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Note: This page contains sample records for the topic "uranium isotopic determination" from the National Library of EnergyBeta (NLEBeta).
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1

Uranium isotopic ratio determination in urine using flow-injection ICP-MS: a tool for emergency monitoring  

Science Journals Connector (OSTI)

......Biological monitoring of uranium exposure in south central...determination of low uranium isotopes ratios in small...Carpenter D. O. Depleted uranium contamination by inhalation...implication for human health assessment. Sci. Total......

Maria Luiza D. P. Godoy; Ligia M. Q. C. Julião; José Marcus Godoy

2009-02-01T23:59:59.000Z

2

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

3

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

4

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

5

High-Resolution Triple Resonance Autoionization of Uranium Isotopes  

SciTech Connect (OSTI)

The near-threshold autoionization (AI) spectrum of uranium has been investigated by triple-resonance excitation with single-mode continuous lasers. Spectra were recorded over the first {approx}30 cm-1 above the first ionization limit at a resolution of 3x10-4 cm 1 using intermediate states with different J values (6, 7, 8) to assign AI level total angular momentum JAI = 5 to 9. Resonances with widths ranging from 8 MHz to 30 GHz were observed; the strongest ones have JAI = 9 and widths of {approx} 60 MHz. Hyperfine structures for 235U and isotope shifts for 234,235U have been measured in the two intermediate levels and in the final AI level for the most favorable excitation path. These measurements were performed using aqueous samples containing sub-milligram quantities of uranium at natural isotopic abundances, indicating the potential of this approach for trace isotope ratio determinations.

Schumann, Philipp G.; Wendt, K; Bushaw, Bruce A.

2005-11-01T23:59:59.000Z

6

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

SciTech Connect (OSTI)

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

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

2013-05-19T23:59:59.000Z

7

Determination of ultratrace boron concentrations in uranium oxide by isotope dilution-thermal ionization mass spectrometry using a simplified separation procedure  

Science Journals Connector (OSTI)

Exhaustive reviews on analytical methodologies and mass spectrometric instrumentation for the determination of boron in different matrices such as biological tissues,...1, 4, 5]. It is an established fact that Isotope

Radhika M. Rao; Ankush R. Parab; K. Sasi Bhushan; Suresh K. Aggarwal

2010-06-01T23:59:59.000Z

8

Determination of uranium concentration in surface soil samples of Iran  

Science Journals Connector (OSTI)

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

A.A. Fathivand; J. Amidi

2006-01-01T23:59:59.000Z

9

Anion exchange method for the sequential determination of uranium, thorium and lead-210 in coal and coal ash  

Science Journals Connector (OSTI)

A radiochemical procedure is presented for the sequential determination of uranium isotopes, thorium isotopes, and210Pb in coal and coal ash. This procedure consists of dry ashing the...210Pb is measured by beta ...

V. R. Casella; C. T. Bishop; A. A. Glosby…

1981-01-01T23:59:59.000Z

10

Evolution of isotopic composition of reprocessed uranium during the multiple recycling in light water reactors with natural uranium feed  

SciTech Connect (OSTI)

A complex approach based on the consistent modeling of neutron-physics processes and processes of cascade separation of isotopes is applied for analyzing physical problems of the multiple usage of reprocessed uranium in the fuel cycle of light water reactors. A number of scenarios of multiple recycling of reprocessed uranium in light water reactors are considered. In the process, an excess absorption of neutrons by the {sup 236}U isotope is compensated by re-enrichment in the {sup 235}U isotope. Specific consumptions of natural uranium for re-enrichment of the reprocessed uranium depending on the content of the {sup 232}U isotope are obtained.

Smirnov, A. Yu., E-mail: a.y.smirnoff@rambler.ru; Sulaberidze, G. A. [National Research Nuclear University MEPhI (Russian Federation); Alekseev, P. N.; Dudnikov, A. A.; Nevinitsa, V. A., E-mail: neva@dhtp.kiae.ru; Proselkov, V. N.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

11

Storage of Hydrogen Isotopes in Uranium Alloys  

Science Journals Connector (OSTI)

Tritium Properties and Interactions with Material / Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988)

T. Yamamoto; Supardjo; T. Terai; F. Ono; S. Tanaka; M. Yamawaki

12

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

13

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...

14

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

15

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

16

Isotopic Tracking of Hanford 300 Area Derived Uranium in the Columbia River  

SciTech Connect (OSTI)

Our objectives in this study are to quantify the discharge rate of uranium (U) to the Columbia River from the Hanford Site's 300 Area, and to follow that U down river to constrain its fate. Uranium from the Hanford Site has variable isotopic composition due to nuclear industrial processes carried out at the site. This characteristic makes it possible to use high-precision isotopic measurements of U in environmental samples to identify even trace levels of contaminant U, determine its sources, and estimate discharge rates. Our data on river water samples indicate that as much as 3.2 kg/day can enter the Columbia River from the 300 Area, which is only a small fraction of the total load of dissolved natural background U carried by the Columbia River. This very low-level of Hanford derived U can be discerned, despite dilution to < 1 percent of natural background U, 350 km downstream from the Hanford Site. These results indicate that isotopic methods can allow the amounts of U from the 300 Area of the Hanford Site entering the Columbia River to be measured accurately to ascertain whether they are an environmental concern, or are insignificant relative to natural uranium background in the Columbia River.

Christensen, John N.; Dresel, P. Evan; Conrad, Mark E.; Patton, Gregory W.; DePaolo, Donald J.

2010-10-31T23:59:59.000Z

17

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

18

Determination of Depleted Uranium in Urine via Isotope Ratio Measurements Using Large-Bore Direct Injection High Efficiency Nebulizer–Inductively Coupled Plasma Mass Spectrometry  

Science Journals Connector (OSTI)

Inductively coupled plasma mass spectrometry (ICP-MS), coupled with a large-bore direct injection high efficiency nebulizer (LB-DIHEN), was utilized to determine the concentration and...

Westphal, Craig S; McLean, John A; Hakspiel, Shelly J; Jackson, William E; McClain, David E; Montaser, Akbar

2004-01-01T23:59:59.000Z

19

Innovative lasers for uranium isotope separation. [Progress report  

SciTech Connect (OSTI)

Copper vapor lasers have important applications to uranium atomic vapor laser isotope separation (AVLIS). The authors have spent the first two years of their project investigating two innovative methods of exciting/pumping copper vapor lasers which have the potential to improve the efficiency and scaling of large laser systems used in uranium isotope separation. Experimental research has focused on the laser discharge kinetics of (1) microwave, and (2) electron beam excitation/pumping of large-volume copper vapor lasers. During the first year, the experiments have been designed and constructed and initial data has been taken. During the second year these experiments have been diagnosed. Highlights of some of the second year results as well as plans for the future include the following: Microwave resonant cavity produced copper vapor plasmas at 2.45 GHz, have been investigated. A CW (0--500 W) signal heats and vaporizes the copper chloride to provide the atomic copper vapor. A pulsed (5 kW, 0.5--5kHz) signal is added to the incoming CW signal via a hybrid mixer to excite the copper states to the laser levels. An enhancement of the visible radiation has been observed during the pulsed pardon of the signal. Electrical probe measurements have been implemented on the system to verify the results of the electromagnetic model formulated last year. Laser gain measurements have been initiated with the use of a commercial copper vapor laser. Measurements of the spatial profile of the emission are also currently being made. The authors plan to increase the amount of pulsed microwave power to the system by implementing a high power magnetron. A laser cavity will be designed and added to this system.

