdf Click to View Fullscreen Contact Agencies Oregon Department of State Lands Oregon Department of Environmental Quality Regulations & Policies OAR 141-075-0010 Geothermal Lease Regulations Triggers None specified Click "Edit With Form" above to add content 03ORENoncompetitiveGeothermalLease.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Noncompetitive geothermal leases are the default leasing option for

306

Method for the production of mineral wool and iron from serpentine ore  

SciTech Connect (OSTI)

Magnesium silicate mineral wools having a relatively high liquidus temperature of at least about 1400.degree. C. and to methods for the production thereof are provided. The methods of the present invention comprise melting a magnesium silicate feedstock (e.g., comprising a serpentine or olivine ore) having a liquidus temperature of at least about 1400.degree. C. to form a molten magnesium silicate, and subsequently fiberizing the molten magnesium silicate to produce a magnesium silicate mineral wool. In one embodiment, the magnesium silicate feedstock contains iron oxide (e.g., up to about 12% by weight). Preferably, the melting is performed in the presence of a reducing agent to produce an iron alloy, which can be separated from the molten ore. Useful magnesium silicate feedstocks include, without limitation, serpentine and olivine ores. Optionally, silicon dioxide can be added to the feedstock to lower the liquidus temperature thereof.

O'Connor, William K. (Albany, OR); Rush, Gilbert E. (Scio, OR); Soltau, Glen F. (Lebanon, OR)

2011-10-11T23:59:59.000Z

307

United States Office of Radiation and EPA 402-B-00-001 Environmental Protection Indoor Air August 2000  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Underground Mining of Uranium Ore . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 The Uranium Fuel Cycle . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 Uranium and Thorium Mill Tailings

308

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

309

An effective model for entropy deposition in high-energy pp, pA, and AA collisions  

E-Print Network [OSTI]

We introduce TRENTO, a new initial condition model for high-energy nuclear collisions based on eikonal entropy deposition via a "reduced thickness" function. The model simultaneously predicts the shapes of experimental proton-proton, proton-nucleus, and nucleus-nucleus multiplicity distributions, and generates nucleus-nucleus eccentricity harmonics consistent with experimental flow constraints. In addition, the model provides a possible resolution to the "knee" puzzle in ultra-central uranium-uranium collisions.

J. Scott Moreland; Jonah E. Bernhard; Steffen A. Bass

2014-12-15T23:59:59.000Z

310

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"

311

:- : 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

312

Potential Uses of Depleted Uranium  

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

313

Semiconductive Properties of Uranium Oxides  

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

314

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"

315

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"

316

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

SciTech Connect (OSTI)

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

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2001-07-01T23:59:59.000Z

317

Depleted Uranium (DU) Cermet Waste Package  

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

318

Depleted Uranium Uses Research and Development  

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

319

Uranium 2009 resources, production and demand  

E-Print Network [OSTI]

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

Organisation for Economic Cooperation and Development. Paris

2010-01-01T23:59:59.000Z

320

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).

Note: This page contains sample records for the topic "uranium ore deposits" 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

Review of uranium bioassay techniques  

SciTech Connect (OSTI)

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

Bogard, J.S.

1996-04-01T23:59:59.000Z

322

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

323

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

324

Depleted uranium exposure and health effects in Gulf War veterans  

Science Journals Connector (OSTI)

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

2006-01-01T23:59:59.000Z

325

Excretion of depleted uranium by Gulf war veterans  

Science Journals Connector (OSTI)

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

R. E. Toohey

2003-07-01T23:59:59.000Z

326

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

Science Journals Connector (OSTI)

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

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

2006-04-15T23:59:59.000Z

327

Uranium Pollution of Meat in Tien-Shan  

Science Journals Connector (OSTI)

Uranium in water, soil, fodder and food products (especially meat) was studied in areas of former Soviet uranium industry in Tien-Shan 1950–1970. Uranium environment migration was very intensive in Tien-Shan, due...

Rustam Tuhvatshin; Igor Hadjamberdiev…

2008-01-01T23:59:59.000Z

328

Sandy Depositional Systems  

Science Journals Connector (OSTI)

Why is the study of sandy depositional systems central to the understanding of sand and sandstone? From earliest times geologists have wanted to know where and under what conditions a sandstone was deposited—t...

F. J. Pettijohn; Paul Edwin Potter; Raymond Siever

1987-01-01T23:59:59.000Z

329

Uranium Weapons Components Successfully Dismantled | National...  

National Nuclear Security Administration (NNSA)

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

330

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

331

U.S. Uranium Reserves Estimates  

Gasoline and Diesel Fuel Update (EIA)

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

332

Adsorptive Stripping Voltammetric Measurements of Trace Uranium...  

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

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

333

Biogeochemical Processes In Ethanol Stimulated Uranium Contaminated...  

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

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

334

Statistical data of the uranium industry  

SciTech Connect (OSTI)

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

none,

1982-01-01T23:59:59.000Z

335

Development of NF3 Deposit Removal Technology for the Portsmouth Gaseous Diffusion Plant  

SciTech Connect (OSTI)

This paper summarizes the Battelle, Stoller, and WASTREN (BSW) team's efforts, to date, in support of the United States Department of Energy's plans to remove uranium and technetium deposits before decommissioning the Portsmouth Gaseous Diffusion Plant. The BSW team investigated nitrogen trifluoride (NF{sub 3}) as a safer yet effective alternative gaseous treatment to the chlorine trifluoride (ClF{sub 3})-elemental fluorine (F{sub 2}) treatment currently used to remove uranium and technetium deposits from the uranium enrichment cascade. Both ClF{sub 3} and F{sub 2} are highly reactive, toxic, and hazardous gases, while NF{sub 3}, although toxic [1], is no more harmful than moth balls [2]. BSW's laboratory thermo-analytical and laboratory-scale prototype studies with NF{sub 3} established that thermal NF{sub 3} can effectively remove likely and potential uranium (UO{sub 2}F{sub 2} and UF{sub 4}) and technetium deposits (a surrogate deposit material, TcO{sub 2}, and pertechnetates) by conversion to volatile compounds. Our engineering evaluations suggest that NF{sub 3}'s effectiveness could be enhanced by combining with a lesser concentration of ClF{sub 3}. BSW's and other's studies indicate compatibility with Portsmouth materials of construction (aluminum, copper, and nickel). (authors)

Scheele, R.D.; McNamara, B.K.; Rapko, B.M.; Edwards, M.K.; Kozelisky, A.E.; Daniel, R.C. [Battelle Pacific Northwest Division, PO Box 999, Battelle Blvd, Richland, Washington 99352 (United States); McSweeney, T.I.; Maharas, S.J.; Weaver, P.J.; Iwamasa, K.J. [Battelle Columbus Operations, 505 King Avenue, Columbus, Ohio 43201 (United States); Kefgen, R.B. [WASTREN, Inc., 1864 Shyville Road, Piketon, Ohio 45661 (United States)

2006-07-01T23:59:59.000Z

336

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

Science Journals Connector (OSTI)

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

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

2009-01-01T23:59:59.000Z

337

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

Science Journals Connector (OSTI)

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

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

2009-01-01T23:59:59.000Z

338

Pre-Colombian Mercury Pollution Associated with the Smelting of Argentiferous Ores in the Bolivian Andes  

E-Print Network [OSTI]

large-scale Hg emissions. Pre-industrial emissions of heavy metals associated with mineral extraction) (Lee et al. 2008). In the New World, early metal pollution appears to be limited Ã? Royal SwedishREPORT Pre-Colombian Mercury Pollution Associated with the Smelting of Argentiferous Ores

Wolfe, Alexander P.

339

1. Department, Course Number, Title ORE 664, Nearshore Processes and Sediment Transport  

E-Print Network [OSTI]

1. Department, Course Number, Title ORE 664, Nearshore Processes and Sediment Transport 2 Sediment transport by waves and currents in coastal areas and its effect on morphological processes. Effect Reference books: 1. Beach Processes and Sedimentation, P.D. Komar, 2nd Edition, Prentice-Hall, Inc., 1998 2

Frandsen, Jannette B.

340

COURSE INFORMATION AND OUTLINE ORE 609 -HYDRODYNAMICS OF FLUID-BODY INTERACTION  

E-Print Network [OSTI]

IN THE ORE LIBRARY · Sarpkaya and Isaacson: Mechanics of Wave Forces on Offshore Structures · Newman: Marine Hydrodynamics · Currie: Fundamental Mechanics of Fluids · Ippen: Estuary and Coastline Hydrodynamics · Mei: The Applied Dynamics of Ocean Surface Waves · Abramowitz and Stegun: Handbook of Mathematical Functions

Frandsen, Jannette B.