Brake, M.L.; Gilgenbach, R.M.

1991-06-01T23:59:59.000Z

20

Isotope ratio determination in boron analysis  

Science Journals Connector (OSTI)

Traditionally, boron (B) isotope ratios have been determined using thermal ionization...+, Cs+, or O-...for analyte ionization. TIMS can be used in negative or positive ion modes with high sensitivity and precisi...

Ram N. Sah; Patrick H. Brown

1998-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

22

Validation of Electrochemically Modulated Separations Performed On-Line with MC-ICP-MS for Uranium and Plutonium Isotopic Analyses  

SciTech Connect (OSTI)

The most time consuming process in uranium or plutonium isotopic analyses is performing the requisite chromatographic separation of the actinides. Filament preparation for thermal ionization (TIMS) adds further delays, but is generally accepted due to the unmatched performance in trace isotopic analyses. Advances in Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS) are beginning to rival the performance of TIMS. Methods, such as Electrochemically Modulated Separations (EMS) can efficiently pre-concentrate U or Pu quite selectively from small solution volumes in a matrix of 0.5 M nitric acid. When performed in-line with ICP-MS, the rapid analyte release from the electrode is fast, and large transient analyte signal enhancements of >100 fold can be achieved as compared to more conventional continuous nebulization of the original starting solution. This makes the approach ideal for very low level isotope ratio measurements. In this paper, some aspects of EMS performance are described. These include low level Pu isotope ratio behavior versus concentration by MC-ICP-MS and uranium rejection characteristics that are also important for reliable low level Pu isotope ratio determinations.

Liezers, Martin; Olsen, Khris B.; Mitroshkov, Alexandre V.; Duckworth, Douglas C.

2010-08-11T23:59:59.000Z

23

Method and apparatus for storing hydrogen isotopes. [stored as uranium hydride in a block of copper  

DOE Patents [OSTI]

An improved method and apparatus for storing isotopes of hydrogen (especially tritium) are provided. The hydrogen gas is stored as hydrides of material (for example uranium) within boreholes in a block of copper. The mass of the block is critically important to the operation, as is the selection of copper, because no cooling pipes are used. Because no cooling pipes are used, there can be no failure due to cooling pipes. And because copper is used instead of stainless steel, a significantly higher temperature can be reached before the eutectic formation of uranium with copper occurs, (the eutectic of uranium with the iron in stainless steel forms at a significantly lower temperature).

McMullen, J.W.; Wheeler, M.G.; Cullingford, H.S.; Sherman, R.H.

1982-08-10T23:59:59.000Z

24

Secretarial Determination of No Adverse Material Impact for Uranium Transfers  

Broader source: Energy.gov [DOE]

The determination covers the Department’s sales or transfers of no more than 2,705 metric tons (MTU) of natural uranium (NU) or NU equivalent in a calendar year.  The proposed transfers include up...

25

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.

26

Standard test method for isotopic analysis of uranium hexafluoride by double standard single-collector gas mass spectrometer method  

E-Print Network [OSTI]

1.1 This is a quantitative test method applicable to determining the mass percent of uranium isotopes in uranium hexafluoride (UF6) samples with 235U concentrations between 0.1 and 5.0 mass %. 1.2 This test method may be applicable for the entire range of 235U concentrations for which adequate standards are available. 1.3 This test method is for analysis by a gas magnetic sector mass spectrometer with a single collector using interpolation to determine the isotopic concentration of an unknown sample between two characterized UF6 standards. 1.4 This test method is to replace the existing test method currently published in Test Methods C761 and is used in the nuclear fuel cycle for UF6 isotopic analyses. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appro...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

27

Standard test method for analysis of isotopic composition of uranium in nuclear-grade fuel material by quadrupole inductively coupled plasma-mass spectrometry  

E-Print Network [OSTI]

1.1 This test method is applicable to the determination of the isotopic composition of uranium (U) in nuclear-grade fuel material. The following isotopic weight percentages are determined using a quadrupole inductively coupled plasma-mass spectrometer (Q-ICP-MS): 233U, 234U, 235U, 236U, and 238U. The analysis can be performed on various material matrices after acid dissolution and sample dilution into water or dilute nitric (HNO3) acid. These materials include: fuel product, uranium oxide, uranium oxide alloys, uranyl nitrate (UNH) crystals, and solutions. The sample preparation discussed in this test method focuses on fuel product material but may be used for uranium oxide or a uranium oxide alloy. Other preparation techniques may be used and some references are given. Purification of the uranium by anion-exchange extraction is not required for this test method, as it is required by other test methods such as radiochemistry and thermal ionization mass spectroscopy (TIMS). This test method is also described i...

American Society for Testing and Materials. Philadelphia

2000-01-01T23:59:59.000Z

28

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

29

Standard test method for isotopic analysis of hydrolyzed uranium hexafluoride and uranyl nitrate solutions by thermal ionization mass spectrometry  

E-Print Network [OSTI]

1.1 This method applies to the determination of isotopic composition in hydrolyzed nuclear grade uranium hexafluoride. It covers isotopic abundance of 235U between 0.1 and 5.0 % mass fraction, abundance of 234U between 0.0055 and 0.05 % mass fraction, and abundance of 236U between 0.0003 and 0.5 % mass fraction. This test method may be applicable to other isotopic abundance providing that corresponding standards are available. 1.2 This test method can apply to uranyl nitrate solutions. This can be achieved either by transforming the uranyl nitrate solution to a uranyl fluoride solution prior to the deposition on the filaments or directly by depositing the uranyl nitrate solution on the filaments. In the latter case, a calibration with uranyl nitrate standards must be performed. 1.3 This test method can also apply to other nuclear grade matrices (for example, uranium oxides) by providing a chemical transformation to uranyl fluoride or uranyl nitrate solution. 1.4 This standard does not purport to address al...

American Society for Testing and Materials. Philadelphia

2005-01-01T23:59:59.000Z

30

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single-Standard Gas Source Multiple Collector Mass Spectrometer Method  

E-Print Network [OSTI]

1.1 This test method is applicable to the isotopic analysis of uranium hexafluoride (UF6) with 235U concentrations less than or equal to 5 % and 234U, 236U concentrations of 0.0002 to 0.1 %. 1.2 This test method may be applicable to the analysis of the entire range of 235U isotopic compositions providing that adequate Certified Reference Materials (CRMs or traceable standards) are available. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

31

Determination of Depleted Uranium in Environmental Bio-monitor Samples and Soil from Target sites in Western Balkan Region  

SciTech Connect (OSTI)

Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper, we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses, lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP-MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2-755.43 Bq/Kg. We have determined {sup 235}U/{sup 238}U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.002097-0.002380. TIMS measurement confirms presence of DU in some samples. However, we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

Sahoo, Sarata K.; Enomoto, Hiroko; Tokonami, Shinji; Ishikawa, Tetsuo [National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage-ku, Chiba 263-8555 (Japan); Ujic, Predrag; Celikovic, Igor; Zunic, Zora S. [Institute of Nuclear Sciences, Vinca, Mike Petrovica Alasa 12-14, 11000 Belgrade (Serbia)

2008-08-07T23:59:59.000Z

32

Determination of Depleted Uranium in Environmental Bio?monitor Samples and Soil from Target sites in Western Balkan Region  

Science Journals Connector (OSTI)

Lichen and Moss are widely used to assess the atmospheric pollution by heavy metals and radionuclides. In this paper we report results of uranium and its isotope ratios using mass spectrometric measurements (followed by chemical separation procedure) for mosses lichens and soil samples from a depleted uranium (DU) target site in western Balkan region. Samples were collected in 2003 from Han Pijesak (Republika Srpska in Bosnia and Hercegovina). Inductively coupled plasma mass spectrometry (ICP?MS) measurements show the presence of high concentration of uranium in some samples. Concentration of uranium in moss samples ranged from 5.2–755.43 Bq/Kg. We have determined 235 U / 238 U isotope ratio using thermal ionization mass spectrometry (TIMS) from the samples with high uranium content and the ratios are in the range of 0.002097–0.002380. TIMS measurement confirms presence of DU in some samples. However we have not noticed any traces of DU in samples containing lesser amount of uranium or from any samples from the living environment of same area.