Note: This page contains sample records for the topic "uranium ore deposits" 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

Utilization of geothermal energy in the mining and processing of tungsten ore. Final report  

SciTech Connect (OSTI)

The engineering, economic, and environmental feasibility of the use of low and moderate temperature geothermal heat in the mining and processing of tungsten ore is explored. The following are covered: general engineering evaluation, design of a geothermal energy system, economics, the geothermal resource, the institutional barriers assessment, environmental factors, an alternate geothermal energy source, and alternates to geothermal development. (MHR)

Erickson, M.V.; Lacy, S.B.; Lowe, G.D.; Nussbaum, A.M.; Walter, K.M.; Willens, C.A.

1981-01-01T23:59:59.000Z

342

REVIEW OF AGING DATA ON EPDM O-RINGS IN THE H1616 SHIPPING PACKAGE  

SciTech Connect (OSTI)

Currently, all H1616 shipping package containers undergo annual re-verification testing, including containment vessel leak testing to verify leak-tightness (<1 x 10{sup -7} ref cc/sec air) as per ANSI N14.5. The purpose of this literature review is to supplement aging studies currently being performed by SRNL on the EPDM O-rings to provide the technical basis for extending annual re-verification testing for the H1616 shipping package and to predict the life of the seals at bounding service conditions. The available data suggest that the EPDM O-rings can retain significant mechanical properties and sealing force at or below bounding service temperatures (169 F or 76 C) beyond the 1 year maintenance period. Interpretation of available data suggests that a service life of at least 2 years and potentially 4-6 years may be possible at bounding temperatures. Seal lifetimes at lower, more realistic temperatures will likely be longer. Being a hydrocarbon elastomer, EPDM O-rings may exhibit an inhibition period due to the presence of antioxidants. Once antioxidants are consumed, mechanical properties and seal performance could decline at a faster rate. Testing is being performed to validate the assumptions outlined in this report and to assess the long-term performance of O-ring seals under actual service conditions.

Skidmore, E.

2012-03-27T23:59:59.000Z

343

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

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

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

344

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

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

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

345

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

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

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

346

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

Energy Savers [EERE]

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

347

President Truman Increases Production of Uranium and Plutonium...  

National Nuclear Security Administration (NNSA)

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

348

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

Science Journals Connector (OSTI)

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

R. L. Kathren

2001-05-01T23:59:59.000Z

349

Modeling of Depleted Uranium Transport in Subsurface Systems  

Science Journals Connector (OSTI)

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

J. Paul Chen; Sotira Yiacoumi

2002-10-01T23:59:59.000Z

350

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

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

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

351

3rd Quarter 2014 Domestic Uranium Production Report  

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

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

352

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

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

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

353

Morphological characterization of O-rings from the GCEP long-term test program. [Dupont 1141, 3M 4762 and 4768, and Parker V884-75 O-rings  

SciTech Connect (OSTI)

Based on the results of the morphological and structural characterizations reported herein the following conclusions have been reached. (1) O-rings of any of the four materials studied should last at least 10 years when employed in a standard static seal configuration utilizing a groove that holds the O-ring. (2) Such a static seal provides considerable protection from reaction. (3) The reaction of UF/sub 6/ with the O-ring material is the dominant degradation reaction; however there are effects on a least one compound that appear to be related to HF penetration into the O-ring matrix. The slow nature of the reaction of UF/sub 6/ with the flanged O-rings makes life projections quite difficult using any means. It would appear that one of the best methods for determining the life of these materials would be actual use combined with routine long-term inspection/sampling of a selected typical subset of O-rings. At GCEP conditions it would not be surprising to find the actual life of the O-rings is longer than any anticipated operation time of the plant facility. 16 figures, 1 table.

Hughes, M.R.; Nolan, T.A.

1984-07-30T23:59:59.000Z

354

Mantle-derived noble gases in ore-forming fluids of the granite-related Yaogangxian tungsten deposit, Southeastern China  

Science Journals Connector (OSTI)

The concentrations of 4He are (0.1–14.5)?×?10?6cm3STPg?1 and those of 40Ar are (0.6–22.0)?×?10?7cm3STPg?1. The large variations of noble gas concentrations probably reflect variations in fluid inclusion abundance...

Rui-Zhong Hu; Xian-Wu Bi; Guo-Hao Jiang; Hong-Wei Chen…

2012-08-01T23:59:59.000Z

355

The influence of fractal size distribution of covers on radon exhalation from uranium mill tailings  

Science Journals Connector (OSTI)

Tailings produced during mining and milling of uranium ores represent potentially large volumes of low level radioactive materials. A typical environmental problem associated with mill tailings is radon emanation. Covering tailings is widely applied to reduce radon exhalation rate. In this paper, the fractal theories and field covering tests are used to study the fractal characters of size distribution of six types of covering materials, including waste rock, sand, laterite, kaolin, mixture of sand and laterite, and mixture of waste rock and laterite, and their influences on radon exhalation. The size distributions of uranium tailings and the six aforementioned covering materials all exhibit a good fractal structure. The contents of fine grain increase with the increasing value of fractal dimension. The results of field radon measurement show that the radon emanation rate of tailings without covers is 14.7–18.6 Bq/m2 s. Covering tests were carried out of the six abovementioned covering materials with thickness of 0.4 m, 0.8 m, 1.2 m, 1.6 m and 2.0 m. The results indicate that the application of these materials for cover layers can decrease the radon exhalation rate markedly. The effectiveness of a cover layer in reducing radon exhalation is related to its fractal texture of size distribution. Under the same thickness conditions, the attenuation coefficient of radon exhalation rate increases with the increasing fractal dimension of size distribution of covers. The empirical expressions of the attenuation coefficients in relation to fractal dimension D of size distribution and thickness x of covers is obtained for evaluating the effectiveness of final covers for uranium tailings impoundments.

Kaixuan Tan; Zehua Liu; Liangshu Xia; Junwen Lv; Hanqiao Hu

2012-01-01T23:59:59.000Z

356

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

...poses virtually no cancer risk. Moreover, Danesi's...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...

Richard Stone

2002-09-13T23:59:59.000Z

357

IPNS enriched uranium booster target  

SciTech Connect (OSTI)

Since startup in 1981, IPNS has operated on a fully depleted /sup 238/U target. With the booster as in the present system, high energy protons accelerated to 450 MeV by the Rapid Cycling Synchrotron are directed at the target and by mechanisms of spallation and fission of the uranium, produce fast neutrons. The neutrons from the target pass into adjacent moderator where they slow down to energies useful for spectroscopy. The target cooling systems and monitoring systems have operated very reliably and safely during this period. To provide higher neutron intensity, we have developed plans for an enriched uranium (booster) target. HETC-VIM calculations indicate that the target will produce approx.90 kW of heat, with a nominal x5 gain (k/sub eff/ = 0.80). The neutron beam intensity gain will be a factor of approx.3. Thermal-hydraulic and heat transport calculations indicate that approx.1/2 in. thick /sup 235/U discs are subject to about the same temperatures as the present /sup 238/U 1 in. thick discs. The coolant will be light demineralized water (H/sub 2/O) and the coolant flow rate must be doubled. The broadening of the fast neutron pulse width should not seriously affect the neutron scattering experiments. Delayed neutrons will appear at a level about 3% of the total (currently approx.0.5%). This may affect backgrounds in some experiments, so that we are assessing measures to control and correct for this (e.g., beam tube choppers). Safety analyses and neutronic calculations are nearing completion. Construction of the /sup 235/U discs at the ORNL Y-12 facility is scheduled to begin late 1985. The completion of the booster target and operation are scheduled for late 1986. No enriched uranium target assembly operating at the projected power level now exists in the world. This effort thus represents an important technological experiment as well as being a ''flux enhancer''.

Schulke, A.W. Jr.