Sarata K. Sahoo; Hiroko Enomoto; Shinji Tokonami; Tetsuo Ishikawa; Predrag Uji?; Igor ?elikovi?; Zora S. Žuni?

2008-01-01T23:59:59.000Z

33

Budgets and behaviors of uranium and thorium series isotopes in the Santa Monica Basin off the California Coast  

SciTech Connect (OSTI)

Samples from three time-series sediment traps deployed in the Santa Monica Basin off the California coast were analyzed to study the flux and scavenging of uranium and thorium series isotopes. Variations of uranium and thorium series isotopes fluxes in the water column were obtained by integrating these time-series deployment results. Mass and radionuclide fluxes measured from bottom sediment traps compare favorably with fluxed determined from sediment core data. This agreement suggests that the near-bottom sediment traps are capable of collecting settling particles representative of the surface sediment. The phase distributions of {sup 234}Th in the water column were calculated by an inverse method using sediment trap data, which help to study the variations of {sup 234}Th scavenging in the water column. Scavenging and radioactive decay of {sup 234}Th are the two principal processes for balancing {sup 234}Th budget in the water column. The residence times of dissolved and particulate {sup 234}Th were determined by a {sup 234}Th scavenging model.

Yu, Lei.

1991-12-16T23:59:59.000Z

34

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

35

Separation Of Uranium And Plutonium Isotopes For Measurement By Multi Collector Inductively Coupled Plasma Mass Spectroscopy  

SciTech Connect (OSTI)

Uranium (U) and plutonium (Pu) isotopes in coral soils, contaminated by nuclear weapons testing in the northern Marshall Islands, were isolated by ion-exchange chromatography and analyzed by mass spectrometry. The soil samples were spiked with {sup 233}U and {sup 242}Pu tracers, dissolved in minerals acids, and U and Pu isotopes isolated and purified on commercially available ion-exchange columns. The ion-exchange technique employed a TEVA{reg_sign} column coupled to a UTEVA{reg_sign} column. U and Pu isotope fractions were then further isolated using separate elution schemes, and the purified fractions containing U and Pu isotopes analyzed sequentially using multi-collector inductively coupled plasma mass spectrometer (MCICP-MS). High precision measurements of {sup 234}U/{sup 235}U, {sup 238}U/{sup 235}U, {sup 236}U/{sup 235}U, and {sup 240}Pu/{sup 239}Pu in soil samples were attained using the described methodology and instrumentation, and provide a basis for conducting more detailed assessments of the behavior and transfer of uranium and plutonium in the environment.

Martinelli, R E; Hamilton, T F; Williams, R W; Kehl, S R

2009-03-29T23:59:59.000Z

36

Standard guide for the determination of uranium-232 in uranium hexafluoride  

E-Print Network [OSTI]

1.1 This method covers the determination of 232U in uranium hexafluoride by alpha spectrometry. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and to determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2006-01-01T23:59:59.000Z

37

Standard test method for isotopic abundance analysis of uranium hexa?uoride and uranyl nitrate solutions by multi-collector, inductively coupled plasma-mass spectrometry  

E-Print Network [OSTI]

Standard test method for isotopic abundance analysis of uranium hexa?uoride and uranyl nitrate solutions by multi-collector, inductively coupled plasma-mass spectrometry

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

38

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

DOE Patents [OSTI]

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

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

1995-05-30T23:59:59.000Z

39

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

DOE Patents [OSTI]

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

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

1995-01-01T23:59:59.000Z

40

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

SciTech Connect (OSTI)

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

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

2003-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

Establishing Specifications for Low Enriched Uranium Fuel Operations Conducted Outside the High Flux Isotope Reactor Site  

SciTech Connect (OSTI)

The National Nuclear Security Administration (NNSA) has funded staff at Oak Ridge National Laboratory (ORNL) to study the conversion of the High Flux Isotope Reactor (HFIR) from the current, high enriched uranium fuel to low enriched uranium fuel. The LEU fuel form is a metal alloy that has never been used in HFIR or any HFIR-like reactor. This report provides documentation of a process for the creation of a fuel specification that will meet all applicable regulations and guidelines to which UT-Battelle, LLC (UTB) the operating contractor for ORNL - must adhere. This process will allow UTB to purchase LEU fuel for HFIR and be assured of the quality of the fuel being procured.

Pinkston, Daniel [ORNL; Primm, Trent [ORNL; Renfro, David G [ORNL; Sease, John D [ORNL

2010-10-01T23:59:59.000Z

42

Quantifying Uranium Isotope Ratios Using Resonance Ionization Mass Spectrometry: The Influence of Laser Parameters on Relative Ionization Probability  

SciTech Connect (OSTI)

Resonance Ionization Mass Spectrometry (RIMS) has been developed as a method to measure relative uranium isotope abundances. In this approach, RIMS is used as an element-selective ionization process to provide a distinction between uranium atoms and potential isobars without the aid of chemical purification and separation. We explore the laser parameters critical to the ionization process and their effects on the measured isotope ratio. Specifically, the use of broad bandwidth lasers with automated feedback control of wavelength was applied to the measurement of {sup 235}U/{sup 238}U ratios to decrease laser-induced isotopic fractionation. By broadening the bandwidth of the first laser in a 3-color, 3-photon ionization process from a bandwidth of 1.8 GHz to about 10 GHz, the variation in sequential relative isotope abundance measurements decreased from >10% to less than 0.5%. This procedure was demonstrated for the direct interrogation of uranium oxide targets with essentially no sample preparation. A rate equation model for predicting the relative ionization probability has been developed to study the effect of variation in laser parameters on the measured isotope ratio. This work demonstrates that RIMS can be used for the robust measurement of uranium isotope ratios.

Isselhardt, B H

2011-09-06T23:59:59.000Z

43

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...

44

Sample preparation for isotopic determination of boron in clay sediments  

Science Journals Connector (OSTI)

The procedures of sample preparation for isotopic determination of boron in clay sediments is very cumbersome, by ... experiments were carried out. In this paper, boron in clay sediments was extracted with HCl .....