1985-01-01T23:59:59.000Z

358

Uranium in prehistoric Indian pottery  

E-Print Network [OSTI]

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

Filberth, Ernest William

2012-06-07T23:59:59.000Z

359

Overview of Depleted Uranium Hexafluoride Management Program  

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

360

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

Science Journals Connector (OSTI)

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

A Bleise; P.R Danesi; W Burkart

2003-01-01T23:59:59.000Z

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


361

Removal of uranium from uranium-contaminated soils -- Phase 1: Bench-scale testing. Uranium in Soils Integrated Demonstration  

SciTech Connect (OSTI)

To address the management of uranium-contaminated soils at Fernald and other DOE sites, the DOE Office of Technology Development formed the Uranium in Soils Integrated Demonstration (USID) program. The USID has five major tasks. These include the development and demonstration of technologies that are able to (1) characterize the uranium in soil, (2) decontaminate or remove uranium from the soil, (3) treat the soil and dispose of any waste, (4) establish performance assessments, and (5) meet necessary state and federal regulations. This report deals with soil decontamination or removal of uranium from contaminated soils. The report was compiled by the USID task group that addresses soil decontamination; includes data from projects under the management of four DOE facilities [Argonne National Laboratory (ANL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), and the Savannah River Plant (SRP)]; and consists of four separate reports written by staff at these facilities. The fundamental goal of the soil decontamination task group has been the selective extraction/leaching or removal of uranium from soil faster, cheaper, and safer than current conventional technologies. The objective is to selectively remove uranium from soil without seriously degrading the soil`s physicochemical characteristics or generating waste forms that are difficult to manage and/or dispose of. Emphasis in research was placed more strongly on chemical extraction techniques than physical extraction techniques.

Francis, C. W.

1993-09-01T23:59:59.000Z

362

Reassessment of individual dosimetry of long-lived alpha radionuclides of uranium miners through experimental determination of urinary excretion of uranium  

Science Journals Connector (OSTI)

......iranium in urine of uranium miners as a tool for...230Th in excreta of uranium mill crushermen. Health Phys. (1983) 45...Measurement of daily urinary uranium excretion in German...potential intakes of depleted uranium(DU). Sci......

I. Malátová; V. Becková; L. Tomásek; M. Slezáková-Marusiaková; J. Hulka

2013-04-01T23:59:59.000Z

363

direct_deposit_111609  

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

PROTECT YOUR BANKING INFORMATION: PROTECT YOUR BANKING INFORMATION: DO NOT complete this form until you are ready to submit it to the Payroll Department. DIRECT DEPOSIT REQUEST Directions: 1. Provide required information neatly, legibly; 2. If Checking Account Direct Deposit, include a voided check. a. DO NOT submit a deposit slip! 3. If Savings Account Direct Deposit, include a copy of savings card. 4. Sign this form; 5. Inter-office mail it to Craft Payroll at "P238." DIRECT DEPOSITION AUTHORIZATION I hereby authorize Los Alamos National Laboratory, hereinafter called The Laboratory, to initiate credit entries and, if necessary, debit entries and adjustments for any credit entries in error to my account listed on this form. If deposit is for:

364

National Uranium Resource Evaluation: Cortez quadrangle, Colorado and Utah  

SciTech Connect (OSTI)

Six stratigraphic units are recognized as favorable for the occurrence of uranium deposits that meet the minimum size and grade requirements of the U.S. Department of Energy in the Cortez 1/sup 0/ x 2/sup 0/ Quadrangle, Utah and Colorado. These units include the Jurassic Salt Wash, Recapture, and Brushy Basin Members of the Morrison Formation and the Entrada Sandstone, the Late Triassic Chinle Formation, and the Permian Cutler Formation. Four areas are judged favorable for the Morrison members which include the Slick Rock, Montezuma Canyon, Cottonwood Wash and Hatch districts. The criteria used to determine favorability include the presence of the following (1) fluvial sandstone beds deposited by low-energy streams; (2) actively moving major and minor structures such as the Paradox Basin and the many folds within it; (3) paleostream transport directions approximately perpendicular to the trend of many of the paleofolds; (4) presence of favorable gray lacustrine mudstone beds; and (5) known uranium occurrences associated with the favorable gray mudstones. Two areas of favorability are recognized for the Chinle Formation. These areas include the Abajo Mountain and Aneth-Ute Mountain areas. The criteria used to determine favorability include the sandstone-to-mudstone ratio for the Chinle Formation and the geographic distribution of the Petrified Forest Member of the Chinle Formation. Two favorable areas are recognized for the Cutler Formation. Both of these areas are along the northern border of the quadrangle between the Abajo Mountains and the Dolores River Canyon area. Two areas are judged favorable for the Entrada Sandstone. One area is in the northeast corner of the quadrangle in the Placerville district and the second is along the eastern border of the quadrangle on the southeast flank of the La Plata Mountains.

Campbell, J A

1982-09-01T23:59:59.000Z

365

FAQ 3-What are the common forms of uranium?  

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

366

Methods for nondestructive assay holdup measurements in shutdown uranium enrichment facilities  

SciTech Connect (OSTI)

Measurement surveys of uranium holdup using nondestructive assay (NDA) techniques are being conducted for shutdown gaseous diffusion facilities at the Oak Ridge K-25 Site (formerly the Oak Ridge Gaseous Diffusion Plant). When in operation, these facilities processed UF{sub 6} with enrichments ranging from 0.2 to 93 wt % {sup 235}U. Following final shutdown of all process facilities, NDA surveys were initiated to provide process holdup data for the planning and implementation of decontamination and decommissioning activities. A three-step process is used to locate and quantify deposits: (1) high-resolution gamma-ray measurements are performed to generally define the relative abundances of radioisotopes present, (2) sizable deposits are identified using gamma-ray scanning methods, and (3) the deposits are quantified using neutron measurement methods. Following initial quantitative measurements, deposit sizes are calculated; high-resolution gamma-ray measurements are then performed on the items containing large deposits. The quantitative estimates for the large deposits are refined on the basis of these measurements. Facility management is using the results of the survey to support a variety of activities including isolation and removal of large deposits; performing health, safety, and environmental analyses; and improving facility nuclear material control and accountability records. 3 refs., 1 tab.

Hagenauer, R.C.; Mayer, R.L. II.

1991-09-01T23:59:59.000Z

367

Spores from Devonian Deposits  

Science Journals Connector (OSTI)

... IN a well-illustrated paper on "Spores from Devonian Deposits, Mimerdalen, Spitsbergen" (Norsk. Polarinstitutt Skrifter, No. 132, 1964), Jorunn Os Vigran deals with the dispersed ...

1965-06-05T23:59:59.000Z

368

EMSL - ion deposition  

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

deposition en Physical Properties of Ambient and Laboratory-Generated Secondary Organic Aerosol. http:www.emsl.pnl.govemslwebpublicationsphysical-properties-ambient-and-labora...

369

EMSL - Deposition and Microfabrication  

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

ion beam for nanolithography and deposition and manipulation of structures at the nano scale* Microfabrication suite for designing and etching complex patterns into varied...

370

Rock-water interaction and evolution of sulphide ores in the late Archaean Chitradurga greenstone belt of southern India  

Science Journals Connector (OSTI)

Sulphide ore mineralization developed in proximity to iron formations in a cyclic volcano-sedimentary sequence that forms the offshore part of the late Archaean intracratonic basin of the Chitradurga greenston...

H. N. Bhattacharyay; A. D. Mukherjee; P. K. Bhattacharyay

1993-11-01T23:59:59.000Z

371

Application of Geothermal Energy to Mineral Processing: Cyanide Heap-Leaching of Low-Grade Gold Ore  

Science Journals Connector (OSTI)

The advent of cyanide heap-leaching for low-grade gold and silver ores has resulted in an unprecedented increase in the output of mines throughout the world. This simple and economical process entails open-pit mi...

Thomas Flynn; Dennis Trexler…

1995-01-01T23:59:59.000Z

372

Influence of the batch's coke-ore ratio and distribution on the porosity of the melting zone  

SciTech Connect (OSTI)

The variation in gas permeability in the melting zone is considered as a function of the height and configuration of the coke packing and the ore component of the batch.

V.P. Tarasov; L.V. Bykov; P.V. Tarasov [Priazovsk State Technical University, Mariupol (Ukraine)

2008-09-15T23:59:59.000Z

373

Investigation of different manganese ores as oxygen carriers in chemical-looping combustion (CLC) for solid fuels  

Science Journals Connector (OSTI)

Abstract The chemical-looping combustion (CLC) process is a novel solution for efficient combustion with direct capture of carbon dioxide. The process uses a metal oxide as an oxygen carrier to transfer oxygen from an air to a fuel reactor, where the fuel reacts with the solid oxygen carrier. In this work, six different manganese ores are investigated as oxygen carriers for CLC application. The chemical-looping characteristics of the oxygen carriers were evaluated in a laboratory-scale fluidized-bed reactor in the temperature range of 900–970 °C during alternating reducing and oxidizing conditions. Three of the manganese ores showed a small oxygen release in inert environment between 850 and 950 °C. During reactivity tests, the gas yield with methane increased with the temperature and complete conversion of 50% CO in H2 was obtained for all of the ores. The rates of char gasification of two fuels, namely Mexican petroleum coke and Swedish wood char, were compared for the different manganese ores at 970 °C and with 50% H2O in N2 as fluidizing gas. Ilmenite and a manufactured Mn-oxide oxygen carrier consisting of Mn3O4 and MgO-stabilized ZrO2 as support were also included for comparison. The char gasification rate and the gas conversion were higher with the manganese ores and the Mn-oxide oxygen carrier compared to ilmenite. However, the higher reactivity of the manganese ores with H2 and the ensuing decrease in H2 inhibition for manganese ores is not sufficient to explain their higher rate of char gasification. Surface analysis of partially gasified petcoke particles in the presence of manganese ores showed formation of cavities and channels as well as a uniform distribution of potassium and sodium elements. The rate of char gasification also increased with the concentration of potassium and sodium impurities in the manganese ores. Thus the results suggest that the increased rate of char conversion for manganese ores is due to alkali-catalyzed steam gasification. The increase in rate of char gasification, in combination with potentially low costs of these materials suggests that manganese ores could be interesting materials for CLC with solid fuels.

Mehdi Arjmand; Henrik Leion; Tobias Mattisson; Anders Lyngfelt

2014-01-01T23:59:59.000Z

374

Demand side management of a run-of-mine ore milling circuit  

Science Journals Connector (OSTI)

Increasing electricity costs coupled with lower prices for some metals such as platinum group metals require a reevaluation of the operation of grinding processes. Demand side management (DSM) has received increasing attention in the field of industrial control as an opportunity to reduce operating costs. DSM through grinding mill power load shifting is presented in this paper using model predictive control and a real-time optimizer. Simulation results indicate that mill power load shifting can potentially achieve cost reductions of $9.90 per kg of unrefined product when applied to a run-of-mine (ROM) ore milling circuit processing platinum bearing ore. DSM is however still not economically feasible when there is a demand to continuously run the milling circuit at maximum throughput.

B. Matthews; I.K. Craig

2013-01-01T23:59:59.000Z

375

Chemical Looping Combustion of Biomass/Coal with Natural Iron Ore as Oxygen Carrier in a Continuous Reactor  

Science Journals Connector (OSTI)

Chemical Looping Combustion of Biomass/Coal with Natural Iron Ore as Oxygen Carrier in a Continuous Reactor ... Chemical looping combustion (CLC) is a new innovative technology with inherent separation of CO2 without energy penalty. ... Experiments on chemical looping combustion of biomass/coal were conducted in a 1 kWth continuous reactor, and an Australia iron ore was selected as oxygen carrier. ...

Haiming Gu; Laihong Shen; Jun Xiao; Siwen Zhang; Tao Song

2010-12-21T23:59:59.000Z

376

Kinetics of Iron Ore Reduction by Methane for Chemical Looping Combustion  

Science Journals Connector (OSTI)

Kinetics of Iron Ore Reduction by Methane for Chemical Looping Combustion ... Chemical-looping combustion (CLC) is a promising concept that can be used in power generation, which integrates power production and CO2 capture. ... With this in mind, chemical-looping combustion (CLC) is a promising concept that can be used in power generation, with the inherent capture of CO2 during the process cycle. ...

Somaye Nasr; Kevin P. Plucknett

2014-01-20T23:59:59.000Z

377

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

378

Carbonate Leaching of Uranium from Contaminated Soils  

Science Journals Connector (OSTI)

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

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

1997-09-30T23:59:59.000Z

379

Statistical data of the uranium industry  

SciTech Connect (OSTI)

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

none,

1983-01-01T23:59:59.000Z

380

Capstone Depleted Uranium Aerosols: Generation and Characterization  

SciTech Connect (OSTI)

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

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

2004-10-19T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

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

382

Interactions of Jet Fuels with Nitrile O-Rings: Petroleum-Derived versus Synthetic Fuels  

SciTech Connect (OSTI)

A transition from petroleum-derived jet fuels to blends with Fischer-Tropsch (F-T) fuels, and ultimately fully synthetic hydro-isomerized F-T fuels has raised concern about the fate of plasticizers in nitrile-butadiene rubber a-rings that are contacted by the fuels as this transition occurs. The partitioning of plasticizers and fuel molecules between nitrile a-rings and petroleum-derived, synthetic, and additized-synthetic jet fuels has been measured. Thermal desorption of o-rings soaked in the various jet fuels followed by gas chromatographic analysis with a mass spectrometric detector showed many of the plasticizer and stabilizer compounds were removed from the o-rings regardless of the contact fuel. Fuel molecules were observed to migrate into the o-rings for the petroleum-derived fuel as did both the fuel and additive for a synthetic F-T jet fuel additized with benzyl alcohol, but less for the unadditized synthetic fuel. The specific compounds or classes of compounds involved in the partitioning were identified and a semiquantitative comparison of relative partitioning of the compounds of interest was made. The results provide another step forward in improving the confidence level of using additized, fully synthetic jet fuel in the place of petroleum-derived fuel.

Gormley, R.J.; Link, D.D.; Baltrus, J.P.; Zandhuis, P.H.

2009-01-01T23:59:59.000Z

383

Use of manganese ore in chemical-looping combustion (CLC)—Effect on steam gasification  

Science Journals Connector (OSTI)

The chemical-looping combustion (CLC) process is a novel solution for efficient combustion with direct separation of carbon dioxide. The process uses a metal oxide as an oxygen carrier to transfer oxygen from an air to a fuel reactor, where the fuel reacts with the solid oxygen carrier. When solid fuel is used in CLC, the char needs to be gasified by e.g. steam to form H2 and CO that can be subsequently oxidized to H2O and CO2 by the oxygen carrier. In this work, the influence of the oxygen carrier on the rate of steam gasification is studied, by comparing the conversion of petcoke in the presence of manganese ore to that of ilmenite. The experiments were carried out in a fluidized-bed reactor at 970 °C using a fluidization gas of 50% steam in nitrogen. The manganese ore shows an increase by a factor five in the rate of steam gasification of char as compared to ilmenite. The dramatic increase in rate of steam gasification, in combination with potentially low costs of this material suggests that manganese ore could be an interesting material for CLC with solid fuels.

Mehdi Arjmand; Henrik Leion; Anders Lyngfelt; Tobias Mattisson

2012-01-01T23:59:59.000Z

384

Geochemical Fingerprinting of Coltan Ores by Machine Learning on Uneven Datasets  

SciTech Connect (OSTI)

Two modern machine learning techniques, Linear Programming Boosting (LPBoost) and Support Vector Machines (SVMs), are introduced and applied to a geochemical dataset of niobium-tantalum ('coltan') ores from Central Africa to demonstrate how such information may be used to distinguish ore provenance, i.e., place of origin. The compositional data used include uni- and multivariate outliers and elemental distributions are not described by parametric frequency distribution functions. The 'soft margin' techniques of LPBoost and SVMs can be applied to such data. Optimization of their learning parameters results in an average accuracy of up to c. 92%, if spot measurements are assessed to estimate the provenance of ore samples originating from two geographically defined source areas. A parameterized performance measure, together with common methods for its optimization, was evaluated to account for the presence of uneven datasets. Optimization of the classification function threshold improves the performance, as class importance is shifted towards one of those classes. For this dataset, the average performance of the SVMs is significantly better compared to that of LPBoost.

Savu-Krohn, Christian, E-mail: christian.savu-krohn@unileoben.ac.at; Rantitsch, Gerd, E-mail: gerd.rantitsch@unileoben.ac.at [Montanuniversitaet Leoben, Department of Applied Geosciences and Geophysics (Austria); Auer, Peter, E-mail: auer@unileoben.ac.at [Chair for Information Technology, Montanuniversitaet Leoben (Austria); Melcher, Frank, E-mail: frank.melcher@bgr.de; Graupner, Torsten, E-mail: torsten.graupner@bgr.de [Federal Institute for Geosciences and Natural Resources (Germany)

2011-09-15T23:59:59.000Z

385

Purification of trona ores by conditioning with an oil-in-water emulsion  

DOE Patents [OSTI]

The present invention is a trona concentrate and a process for floating gangue material from trona ore that comprises forming an emulsion, conditioning the trona ore at a high solids content in a saturated trona suspension, and then floating and removing the gangue material. The process for separating trona from gangue materials in trona ore can include emulsifying an oil in an aqueous solution to form an oil-in-water emulsion. A saturated trona suspension having a high solids content can also be formed having trona of a desired particle size. The undissolved trona in the saturated suspension can be conditioned by mixing the saturated suspension and the oil-in-water emulsion to form a conditioning solid suspension of trona and gangue material. A gas can be injected through the conditioning solid suspension to float the gangue material. Thus, the floated gangue material can be readily separated from the trona to form a purified trona concentrate without requirements of additional heat or other expensive processing steps.