Yanling Zhang; Yingkai Xiao; Yunqi Ma; Qin Zhuge…

2013-06-01T23:59:59.000Z

45

Uranium-series isotopes transport in surface, vadose and ground waters at San Marcos uranium bearing basin, Chihuahua, Mexico  

Science Journals Connector (OSTI)

In the U deposit area at San Marcos in Chihuahua, Mexico, hydrogeological and climatic conditions are very similar to the Nopal I, Peña Blanca U deposit, 50 km away. The physicochemical parameters and activity concentrations of several 238U-series isotopes have been determined in surface, vadose and ground waters at San Marcos. The application of some published models to activity ratios of these isotopes has allowed assessing the order of magnitude of transport parameters in the area. Resulting retardation factors in San Marcos area are Rf238 ? 250–14,000 for the unsaturated zone and ?110–1100 for the saturated zone. The results confirm that the mobility of U in San Marcos is also similar to that of the Nopal I U deposit and this area can be considered as a natural analog of areas suitable for geologic repositories of high-level nuclear waste.

Juan Carlos Burillo Montúfar; Manuel Reyes Cortés; Ignacio Alfonso Reyes Cortés; Ma. Socorro Espino Valdez; Octavio Raúl Hinojosa de la Garza; Diana Pamela Nevárez Ronquillo; Eduardo Herrera Peraza; Marusia Rentería Villalobos; María Elena Montero Cabrera

2012-01-01T23:59:59.000Z

46

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

Science Journals Connector (OSTI)

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

Guogang Jia; M. Belli; U. Sansone…

47

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

SciTech Connect (OSTI)

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

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

2009-03-01T23:59:59.000Z

48

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

An engineering design study that would enable the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel is ongoing at Oak Ridge National Laboratory. The computational models used to search for a low-enriched uranium (LEU) fuel design that would meet the requirements for the conversion study, and the recent results obtained with these models during FY 2009, are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating high-enriched uranium fuel core. These studies indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2009-11-01T23:59:59.000Z

49

Isotope Shift Measurements of Stable and Short-Lived Lithium Isotopes for Nuclear Charge Radii Determination  

E-Print Network [OSTI]

Changes in the mean-square nuclear charge radii along the lithium isotopic chain were determined using a combination of precise isotope shift measurements and theoretical atomic structure calculations. Nuclear charge radii of light elements are of high interest due to the appearance of the nuclear halo phenomenon in this region of the nuclear chart. During the past years we have developed a new laser spectroscopic approach to determine the charge radii of lithium isotopes which combines high sensitivity, speed, and accuracy to measure the extremely small field shift of an 8 ms lifetime isotope with production rates on the order of only 10,000 atoms/s. The method was applied to all bound isotopes of lithium including the two-neutron halo isotope Li-11 at the on-line isotope separators at GSI, Darmstadt, Germany and at TRIUMF, Vancouver, Canada. We describe the laser spectroscopic method in detail, present updated and improved values from theory and experiment, and discuss the results.

W. Nörtershäuser; R. Sánchez; G. Ewald; A. Dax; J. Behr; P. Bricault; B. A. Bushaw; J. Dilling; M. Dombsky; G. W. F. Drake; S. Götte; H. -J. Kluge; Th. Kühl; J. Lassen; C. D. P. Levy; K. Pachucki; M. Pearson; M. Puchalski; A. Wojtaszek; Z. -C. Yan; C. Zimmermann

2010-09-02T23:59:59.000Z

50

Mobility determination of lead isotopes in glass for retrospective radon measurements  

Science Journals Connector (OSTI)

......al. Retention of Pb isotopes in glass surfaces for...Vierinen K. The ion guide isotope separator online...Whitlow H. J. Boron diffusion in bulk cobalt...srim.org . Mobility determination of lead isotopes in glass for retrospective......

Mikko Laitinen; Iiro Riihimäki; Jörgen Ekman; A. R. Ananda Sagari; Lennart B. Karlsson; Somjai Sangyuenyongpipat; Sergey Gorelick; Heikki Kettunen; Heikki Penttilä; Ragnar Hellborg; Timo Sajavaara; Johan Helgesson; Harry J. Whitlow

2008-08-01T23:59:59.000Z

51

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%.

52

DETERMINATION OF 237NP AND PU ISOTOPES IN LARGE SOIL SAMPLES BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY  

SciTech Connect (OSTI)

A new method for the determination of {sup 237}Np and Pu isotopes in large soil samples has been developed that provides enhanced uranium removal to facilitate assay by inductively coupled plasma mass spectrometry (ICP-MS). This method allows rapid preconcentration and separation of plutonium and neptunium in large soil samples for the measurement of {sup 237}Np and Pu isotopes by ICP-MS. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via {sup 238}U peak tailing. The method provides enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then transferring Pu to DGA resin for additional purification. The decontamination factor for removal of uranium from plutonium for this method is greater than 1 x 10{sup 6}. Alpha spectrometry can also be applied so that the shorter-lived {sup 238}Pu isotope can be measured successfully. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu and {sup 238}Pu were measured by alpha spectrometry.

Maxwell, S.

2010-07-26T23:59:59.000Z

53

Linking specific heterotrophic bacterial populations to bioreduction of uranium and nitrate using stable isotope probing in contaminated subsurface sediments  

SciTech Connect (OSTI)

Shifts in terminal electron-accepting processes during biostimulation of uranium-contaminated sediments were linked to the composition of stimulated microbial populations using DNA-based stable isotope probing. Nitrate reduction preceded U(VI) and Fe(III) reduction in [{sup 13}C]ethanol-amended microcosms. The predominant, active denitrifying microbial groups were identified as members of the Betaproteobacteria, whereas Actinobacteria dominated under metal-reducing conditions.

Akob, Denise M. [Florida State University; Kerkhof, Lee [Rutgers University; Kusel, Kirsten [Friedrich Schiller University Jena, Jena Germany; Watson, David B [ORNL; Palumbo, Anthony Vito [ORNL; Kostka, Joel [Florida State University

2011-01-01T23:59:59.000Z

54

Determination of americium and curium by isotope dilution  

SciTech Connect (OSTI)

The authors propose a method for the determination of americium and curium in solutions of spent fuels from water cooled and moderated reactors that is based on isotope dilution with Am 241 and Cm 244 combined with extraction chromatography of americium and curium and alpha spectroscopy of the labels.

Yablochkin, A.V.; Krapivin, M.I.; Fedotov, S.N.; Yudina, V.G.; Yakobson, A.A.

1987-11-01T23:59:59.000Z

55

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

SciTech Connect (OSTI)

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

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

2008-08-07T23:59:59.000Z

56

Determination of Method Detection Limits for Trace 232-Thorium and 238-Uranium in Copper using Ion Exchange and ICPMS  

SciTech Connect (OSTI)

Determination of Method Detection Limits for Trace 232-Thorium and 238-Uranium in Copper using Ion Exchange and ICPMS

Hoppe, Eric W.; LaFerriere, Brian D.; Maiti, Tapas C.; Soin, Aleksandr

2014-04-15T23:59:59.000Z

57

Using k0-UNAA for the determination of depleted uranium in the moss biomonitoring technique  

Science Journals Connector (OSTI)

The use of ammunition containing depleted uranium (DU) in several military actions is of growing health concern to the population related to the risk arising from contamination of the environment with DU penetrators and dust. Environmental monitoring of uranium and its isotopic ratios therefore become important parameters since they allow for source identification. Neutron activation analysis according to the k0-standardisation not only allows for quantification of trace elements including uranium, but it can also provide information about the 235U/238U isotope ratio. The application of this method as a screening technique to moss samples, as a bio-indicator for this atmospheric pollution, was evaluated for samples spiked with different 235U/238U isotope ratios. Detection limits of about 0.6 ng/g and 6 ng/g were obtained for 235U and 238U, respectively. The concentration of natural uranium found in moss samples is however the limiting factor, reducing the quantification limit for DU to 400 ng/g.