Miller, J. D. (Salt Lake City, UT); Wang, Xuming (Salt Lake City, UT); Li, Minhua (Salt Lake City, UT)

2009-04-14T23:59:59.000Z

386

Uranium contamination of the Aral Sea  

Science Journals Connector (OSTI)

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

Jana Friedrich

2009-01-01T23:59:59.000Z

387

Synthesis of uranium nitride and uranium carbide powder by carbothermic reduction  

SciTech Connect (OSTI)

Uranium nitride and uranium carbide are being considered as high burnup fuels in next generation nuclear reactors and accelerated driven systems for the transmutation of nuclear waste. The same characteristics that make nitrides and carbides candidates for these applications (i.e. favorable thermal properties, mutual solubility of nitrides, etc.), also make these compositions candidate fuels for space nuclear reactors. In this paper, we discuss the synthesis and characterization of depleted uranium nitride and carbide for a space nuclear reactor program. Importantly, this project emphasized that to synthesize high quality uranium nitride and carbide, it is necessary to understand the exact stoichiometry of the oxide feedstock. (authors)

Dunwoody, J.T.; Stanek, C.R.; McClellan, K.J.; Voit, S.L.; Volz, H.M. [Los Alamos National Laboratory, Los Alamos, New Mexico (United States); Hickman, R.R. [NASA Marshall Space Flight Center, Huntsville, Alabama (United States)

2007-07-01T23:59:59.000Z

388

Crystal Chemistry of Early Actinides (Thorium, Uranium, and Neptunium) and Uranium Mesoporous Materials.  

E-Print Network [OSTI]

??Despite their considerable global importance, the structural chemistry of actinides remains understudied. Thorium and uranium fuel cycles are used in commercial nuclear reactors in India… (more)

Sigmon, Ginger E.

2010-01-01T23:59:59.000Z

389

Prokaryotic microorganisms in uranium mining waste piles and their interactions with uranium and other heavy metals.  

E-Print Network [OSTI]

??The influence of uranyl and sodium nitrate under aerobic and anaerobic conditions on the microbial community structure of a soil sample from the uranium mining… (more)

Geißler, Andrea

2007-01-01T23:59:59.000Z

390

Solution deposition assembly  

DOE Patents [OSTI]

Methods and devices are provided for improved deposition systems. In one embodiment of the present invention, a deposition system is provided for use with a solution and a substrate. The system comprises of a solution deposition apparatus; at least one heating chamber, at least one assembly for holding a solution over the substrate; and a substrate curling apparatus for curling at least one edge of the substrate to define a zone capable of containing a volume of the solution over the substrate. In another embodiment of the present invention, a deposition system for use with a substrate, the system comprising a solution deposition apparatus; at heating chamber; and at least assembly for holding solution over the substrate to allow for a depth of at least about 0.5 microns to 10 mm.

Roussillon, Yann; Scholz, Jeremy H; Shelton, Addison; Green, Geoff T; Utthachoo, Piyaphant

2014-01-21T23:59:59.000Z

391

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.

392

Uranium Management and Policy | Department of Energy  

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

Test Program, and reporting annually to Congress on the impact of the U.S.-Russia Highly Enriched Uranium Purchase Agreement on the U.S. nuclear fuel industry. NE-54's...

393

Depleted uranium disposition study -- Supplement, Revision 1  

SciTech Connect (OSTI)

The Department of Energy Office of Weapons and Materials Planning has requested a supplemental study to update the recent Depleted Uranium Disposition report. This supplemental study addresses new disposition alternatives and changes in status.

Becker, G.W.

1993-11-01T23:59:59.000Z

394

Method of recovering uranium from aqueous solution  

SciTech Connect (OSTI)

Anion exchange resin derived from insoluble crosslinked polymers of vinyl benzyl chloride which are prepared by polymerizing vinyl benzyl chloride and a crosslinking monomer are particularly suitable in the treatment of uranium bearing leach liquors.

Albright, R.L.

1980-01-22T23:59:59.000Z

395

Ex Parte Communications- Uranium Producers of America  

Broader source: Energy.gov [DOE]

On Thursday, February 12, 2015, representatives from the Uranium  Producers  of America (UPA) met with the Department of Energy (DOE) officials to discuss the management of the federal excess...

396

The Uranium Resource: A Comparative Analysis  

SciTech Connect (OSTI)

An analogy was drawn between uranium and thirty five minerals for which the USGS maintains extensive records. The USGS mineral price data, which extends from 1900 to the present, was used to create a simple model describing long term price evolution. Making the assumption that the price of uranium, a geologically unexceptional mineral, will evolve in a manner similar to that of the USGS minerals, the model was used to project its price trend for this century. Based upon the precedent set by the USGS data, there is an 80% likelihood that the price of uranium will decline. Moreover, the most likely scenario would see the equilibrium price of uranium decline by about 40% by mid-century. (authors)

Schneider, Erich A. [The University of Texas at Austin, 1 University Station C2200, Austin, TX, 78712 (United States); Sailor, William C. [Los Alamos National Laboratory, PO Box 1663, Los Alamos, NM, 87545 (United States)

2007-07-01T23:59:59.000Z

397

Uranium Leasing Program | Department of Energy  

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

» 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

398

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

399

Copyright 2007, SEPM (Society for Sedimentary Geology) 0883-1351/07/0022-0577/$3.00 PALAIOS, 2007, v. 22, p. 577582  

E-Print Network [OSTI]

IMPLICATIONS OF URANIUM ROLL FRONTS PENNILYN HIGGINS* University of Wyoming Department of GeologyCopyright 2007, SEPM (Society for Sedimentary Geology) 0883-1351/07/0022-0577/$3.00 PALAIOS, 2007 deep structural basins containing both abundant vertebrate fossils and uranium-ore deposits in the form

Higgins, Pennilyn

400

Depleted uranium: A DOE management guide  

SciTech Connect (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

Note: This page contains sample records for the topic "uranium ore deposits" 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

The ultimate disposition of depleted uranium  

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

402

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.

403

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)

404

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

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

405

Perspectives on Deposition Velocity  

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

Deposition Deposition Velocity ... Going down the rabbit hole to explain that sinking feeling Brian DiNunno, Ph.D. Project Enhancement Corporation June 6 th , 2012 Discussion Framework  Development of the HSS Deposition Velocity Safety Bulletin  Broader discussion of appropriate conservatism within dispersion modeling and DOE-STD-3009 DOE-STD-3009 Dose Comparison "General discussion is provided for source term calculation and dose estimation, as well as prescriptive guidance for the latter. The intent is that calculations be based on reasonably conservative estimates of the various input parameters." - DOE-STD-3009, Appendix A.3 DOE-STD-3009 Dispersion

406

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

SciTech Connect (OSTI)

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

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2000-07-01T23:59:59.000Z

407

Doses and risks from uranium are not increased significantly by interactions with natural background photon radiation  

Science Journals Connector (OSTI)

......higher fraction of depleted uranium (DU). These...in mandibular cancer patients following...Reprocessed uranium exposure and lung cancer risk. Health...and risks from uranium are not increased...The impact of depleted uranium (DU......

R. J. Tanner; J. S. Eakins; J. T. M. Jansen; J. D. Harrison

2012-08-01T23:59:59.000Z

408

Sizing particles of natural uranium and nuclear fuels using poly-allyl-diglycol carbonate autoradiography  

Science Journals Connector (OSTI)

......particles of natural uranium and nuclear fuels...low enriched, depleted and natural uranium and also aged...committed doses and cancer risks(4...Bristol, UK, sized uranium fragments found...nuclear fuels of depleted uranium (depUO2......

G. Hegyi; R. B. Richardson

2008-07-01T23:59:59.000Z

409

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

SciTech Connect (OSTI)

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 µg 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

410

EMSL: Capabilities: Deposition and Microfabrication  

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

Deposition and Microfabrication Deposition and Microfabrication Additional Information Meet the Deposition and Microfabrication Experts Related EMSL User Projects Deposition and Microfabrication Tools are Applied to all Science Themes Deposition and Microfabrication brochure Designed to augment research important to a variety of disciplines, EMSL's Deposition and Microfabrication Capability tackles serious scientific challenges from a microscopic perspective. From deposition instruments that emphasize oxide films and interfaces to a state-of-the-art microfabrication suite, EMSL has equipment to tailor surfaces, as diverse as single-crystal thin films or nanostructures, or create the microenvironments needed for direct experimentation at micron scales. Users benefit from coupling deposition and microfabrication applications

411

Electrophoretic deposition of biomaterials  

Science Journals Connector (OSTI)

...Wilson 2003). The use of citric acid as a dispersant allowed the deposition of thin...poly(lactic-co-glycolic acid) (PLGA) nanoparticles embedded...stent for local drug delivery. Polyacrylic acid was used as surfactant because...