Peter Vermaercke; Liesel Sneyers; Fulvio Farina Arbocco; Yulia Aleksiayenak

2011-01-01T23:59:59.000Z

58

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

59

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

Science Journals Connector (OSTI)

Spatial and temporal distribution of the radioisotopes concentrations were determined in sediments near the surface and core samples extracted from two reservoirs located in an arid region close to Chihuahua City Mexico. At San Marcos reservoir one core was studied while from Luis L. Leon reservoir one core from the entrance and another one close to the wall were investigated. 232 Th -series 238 U -series 40 K and 137 Cs activity concentrations (AC Bq kg?1) were determined by gamma spectrometry with a high purity Ge detector. 238 U and 234 U ACs were obtained by liquid scintillation and alpha spectrometry with a surface barrier detector. Dating of core sediments was performed applying CRS method to 210 Pb activities. Results were verified by 137 Cs AC. Resulting activity concentrations were compared among corresponding surface and core sediments. High 238 U -series AC values were found in sediments from San Marcos reservoir because this site is located close to the Victorino uranium deposit. Low AC values found in Luis L. Leon reservoir suggest that the uranium present in the source of the Sacramento – Chuviscar Rivers is not transported up to the Conchos River. Activity ratios (AR) 234 U / 238 U and 238 U / 226 Ra in sediments have values between 0.9–1.2 showing a behavior close to radioactive equilibrium in the entire basin. 232 Th / 238 U 228 Ra / 226 Ra ARs are witnesses of the different geological origin of sediments from San Marcos and Luis L. Leon reservoirs.

2014-01-01T23:59:59.000Z

60

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

E-Print Network [OSTI]

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

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

62

Determination of boron isotope ratios in geological materials by inductively coupled plasma mass spectrometry  

Science Journals Connector (OSTI)

Determination of boron isotope ratios in geological materials by inductively coupled plasma mass spectrometry ... Isotope dilution analysis using flow injection inductively coupled plasma mass spectrometry was applied to determine low boron contents in iron and steel samples. ...

D. Conrad Gregoire

1987-10-01T23:59:59.000Z

63

Leaching of depleted uranium in soil as determined by column experiments  

Science Journals Connector (OSTI)

The basic features of the leachability of depleted uranium (DU) projectiles in soil was investigated...235U and 238U were determined by inductively coupled plasma mass spectrometry. The leaching rates of 238U fro...

W. Schimmack; U. Gerstmann; U. Oeh; W. Schultz…

2005-12-01T23:59:59.000Z

64

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

SciTech Connect (OSTI)

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

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

2006-11-01T23:59:59.000Z

65

Atomic Spectroscopy and Separated Isotopes  

Science Journals Connector (OSTI)

The advantages in the use of separated isotopes in atomic spectroscopy for the determination of nuclear momentsI ? Q and for studies of the isotope-shift phenomena are discussed. Illustrations of spectra are given for mercury uranium and samarium. In addition a summary is given of twenty-two so-called problem nuclei i.e. those naturally occurring isotopes for which the nuclear moments are completely uncertain. Concluding remarks are made on such problems as the evaluation of the absolute magnitude of isotope shifts the role of “forbidden transitions” in isotope spectra and the potential future value of spectro-isotopic assay techniques.

J. R. McNally Jr.

1952-01-01T23:59:59.000Z

66

Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

An engineering design study of the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel is ongoing at Oak Ridge National Laboratory. The computational models developed during fiscal year 2010 to search for an LEU fuel design that would meet the requirements for the conversion and the results obtained with these models are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating HEU fuel core. The results obtained indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations under the assumption that the operating power for the reactor fueled with LEU can be increased from the current value of 85 MW to 100 MW.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2011-05-01T23:59:59.000Z

67

A World without Sample Preparation: Developing Rapid Uranium Isotope Measurement Capabilities by Resonance Ionization Mass Spectrometry (RIMS)  

SciTech Connect (OSTI)

We are developing highly sensitive, highly discriminating laser-based techniques for rapid determination of isotopic compositions. Rapid command of such information is critical to assessment of the origin and history of nuclear materials, particularly in post-detonation scenarios.

Knight, K B; Hutcheon, I D; Isselhardt, B H; Savina, M R; Prussin, S G

2009-06-08T23:59:59.000Z

68

Extraction and Determination of Boron Isotopic Composition in Tourmalines  

Science Journals Connector (OSTI)

Tourmaline is an abundant boron-rich alumosilicate mineral with complex chemistry and rich in Fe, Mg, Al, Si elements. In this study, tourmaline samples were decomposed by alkali fusion method, and then the boron was separated and purified using three different procedures. It was found that both Fe3+ and Al3+ ions, rich in tourmaline samples seriously, which affected the accurate determination of boron concentration by Azomethine-H spectrophotometric method and also caused a loss of boron by specific adsorption when large amount of amorphous hydroxide precipitate formed in ion-exchange columns. The addition of small amount of EDTA can eliminate the influence, but brings serious isobaric interference on boron isotopic analysis by TIMS. Finally, a three-column ion-exchange procedure was established including the first mixed resin column, the peristaltic pump coupled boron specific resin column, and the second mixed resin column, which ensures the full recovery of boron (> 99%) from tourmaline samples with complex matrices. The PTIMS-Cs2BO2+-static double-collection method was established by selecting H3-H4 Faraday cups and optimizing parameters in Zoom Optics (Focus Quad: 15; Dispersion Quad: ?85) in a Triton TI mass spectrometer. The determined average 11B/10B value of NIST SRM 951 standard boron solution was 4.05044±0.00012 (2?, n = 8, 1 ?g B), which was superior to the dynamic collection method in internal/external precision. A ?11B value of ?0.3% for NIST SRM 951 through the same pretreatment procedure was obtained, indicating that there was no isotopic fractionation occurred during the extraction procedure. The comparison of boron isotopic compositions in natural samples by TIMS and MC-ICP-MS after the chemistry procedure indicated that ?11B values determined by the static PTIMS-Cs2BO2+ method were in good agreement with that by MC-ICP-MS.

Xiong YAN; Shao-Yong JIANG; Hai-Zhen WEI; Yan YAN; He-Pin WU; Wei PU

2012-01-01T23:59:59.000Z

69

In-line assay monitor for uranium hexafluoride  

DOE Patents [OSTI]

An in-line assay monitor for determining the content of uranium-235 in a uranium hexafluoride gas isotopic separation system is provided which removes the necessity of complete access to the operating parameters of the system for determining the uranium-235 content. The method and monitor for carrying out the method involve cooling of a radiation pervious chamber connected in fluid communication with the selected point in the system to withdraw a specimen and solidify the specimen in the chamber. The specimen is irradiated by means of an ionizing radiation source of energy different from that of the 185 keV gamma emissions from uranium-235. The uranium-235 content of the specimen is determined from comparison of the accumulated 185 keV energy counts and reference energy counts. The latter is used to measure the total uranium isotopic content of the specimen.

Wallace, S.A.

1980-03-21T23:59:59.000Z

70

ISOTOPES  

E-Print Network [OSTI]

uranium, heavy-water-moderated CANDU reactor, as contrastedis important, and in the CANDU power reactor, which uses

Lederer, C. Michael

2013-01-01T23:59:59.000Z

71

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

72

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

SciTech Connect (OSTI)

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

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

2007-11-01T23:59:59.000Z

73

Uranium-plutonium-neptunium fuel cycle to produce isotopically denatured plutonium  

SciTech Connect (OSTI)

In view of the considerable amount of /sup 237/ Np produced as a by-product in nuclear power reactors, possible utilization of this nuclide in the nuclear fuel cycle has been studied. In particular, the performance of a gas-cooled fast breeder reactor as a neptunium burner was assessed. A strategy was developed and mass flows were computed for a denatured plutonium LWR strategy using uranium, plutonium and neptunium recycling. 10 refs.

Wydler, P.; Heer, W.; Stiller, P.; Wenger, H.U.

1980-06-01T23:59:59.000Z

74

Assumptions and Criteria for Performing a Feasability Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel  

SciTech Connect (OSTI)

A computational study will be initiated during fiscal year 2006 to examine the feasibility of converting the High Flux Isotope Reactor from highly enriched uranium fuel to low-enriched uranium. The study will be limited to steady-state, nominal operation, reactor physics and thermal-hydraulic analyses of a uranium-molybdenum alloy that would be substituted for the current fuel powder--U{sub 3}O{sub 8} mixed with aluminum. The purposes of this document are to (1) define the scope of studies to be conducted, (2) define the methodologies to be used to conduct the studies, (3) define the assumptions that serve as input to the methodologies, (4) provide an efficient means for communication with the Department of Energy and American research reactor operators, and (5) expedite review and commentary by those parties.

Primm, R.T., III; Ellis, R.J.; Gehin, J.C.; Moses, D.L.; Binder, J.L.; Xoubi, N. (U. of Cincinnati)

2006-02-01T23:59:59.000Z

75

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.

76

Determination of boron in nuclear materials by isotope dilution technique. Part I  

Science Journals Connector (OSTI)

The application of the mass-spectrometric stable-isotope dilution technique for the determination of microgram and submicrogram quantities of boron in nuclear materials is described. An adequate...10B) is added t...

J. Marsel; D. Milivojevi?

1971-01-01T23:59:59.000Z

77

Determination of boron traces in rye grass BCR 281 by isotope dilution mass spectrometry  

Science Journals Connector (OSTI)

A method for the isotope dilution mass spectrometric (IDMS) determination of boron in rye grass at the 5 ?g...?1 level has been developed. The mass spectrometric measurements are performed using negative thermal ...

A. Lamberty; V. Holland; A. Verbruggen…

1988-01-01T23:59:59.000Z

78

Standard test method for determination of technetium-99 in uranium hexafluoride by liquid scintillation counting  

E-Print Network [OSTI]

1.1 This test method is a quantitative method used to determine technetium-99 (99Tc) in uranium hexafluoride (UF6) by liquid scintillation counting. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

79

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

80

Microscopic description of fission in Uranium isotopes with the Gogny energy density functional  

E-Print Network [OSTI]

The most recent parametrizations D1S, D1N and D1M of the Gogny energy density functional are used to describe fission in the isotopes $^{232-280}$ U. Fission paths, collective masses and zero point quantum corrections, obtained within the constrained Hartree-Fock-Bogoliubov approximation, are used to compute the systematics of the spontaneous fission half-lives $t_\\mathrm{SF}$, the masses and charges of the fission fragments as well as their intrinsic shapes. The Gogny-D1M parametrization has been benchmarked against available experimental data on inner and second barrier heights, excitation energies of the fission isomers and half-lives in a selected set of Pu, Cm, Cf, Fm, No, Rf, Sg, Hs and Fl nuclei. It is concluded that D1M represents a reasonable starting point to describe fission in heavy and superheavy nuclei. Special attention is also paid to understand the uncertainties in the predicted $t_\\mathrm{SF}$ values arising from the different building blocks entering the standard semi-classical Wentzel-Kramers-Brillouin formula. Although the uncertainties are large, the trend with mass or neutron numbers are well reproduced and therefore the theory still has predictive power. In this respect, it is also shown that modifications of a few per cent in the pairing strength can have a significant impact on the collective masses leading to uncertainties in the $t_\\mathrm{SF}$ values of several orders of magnitude.

R. Rodriguez-Guzman; L. M. Robledo

2014-05-25T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

Determination of boron isotope ratios by Zeeman effect background correction-graphite furnace atomic absorption spectrometry  

Science Journals Connector (OSTI)

A new method for the determination of isotopic ratio of boron using Zeeman effect background correction-graphite furnace atomic absorption spectrometry with conventional atomizer and natural-boron hollow cathode source is described. The isotope-shift Zeeman effect at 208.9 nm is utilized for isotopic ratio determination. At a given concentration of total boron, the net absorbance decreases linearly with increasing 10B/11B ratio. The absorbances are recorded at the field strength of 1.0 T. The isotope ratios measured by the proposed method were in good agreement with the results obtained by inductively coupled plasma-quadruple mass spectrometry or thermal ionization mass spectrometry. The present method is fairly fast and less expensive compared to the above techniques and is quite suitable for plant environments.

S. Thangavel; S.V. Rao; K. Dash; J. Arunachalam

2006-01-01T23:59:59.000Z

82

Analysis of IAEA environmental samples for plutonium and uranium by ICP/MS in support of international safeguards  

Science Journals Connector (OSTI)

A method for the separation and determination of total and isotopic uranium and plutonium by ICP/MS was developed for IAEA samples on cellulose-based media. Preparation of the IAEA samples involved a series of...

O. T. Farmer III; K. B. Olsen; M. L. Thomas…

2008-05-01T23:59:59.000Z

83

Modeling non-steady state radioisotope transport in the vadose zone--A case study using uranium isotopes at Pena Blanca, Mexico  

SciTech Connect (OSTI)

Current models using U- and Th-series disequilibria to study radioisotope transport in groundwater systems mostly consider a steady-state situation. These models have limited applicability to the vadose zone (UZ) where the concentration and migratory behavior of radioisotopes in fluid are often transitory. We present here, as a first attempt of its kind, a model simulating the non-steady state, intermittent fluid transport in vadose layers. It provides quantitative constraints on in-situ migration of dissolved and colloidal radioisotopes in terms of retardation factor and rock-water interaction (or water transit) time. For uranium, the simulation predicts that intermittent flushing in the UZ leads to a linear relationship between reciprocal U concentration and {sup 234}U/{sup 238}U ratio in percolating waters, with the intercept and slope bearing information on the rates of dissolution and {alpha}-recoil of U isotopes, respectively. The general validity of the model appears to be borne out by the measurement of uranium isotopes in UZ waters collected at various times over a period during 1995-2006 from a site in the Pena Blanca mining district, Mexico, where the Nopal I uranium deposit is located. Enhanced {sup 234}U/{sup 238}U ratios in vadose-zone waters resulting from lengthened non-flushing time as prescribed by the model provide an interpretative basis for using {sup 234}U/{sup 238}U in cave calcites to reconstruct the regional changes in hydrology and climate. We also provide a theoretical account of the model's potential applications using radium isotopes.

Ku, T. L.; Luo, S.; Goldstein, S. J.; Murrell, M. T.; Chu, W. L.; Dobson, P. F.