2010-01-01T23:59:59.000Z

412

Zinc–germanium ores of the Tres Marias Mine, Chihuahua, Mexico  

Science Journals Connector (OSTI)

The Tres Marias carbonate-hosted Zn–Ge deposit in Chihuahua, Mexico contains sphalerite with the highest average...

Bernhardt Saini-Eidukat; Frank Melcher; Jerzy Lodziak

2009-04-01T23:59:59.000Z

413

Radioisotope Thermoelectric Generator Package O-Ring Seal Material Validation Testing  

SciTech Connect (OSTI)

The Radioisotope Thermoelectric Generator Package O-Ring Seal Material Validation Test was conducted to validate the use of the Butyl material as a primary seal throughout the required temperature range. Three tests were performed at (1) 233 K ({minus}40 {degrees}F), (2) a specified operating temperature, and (3) 244 K ({minus}20 {degrees}F) before returning to room temperature. Helium leak tests were performed at each test point to determine seal performance. The two major test objectives were to establish that butyl rubber material would maintain its integrity under various conditions and within specified parameters and to evaluate changes in material properties.

Adkins, H.E.; Ferrell, P.C.; Knight, R.C.

1994-09-30T23:59:59.000Z

414

A REAL TIME COAL CONTENT ORE GRADE (C2OG) SENSOR  

SciTech Connect (OSTI)

This eighth quarterly technical report discusses the progress made on a machine vision technique for determining coal content and preparations for Year-3 system deployment. Classification maps for coal have been generated and shown to two coal-mining executives. An application for licensing high-speed hyperspectral data analysis software from the Naval Research Laboratory (NRL) has been made. Both Western Energy and Stillwater Mining Company have offered platforms for Year-3 deployment. Barretts Minerals has expressed renewed interest in using Resonon's machine vision system for identifying dolomite in their talc ore and have agreed to provide samples to the Montana Tech team.

Dr. Rand Swanson

2003-07-21T23:59:59.000Z

415

A REAL TIME COAL CONTENT ORE GRADE (C2OG) SENSOR  

SciTech Connect (OSTI)

This tenth quarterly technical report discusses the progress made on a machine vision technique for ore grading based on hyperspectral imaging. A graduate student at Montana Tech has successfully defended her thesis related to this project. Arrangements with Stillwater Mining Company to deploy a machine vision system in their core room have been completed. Designs for they system that will be installed next quarter have been drawn and parts are being machined. Presentations on the spectral imaging system developed during this effort have been made to Stillwater Mining Company and at a remote sensing symposium at Montana State University.

Rand Swanson

2004-01-23T23:59:59.000Z

416

Uranium roll front study in the upper Jackson group, Atascosa County, Texas  

E-Print Network [OSTI]

(Eargle, et al. , 1975). Alkaline groundwaters dissolved uranium from these source rocks during periods of dry climate weathering and transported it through porous rock uni ts to the depositional site where i t encountered a reducing environment.... Randall for their guidance and ass1stance dur1ng this project. Mr. W1111am Kalich also deserves thanks for h1s photographic expert1se dur1ng final analys1s at the m1ne site. Special thanks are due Mr. Ernest Ledger for h1s school on microphotography...

Miller, Michael Eugene

2012-06-07T23:59:59.000Z

417

DOE Uranium Leasing Program - Lease Tract Metrics  

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

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

418

DOE Announces Policy for Managing Excess Uranium Inventory | Department of  

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

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

419

NNSA Authorizes Start-Up of Highly Enriched Uranium Materials...  

National Nuclear Security Administration (NNSA)

Releases NNSA Authorizes Start-Up of Highly Enriched Uranium ... NNSA Authorizes Start-Up of Highly Enriched Uranium Materials Facility at Y-12 applicationmsword icon R-10-01...

420

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

Science Journals Connector (OSTI)

...transmission of genetic damage by depleted uranium and tungsten alloy Alexandra Miller...The radioactive heavy metal, depleted uranium (DU), an alpha-particle emitter...fragments will affect the long-term health of offspring conceived by these...

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

2006-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "uranium ore deposits" 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

Depleted uranium internal contamination: Carcinogenesis and leukemogenesis in vivo  

Science Journals Connector (OSTI)

...Association for Cancer Research 1 May 2005...Proc Amer Assoc Cancer Res, Volume 46, 2005 Depleted uranium internal contamination...Proc Amer Assoc Cancer Res, Volume 46, 2005] 2080 Depleted uranium is a heavy metal...

Alexandra C. Miller; Mike Stewart; Rafael Rivas; Robert Merlot; and Paul Lison

2005-05-01T23:59:59.000Z

422

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

Science Journals Connector (OSTI)

...Association for Cancer Research 15 April...Proc Amer Assoc Cancer Res, Volume 47, 2006 Depleted uranium - induced malignant...Proc Amer Assoc Cancer Res, Volume 47, 2006] 5215 Depleted uranium (DU) has been...

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

2006-04-15T23:59:59.000Z

423

Depleted uranium mobility and fractionation in contaminated soil (Southern Serbia)  

Science Journals Connector (OSTI)

During the Balkan conflict in 1999, soil in contaminated areas was enriched in depleted uranium (DU) isotopic signature, relative to the in-situ natural uranium present. After the military activities, most...

Mirjana B. Radenkovi?; Svjetlana A. Cupa?…

2008-01-01T23:59:59.000Z

424

Depleted uranium internal contamination: Carcinogenesis and leukemogenesis in vivo  

Science Journals Connector (OSTI)

...Abstract 3464: Epigenetic mechanism is involved in depleted uranium-induced transformation in human lung epithelial...Wise 1 1Univ. of Southern Maine, Portland, ME. Depleted uranium (DU) is commonly used in military applications...

Alexandra C. Miller; Mike Stewart; Rafael Rivas; Robert Merlot; and Paul Lison

2005-05-01T23:59:59.000Z

425

Numerical simulation for formed projectile of depleted uranium alloy  

Science Journals Connector (OSTI)

The numerical simulation for forming projectile of depleted uranium alloy with the SPH (Smooth Particle Hydrodynamic ... . To describe the deformed behaviors of the depleted uranium alloy under high pressure and ...

Song Shun-cheng; Gao Ping; Cai Hong-nian

2003-09-01T23:59:59.000Z

426

Alpha spectrometric characterization of process-related particle size distributions from active particle sampling at the Los Alamos National Laboratory uranium foundry  

SciTech Connect (OSTI)

Uranium particles within the respirable size range pose a significant hazard to the health and safety of workers. Significant differences in the deposition and incorporation patterns of aerosols within the respirable range can be identified and integrated into sophisticated health physics models. Data characterizing the uranium particle size distribution resulting from specific foundry-related processes are needed. Using personal air sampling cascade impactors, particles collected from several foundry processes were sorted by activity median aerodynamic diameter onto various Marple substrates. After an initial gravimetric assessment of each impactor stage, the substrates were analyzed by alpha spectrometry to determine the uranium content of each stage. Alpha spectrometry provides rapid nondestructive isotopic data that can distinguish process uranium from natural sources and the degree of uranium contribution to the total accumulated particle load. In addition, the particle size bins utilized by the impactors provide adequate resolution to determine if a process particle size distribution is: lognormal, bimodal, or trimodal. Data on process uranium particle size values and distributions facilitate the development of more sophisticated and accurate models for internal dosimetry, resulting in an improved understanding of foundry worker health and safety.

Plionis, Alexander A [Los Alamos National Laboratory; Peterson, Dominic S [Los Alamos National Laboratory; Tandon, Lav [Los Alamos National Laboratory; Lamont, Stephen P [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

427

3rd Quarter 2014 Domestic Uranium Production Report  

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

of ore per day)",2013,"1st quarter 2014","2nd quarter 2014","3rd quarter 2014" "EFR White Mesa LLC","White Mesa Mill","San Juan, Utah",2000,"Operating-Processing Alternate...

428

Retrieval of buried depleted uranium from the T-1 trench  

SciTech Connect (OSTI)

The Trench 1 remediation project will be conducted this year to retrieve depleted uranium and other associated materials from a trench at Rocky Flats Environmental Technology Site. The excavated materials will be segregated and stabilized for shipment. The depleted uranium will be treated at an offsite facility which utilizes a novel approach for waste minimization and disposal through utilization of a combination of uranium recycling and volume efficient uranium stabilization.

Burmeister, M. [Rocky Mountain Remediation Services, Golden, CO (United States); Castaneda, N. [Dept. of Energy, Golden, CO (United States). Rocky Flats Field Office; Greengard, T. [Kaiser-Hill Co., Golden, CO (United States)]|[Science Applications International Corp. (United States); Hull, C. [S.M. Stoller Corp., Boulder, CO (United States); Barbour, D.; Quapp, W.J. [Starmet Corp. (United States)

1998-07-01T23:59:59.000Z

429

Uranium Sequestration via Phosphate Infiltration/Injection Test...  

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

- Immediate sequestration - Stable mineral form * Apatite formation - Sorbent for uranium - Conversion to autunite 5 Advantages of Phosphate Technology * Direct treatment...

430

Vacuum arc deposition devices  

SciTech Connect (OSTI)

The vacuum arc is a high-current, low-voltage electrical discharge which produces a plasma consisting of vaporized and ionized electrode material. In the most common cathodic arc deposition systems, the arc concentrates at minute cathode spots on the cathode surface and the plasma is emitted as a hypersonic jet, with some degree of contamination by molten droplets [known as macroparticles (MPs)] of the cathode material. In vacuum arc deposition systems, the location and motion of the cathode spots are confined to desired surfaces by an applied magnetic field and shields around undesired surfaces. Substrates are mounted on a holder so that they intercept some portion of the plasma jet. The substrate often provides for negative bias to control the energy of depositing ions and heating or cooling to control the substrate temperature. In some systems, a magnetic field is used to guide the plasma around an obstacle which blocks the MPs. These elements are integrated with a deposition chamber, cooling, vacuum gauges and pumps, and power supplies to produce a vacuum arc deposition system.

Boxman, R.L.; Zhitomirsky, V.N. [Electrical Discharge and Plasma Laboratory, Faculty of Engineering, Tel Aviv University, P.O. Box 39040, Tel Aviv 69978 (Israel)

2006-02-15T23:59:59.000Z

431

Instrument Series: Deposition and Microfabrication  

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

Deposition and Microfabrication Deposition and Microfabrication Sputter Deposition System Only available at EMSL, the Discovery ® Deposition System has been customized to be a fully automated multi-functional "hybrid" instrument with several modes for thin film processing, including multi-target sputtering, effusion cell deposition, electron beam deposition, and in-situ reflection high-energy electron diffraction (RHEED) materials characterization. Unlike most systems, the Discovery ® Deposition System's unique configuration offers operational flexibility, efficiency, and control, allowing a range of applications and materials to be processed simultaneously. Because it is software controlled, users can provide their own "recipes" and have a complete log of what happens throughout the

432

Depleted uranium plasma reduction system study  

SciTech Connect (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

433

Depleted uranium hexafluoride: Waste or resource?  

SciTech Connect (OSTI)

the US Department of Energy is evaluating technologies for the storage, disposal, or re-use of depleted uranium hexafluoride (UF{sub 6}). This paper discusses the following options, and provides a technology assessment for each one: (1) conversion to UO{sub 2} for use as mixed oxide duel, (2) conversion to UO{sub 2} to make DUCRETE for a multi-purpose storage container, (3) conversion to depleted uranium metal for use as shielding, (4) conversion to uranium carbide for use as high-temperature gas-cooled reactor (HTGR) fuel. In addition, conversion to U{sub 3}O{sub 8} as an option for long-term storage is discussed.

Schwertz, N.; Zoller, J.; Rosen, R.; Patton, S. [Lawrence Livermore National Lab., CA (United States); Bradley, C. [USDOE Office of Nuclear Energy, Science, Technology, Washington, DC (United States); Murray, A. [SAIC (United States)

1995-07-01T23:59:59.000Z

434

Method for fluorination of uranium oxide  

DOE Patents [OSTI]

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

435

Modeling Uranium-Proton Ion Exchange in Biosorption  

E-Print Network [OSTI]

threatening heavy metals because of its high toxicity and some radioactivity. Excessive amounts of uranium seaweed biomass was used to remove the heavy metal uranium from the aqueous solution. Uranium biosorption the heavy metal uptake performance of different biosorbents.LangmuirandFreundlichmodelsoftengenerally fit

Volesky, Bohumil

436

Bioremediation of Uranium Plumes with Nano-scale  

E-Print Network [OSTI]

(IV) (UO2[s], uraninite) Anthropogenic · Release of mill tailings during uranium mining - MobilizationBioremediation 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

Fay, Noah

437

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 Occurring Radioactive Materials from Uranium Mining, Volume I: Mining and Reclamation Background (Revised

438

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"

439

Caulobacter crescentus as a Whole-Cell Uranium Biosensor  

Science Journals Connector (OSTI)

...results, we constructed a uranium reporter that places...strongly upregulated under uranium stress conditions. MATERIALS...Pb(NO3)2], and depleted uranyl nitrate [UO2...and by Damon Runyon Cancer Research Foundation fellowship...specificity for chelated uranium(VI): isolation and...

Nathan J. Hillson; Ping Hu; Gary L. Andersen; Lucy Shapiro

2007-09-28T23:59:59.000Z

440

Estimating terrestrial uranium and thorium by antineutrino flux measurements  

E-Print Network [OSTI]

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

Mcdonough, William F.

Note: This page contains sample records for the topic "uranium ore deposits" 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

Cathodic Arc Plasma Deposition  

Office of Scientific and Technical Information (OSTI)

Cathodic Arc Plasma Deposition Cathodic Arc Plasma Deposition André Anders Lawrence Berkeley National Laboratory, University of California, 1 Cyclotron Road, Mailstop 53, Berkeley, California 94720 aanders@lbl.gov Abstract Cathodic arc plasma deposition is one of oldest coatings technologies. Over the last two decades it has become the technology of choice for hard, wear resistant coatings on cutting and forming tools, corrosion resistant and decorative coatings on door knobs, shower heads, jewelry, and many other substrates. The history, basic physics of cathodic arc operation, the infamous macroparticle problem and common filter solutions are reviewed. Cathodic arc plasmas stand out due to their high degree of ionization, with important consequences for film nucleation, growth, and efficient utilization of substrate bias. The

442

U. S. forms uranium enrichment corporation  

SciTech Connect (OSTI)

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

443

AGING BEHAVIOR OF VITON O-RING SEALS IN THE 9975 SHIPPING PACKAGE  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is storing plutonium (Pu) materials in the K-Area Materials Storage (KAMS) facility. The Pu materials were packaged according to the DOE-STD-3013 standard and shipped to the SRS in Type B 9975 packages. The robust 9975 shipping package was not designed for long-term product storage, but it is a specified part of the storage configuration and the KAMS facility safety basis credits the 9975 design with containment. Within the 9975 package, nested stainless steel containment vessels are closed with dual O-ring seals based on Viton{reg_sign} GLT or GLT-S fluoroelastomer. The aging behavior of the O-ring compounds is being studied to provide the facility with advanced notice of nonconformance and to develop life prediction models. A combination of field surveillance, leak testing of surrogate fixtures aged at bounding service temperatures, and accelerated-aging methodologies based on compression stress-relaxation and oxygen consumption analysis is being used to evaluate seal performance. A summary of the surveillance program relative to seal aging behavior is presented.

Skidmore, E.; Daugherty, W.; Hoffman, E.; Dunn, K.; Bellamy, S.

2012-01-13T23:59:59.000Z

444

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)

445

Aseismic design criteria for uranium enrichment plants  

SciTech Connect (OSTI)

In this paper technological, economical, and safety issues of aseismic design of uranium enrichment plants are presented. The role of management in the decision making process surrounding these issues is also discussed. The resolution of the issues and the decisions made by management are controlling factors in developing aseismic design criteria for any facility. Based on past experience in developing aseismic design criteria for the GCEP various recommendations are made for future enrichment facilities, and since uranium enrichment plants are members of the nuclear fuel cycle the discussion and recommendations presented herein are applicable to other nonreactor nuclear facilities.

Beavers, J.E.

1980-01-01T23:59:59.000Z

446

Evaporation of Enriched Uranium Solutions Containing Organophosphates  

SciTech Connect (OSTI)

The Savannah River Site has enriched uranium (EU) solution which has been stored for almost 10 years since being purified in the second uranium cycle of the H area solvent extraction process. The preliminary SRTC data, in conjunction with information in the literature, is promising. However, very few experiments have been run, and none of the results have been confirmed with repeat tests. As a result, it is believed that insufficient data exists at this time to warrant Separations making any process or program changes based on the information contained in this report. When this data is confirmed in future testing, recommendations will be presented.