2009-06-01T23:59:59.000Z

84

Standard test method for determination of impurities in nuclear grade uranium compounds by inductively coupled plasma mass spectrometry  

E-Print Network [OSTI]

1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish ...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

85

RAPID FUSION METHOD FOR DETERMINATION OF PLUTONIUM ISOTOPES IN LARGE RICE SAMPLES  

SciTech Connect (OSTI)

A new rapid fusion method for the determination of plutonium in large rice samples has been developed at the Savannah River National Laboratory (Aiken, SC, USA) that can be used to determine very low levels of plutonium isotopes in rice. The recent accident at Fukushima Nuclear Power Plant in March, 2011 reinforces the need to have rapid, reliable radiochemical analyses for radionuclides in environmental and food samples. Public concern regarding foods, particularly foods such as rice in Japan, highlights the need for analytical techniques that will allow very large sample aliquots of rice to be used for analysis so that very low levels of plutonium isotopes may be detected. The new method to determine plutonium isotopes in large rice samples utilizes a furnace ashing step, a rapid sodium hydroxide fusion method, a lanthanum fluoride matrix removal step, and a column separation process with TEVA Resin? cartridges. The method can be applied to rice sample aliquots as large as 5 kg. Plutonium isotopes can be determined using alpha spectrometry or inductively-coupled plasma mass spectrometry (ICP-MS). The method showed high chemical recoveries and effective removal of interferences. The rapid fusion technique is a rugged sample digestion method that ensures that any refractory plutonium particles are effectively digested. The MDA for a 5 kg rice sample using alpha spectrometry is 7E-5 mBq g{sup -1}. The method can easily be adapted for use by ICP-MS to allow detection of plutonium isotopic ratios.

Maxwell, S.

2013-03-01T23:59:59.000Z

86

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

87

In-line assay monitor for uranium hexafluoride  

DOE Patents [OSTI]

An in-line assay monitor for determining the content of uranium-235 in a uranium hexafluoride gas isotopic separation system is provided which removes the necessity of complete access to the operating parameters of the system for determining the uranium-235 content. The monitor is intended for uses such as safeguard applications to assure that weapons grade uranium is not being produced in an enrichment cascade. The method and monitor for carrying out the method involve cooling of a radiation pervious chamber connected in fluid communication with the selected point in the system to withdraw a specimen and solidify the specimen in the chamber. The specimen is irradiated by means of an ionizing radiation source of energy different from that of the 185 keV gamma emissions from the uranium-235 present in the specimen. Simultaneously, the gamma emissions from the uranium-235 of the specimen and the source emissions transmitted through the sample are counted and stored in a multiple channel analyzer. The uranium-235 content of the specimen is determined from the comparison of the accumulated 185 keV energy counts and the reference energy counts. The latter is used to measure the total uranium isotopic content of the specimen. The process eliminates the necessity of knowing the system operating conditions and yet obtains the necessary data without need for large scintillation crystals and sophisticated mechanical designs.

Wallace, Steven A. (Knoxville, TN)

1981-01-01T23:59:59.000Z

88

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

89

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

SciTech Connect (OSTI)

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

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

2014-03-01T23:59:59.000Z

90

Determination of Young's modulus and mechanical damping as a function of temperature for depleted uranium-0.75 wt% titanium using the PUCOT  

E-Print Network [OSTI]

[3f. The components fabricated from depleted uranium offer substantial size and cost savings over all other available materials. Large containers of depleted uranium, weighing up to several thousand kilograms each, are used to transport and store...DETERMINATION OF YOUNG'S MODULUS AND MECHANICAL DAMPING AS A FUNCTION OF TEMPERATURE FOR DEPLETED URANIUM-0. 75 WT% TITANIUM USING THE PUCOT A Thesis bY KEITH HOWARD KEENE Submitted to the Graduate College of Texas A&M University in partial...

Keene, Keith Howard

2012-06-07T23:59:59.000Z

91

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride  

E-Print Network [OSTI]

1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

92

U235: A Gamma Ray Analysis Code for Uranium Isotopic Determination  

Office of Scientific and Technical Information (OSTI)

Color: metallic gray Discoverer: Martin Klaproth Date discovered: 1789 Discovered at: Germany Meaning of name: Planet Uranus Radii (pm) Atomic: 138.5 van der Waals: Covalent: 142...

93

Enclosure 1 -CCP-AK-INL-004, Table 5-2 (1 page) Table 5-2. Isotopic Compositions of Rocky Flats Plutonium and Uranium  

E-Print Network [OSTI]

Flats Plutonium and Uranium Weapons-Grade Plutonium Enriched Uranium Depleted Uranium Plutonium-238 0.01 ­ 0.05% Uranium-234 0.1 ­ 1.02% Uranium-234 0.0006% Plutonium-239 92.8 ­ 94.4% Uranium-235 90 ­ 94% Uranium-235 0.2 ­ 0.3% Plutonium-240 4.85 ­ 6.5% Uranium-236 0.4 ­ 0.5% Uranium-238 99.7 ­ 99.8% Plutonium

94

RAPID DETERMINATION OF 237 NP AND PU ISOTOPES IN WATER BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY AND ALPHA SPECTROMETRY  

SciTech Connect (OSTI)

A new method that allows rapid preconcentration and separation of plutonium and neptunium in water samples was developed for the measurement of {sup 237}Np and Pu isotopes by inductively-coupled plasma mass spectrometry (ICP-MS) and alpha spectrometry; a hybrid approach. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via peak tailing. The method provide enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then moving Pu to DGA resin for additional removal of uranium. The decontamination factor for uranium from Pu is almost 100,000 and the decontamination factor for U from Np is greater than 10,000. This method uses stacked extraction chromatography cartridges and vacuum box technology to facilitate rapid separations. Preconcentration is performed using a streamlined calcium phosphate precipitation method. Purified solutions are split between ICP-MS and alpha spectrometry so that long and short-lived Pu isotopes can be measured successfully. The method allows for simultaneous extraction of 20 samples (including QC samples) in 4 to 6 hours, and can also be used for emergency response. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu, {sup 238}Pu, and {sup 239}Pu were measured by alpha spectrometry.

Maxwell, S.; Jones, V.; Culligan, B.; Nichols, S.; Noyes, G.

2010-06-23T23:59:59.000Z

95

Accurate and Precise Determination of Boron Isotopic Ratios at Low Concentration by Positive Thermal Ionization Mass Spectrometry Using Static Multicollection of Cs2BO2+ Ions  

Science Journals Connector (OSTI)

Accurate and Precise Determination of Boron Isotopic Ratios at Low Concentration by Positive Thermal Ionization Mass Spectrometry Using Static Multicollection of Cs2BO2+ Ions ... (1) A relatively large mass difference (10%) between the two isotopes and high volatility results in significant boron isotopic variation from ?70‰(2) to +75‰(3) in natural materials; thus, boron isotopes have numerous applications in geochemistry, isotope hydrology, oceanography, environmental sciences, cosmology, and nuclear technology. ... (2) Our method provided better long-term stability of NIST 951 standard compared to “Zoom Quad” mode when more than two isotopes were determined in addition to boron isotope. ...