Pierce, R.A.

1999-03-18T23:59:59.000Z

447

Uranium in the Savannah River Site environment  

SciTech Connect (OSTI)

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

448

Uranium in the Savannah River Site environment  

SciTech Connect (OSTI)

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

449

Improving Repository Performance by Using DU Dioxide Fill  

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

DU Dioxide Fill DU Dioxide Fill Improving Repository Performance by Using DU Dioxide Fill Fills may improve repository performance by acting as sacrificial materials, which delay the degradation of SNF uranium dioxide. Because fill and SNF have the same chemical form of uranium (uranium dioxide), the DU dioxide in a repository is the only fill which has the same behavior as that of the SNF. In the natural environment, some uranium ore deposits have remained intact for very long periods of time. The outer parts of the ore deposit degrade while the inner parts of the deposit are protected. The same approach is proposed herein for protecting SNF. The application could use half or more of the DU inventory in the United States. Behavior of Uranium and Potential Behavior of a Waste Package with SNF and Fill

450

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

SciTech Connect (OSTI)

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

Kathren, R.L.

1992-09-01T23:59:59.000Z

451

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

Science Journals Connector (OSTI)

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

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

2010-04-23T23:59:59.000Z

452

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

Science Journals Connector (OSTI)

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

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

2011-09-01T23:59:59.000Z

453

Possibility of nuclear pumped laser experiment using low enriched uranium  

SciTech Connect (OSTI)

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

454

In situ gasification chemical looping combustion of a coal using the binary oxygen carrier natural anhydrite ore and natural iron ore  

Science Journals Connector (OSTI)

Abstract CaSO4 is an attractive oxygen carrier for Chemical–looping combustion (CLC), because of its high oxygen capacity and low price. But the utilization of CaSO4 oxygen carrier suffers the problems of low reactivity, deactivation caused by sulfur loss and the incomplete fuel conversion due to the thermodynamic limitations. To improve the stability and reactivity of CaSO4 oxygen carrier, a small amount of natural iron ore were added in. The kinetic behavior and thermodynamics of the reduction of the binary oxygen carrier by coal under steam atmosphere were investigated. The results show that Fe2O3 improves the performance of coal gasification and the subsequent conversion of coal syngas to CO2 and H2O. Besides, the addition of Fe2O3 reduces the chance of CaSO4 reduction to CaO by coal syngas, and the oxygen transfer capacity of CaSO4 is maintained. The optimal reaction conditions in fuel reactor are shifted from 950 °C without Fe2O3 to 900 °C with 7% Fe2O3. And the decreases in CO, SO2 and H2S environmental factors can be well up to 81.48%, 76.35% and 100%, respectively. Meanwhile, the CO2 concentration in the dry gas products increases from 81.63% up to 95.35%.

Min Zheng; Laihong Shen; Xiaoqiong Feng

2014-01-01T23:59:59.000Z

455

Reassessment of individual dosimetry of long-lived alpha radionuclides of uranium miners through experimental determination of urinary excretion of uranium  

Science Journals Connector (OSTI)

......the occurrence of lung cancers(1). External gamma...been measured in Czech uranium mines since 1960s(2...Measurement of daily urinary uranium excretion in German peacekeeping...potential intakes of depleted uranium(DU). Sci. Total......

I. Malátová; V. Becková; L. Tomásek; M. Slezáková-Marusiaková; J. Hulka

2013-04-01T23:59:59.000Z

456

Content of uranium in urine of uranium miners as a tool for estimation of intakes of long-lived alpha radionuclides  

Science Journals Connector (OSTI)

......238U and 230Th in excreta of uranium mill crushermen. Health Phys. (1983) 45(3...Measurement of daily urinary uranium excretion in German peacekeeping...assess potential intakes of depleted uranium(DU). Sci. Total Environ......

I. Malátová; V. Becková; L. Tomásek; J. Hulka

2011-11-01T23:59:59.000Z

457

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

SciTech Connect (OSTI)

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

NONE

1995-07-05T23:59:59.000Z

458

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

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

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

459

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

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

460

FAQ 8-What is uranium hexafluoride (UF6)?  

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

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461

DOE Releases Excess Uranium Inventory Plan | Department of Energy  

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

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

462

Uranium Processing Facility | Y-12 National Security Complex  

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

463

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

464

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

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

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

465

Excess Uranium Inventory Management Plan | Department of Energy  

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

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

466

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

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

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

467

Uranium Leasing Program Draft Programmatic EIS Issued for Public Comment |  

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

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

468

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

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

469

The multiphoton ionization of uranium hexafluoride  

SciTech Connect (OSTI)

Multiphoton ionization (MPI) time-of-flight mass spectroscopy and photoelectron spectroscopy studies of UF{sub 6} have been conducted using focused light from the Nd:YAG laser fundamental ({lambda}=1064 nm) and its harmonics ({lambda}=532, 355, or 266 nm), as well as other wavelengths provided by a tunable dye laser. The MPI mass spectra are dominated by the singly and multiply charged uranium ions rather than by the UF{sub x}{sup +} fragment ions even at the lowest laser power densities at which signal could be detected. The laser power dependence of U{sup n+} ions signals indicates that saturation can occur for many of the steps required for their ionization. In general, the doubly-charged uranium ion (U{sup 2+}) intensity is much greater than that of the singly-charged uranium ion (U{sup +}). For the case of the tunable dye laser experiments, the U{sup n+} (n = 1- 4) wavelength dependence is relatively unstructured and does not show observable resonance enhancement at known atomic uranium excitation wavelengths. The dominance of the U{sup 2+} ion and the absence or very small intensities of UF{sub x}{sup +} fragments, along with the unsaturated wavelength dependence, indicate that mechanisms may exist other than ionization of bare U atoms after the stepwise photodissociation of F atoms from the parent molecule.

Armstrong, D.P. (Oak Ridge K-25 Site, TN (United States). UEO Enrichment Technical Operations Div.) [Oak Ridge K-25 Site, TN (United States). UEO Enrichment Technical Operations Div.

1992-05-01T23:59:59.000Z

470

U.S. forms uranium enrichment corporation  

Science Journals Connector (OSTI)

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 U.S. Enrichment Corp. (USEC)—both the DOE enrichment ...

RICHARD SELTZER

1993-07-12T23:59:59.000Z

471

URANIUM MILL TAILINGS RADON FLUX CALCULATIONS  

E-Print Network [OSTI]

at the Piñon Ridge Property in western Montrose County, Colorado. The Piñon Ridge Mill includesURANIUM MILL TAILINGS RADON FLUX CALCULATIONS PI�ON RIDGE PROJECT MONTROSE COUNTY, COLORADO Submitted To: Energy Fuels Resources Corporation 44 Union Boulevard, Suite 600 Lakewood, Colorado 80228

472

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

473

Radiological health aspects of uranium milling  

SciTech Connect (OSTI)

This report describes the operation of conventional and unconventional uranium milling processes, the potential for occupational exposure to ionizing radiation at the mill, methods for radiological safety, methods of evaluating occupational radiation exposures, and current government regulations for protecting workers and ensuring that standards for radiation protection are adhered to. In addition, a survey of current radiological health practices is summarized.

Fisher, D.R.; Stoetzel, G.A.

1983-05-01T23:59:59.000Z

474

Physicochemical Characterization of Capstone Depleted Uranium Aerosols II: Particle Size Distributions as a Function of Time  

SciTech Connect (OSTI)

The Capstone Depleted Uranium (DU) Aerosol Study, which generated and characterized aerosols containing depleted uranium from perforation of armored vehicles with large-caliber DU penetrators, incorporated a sampling protocol to evaluated particle size distributions. Aerosol particle size distribution is an important parameter that influences aerosol transport and deposition processes as well as the dosimetry of the inhaled particles. These aerosols were collected on cascade impactor substrates using a pre-established time sequence following the firing event to analyze the uranium concentration and particle size of the aerosols as a function of time. The impactor substrates were analyzed using beta spectrometry, and the derived uranium content of each served as input to the evaluation of particle size distributions. Activity median aerodynamic diameters (AMADs) of the particle size distributions were evaluated using unimodal and bimodal models. The particle size data from the impactor measurements was quite variable. Most size distributions measured in the test based on activity had bimodal size distributions with a small particle size mode in the range of between 0.2 and 1.2 um and a large size mode between 2 and 15 um. In general, the evolution of particle size over time showed an overall decrease of average particle size from AMADs of 5 to 10 um shortly after perforation to around 1 um at the end of the 2-hr sampling period. The AMADs generally decreased over time because of settlin