Mao-yong He; Ying-kai Xiao; Zhang-dong Jin; Yun-qi Ma; Jun Xiao; Yan-ling Zhang; Chong-guang Luo; Fei Zhang

2013-05-29T23:59:59.000Z

96

Determination of boron isotopic variations in aquatic systems with negative thermal ionization mass spectrometry as a tracer for anthropogenic influences  

Science Journals Connector (OSTI)

A technique for precise boron isotope ratio measurements with a high detection power ... –0.3% have been obtained for the determination of the 11B/10B isotope ratio using nanogram amounts of boron. Ba(OH)2 has be...

S. Eisenhut; K. G. Heumann; A. Vengosh

1996-03-01T23:59:59.000Z

97

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

98

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.

99

Determination of the separation coefficients of the isotopes of boron in the equilibrium evaporation of BCl3  

Science Journals Connector (OSTI)

The separation coefficients of the isotopes of boron are determined for equilibrium evaporation of boron chloride in the temperature interval 12.7 to 85 °C. The methods are described, and the equation relating...

N. N. Sevryugova; O. V. Uvarov; N. M. Zhavoronkov

1956-01-01T23:59:59.000Z

100

Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method  

SciTech Connect (OSTI)

For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios were measured again in unirradiated samples to obtain reference or starting values at the same time irradiated samples were analyzed. In particular, 49Ti/48Ti ratios were indistinguishably close to values determined several months earlier and to expected natural values. 2. 49Ti/48Ti ratios were measured in 3 irradiated samples thus far, and demonstrate marked departures from natural or initial ratios, well beyond analytical uncertainty, and the ratios vary with reported fluence values. The irradiated samples appear to have significant surface contamination or radiation damage which required more time for SIMS analyses. 3. Other activated impurity elements still limit the sample size for SIMS analysis of irradiated samples. The sub-samples chosen for SIMS analysis, although smaller than optimal, were still analyzed successfully without violating the conditions of the applicable Radiological Work Permit

Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J.; Hurley, David E.

2007-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

102

Mass-Independent Isotope Effects  

Science Journals Connector (OSTI)

Scientific interests: ESR and NMR spectroscopies, molecular magnets, mechanisms of chemical and biochemical reactions, spin physics and chemistry, isotopes and isotope effects in chemistry and biochemistry. ... Another mass-independent isotope effect was detected in 1983 as a deviation of isotopic distribution in reaction products from that which would be expected from the mass-dependent isotope effect. ... Later, Nomura et al.(92) have found isotopic 233U anomaly in the U4+–U6+ exchange reaction; they noted that the isotope effect was correlated with isotope shifts in the atomic spectra of uranium isotopes. ...

Anatoly L. Buchachenko

2013-01-09T23:59:59.000Z

103

Isotope Dilution Analysis for Flow Injection ICPMS Determination of Microgram per Gram Levels of Boron in Iron and Steel after Matrix Removal  

Science Journals Connector (OSTI)

Isotope Dilution Analysis for Flow Injection ICPMS Determination of Microgram per Gram Levels of Boron in Iron and Steel after Matrix Removal ... 15,16ID analysis coupled with ICPMS is a powerful technique capable of highly accurate and precise determinations of elements that have two or more stable isotopes. ... To determine boron in unknowns, first the boron isotopic composition of the enriched spike must be characterized, and then the total boron concentration of the spike solution must be determined. ...

Aurora G. Coedo; Teresa Dorado; Bernardo J. Fernandez; Francisco J. Alguacil

1996-03-15T23:59:59.000Z

104

lead-isotope age  

Science Journals Connector (OSTI)

lead-isotope age, lead-lead age [An age in years calculated from the ratio of lead-207 to lead-206, a by-product of the uranium-thorium-lead age method] ? Blei-Isotopen-Alter n

2014-08-01T23:59:59.000Z

105

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

106

Calculating Capstone Depleted Uranium Aerosol Concentrations from Beta Activity Measurements  

SciTech Connect (OSTI)

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

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

2009-03-01T23:59:59.000Z

107

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

108

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.

109

unstable isotope  

Science Journals Connector (OSTI)

unstable isotope, radioisotope ? unstabiles Isotop n, nichtstabiles Isotop, radioaktives Isotop, Radioisotop

2014-08-01T23:59:59.000Z

110

Distribution of uranium and some selected trace metals in human scalp hair from Balkans  

Science Journals Connector (OSTI)

......Balkan conflict zones, uranium isotopic measurement...blood and urine. Natural uranium (NU) comprises 0...27 % of 238U, whereas depleted uranium (DU), produced in...incidence of several cancers (including childhood......

Z. S. Zunic; S. Tokonami; S. Mishra; H. Arae; R. Kritsananuwat; S. K. Sahoo

2012-11-01T23:59:59.000Z

111

Determination of the theoretical feasibility for the transmutation of europium isotopes from high flux isotope reactor control cylinders  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is a 100 MWth light-water research reactor designed and built in the 1960s primarily for the production of transuranic isotopes. The HFIR is equipped with two concentric cylindrical blade assemblies, known as control cylinders, that are used to control reactor power. These control cylinders, which become highly radioactive from neutron exposure, are periodically replaced as part of the normal operation of the reactor. The highly radioactive region of the control cylinders is composed of europium oxide in an aluminum matrix. The spent HFIR control cylinders have historically been emplaced in the ORNL Waste Area Grouping (WAG) 6. The control cylinders pose a potential radiological hazard due to the long lived radiotoxic europium isotopes {sup 152}Eu, {sup 154}Eu, and {sup 155}Eu. In a 1991 health evaluation of WAG 6 (ERD 1991) it was shown that these cylinders were a major component of the total radioactivity in WAG 6 and posed a potential exposure hazard to the public in some of the postulated assessment scenarios. These health evaluations, though preliminary and conservative in nature, illustrate the incentive to investigate methods for permanent destruction of the europium radionuclides. When the cost of removing the control cylinders from WAG 6, performing chemical separations and irradiating the material in HFIR are factored in, the option of leaving the control cylinders in place for decay must be considered. Other options, such as construction of an engineered barrier around the disposal silos to reduce the chance of migration, should also be analyzed.

Elam, K.R.; Reich, W.J.

1995-09-01T23:59:59.000Z

112

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

113

Temperature Zonal Combustion Reactor for the 15-Nitrogen and 13-Carbon Isotopic Determination of Enriched Biosynthetic Materials  

Science Journals Connector (OSTI)

Temperature Zonal Combustion Reactor for the 15-Nitrogen and 13-Carbon Isotopic Determination of Enriched Biosynthetic Materials ... After the furnace controller had been reset from 250 °C (VHT) to 700 °C (combustion), the sample zone temperature increased at ?50 °C/min, which coincided with a pressure rise from 255 to 363 Torr (over some 8 min). ...

Michael May; John Kuo; Michael Gray; I. Knyazhansky; C. T. Tan

2010-03-31T23:59:59.000Z

114

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

115

Development of Particle Induced Gamma-Ray Emission Methods for Nondestructive Determination of Isotopic Composition of Boron and Its Total Concentration in Natural and Enriched Samples  

Science Journals Connector (OSTI)

Development of Particle Induced Gamma-Ray Emission Methods for Nondestructive Determination of Isotopic Composition of Boron and Its Total Concentration in Natural and Enriched Samples ... The isotopic composition of boron in natural and enriched samples was determined by comparing peak area ratios corresponding to 10B and 11B of samples to natural boric acid standard. ...

Sumit Chhillar; Raghunath Acharya; Suparna Sodaye; Pradeep K. Pujari

2014-10-14T23:59:59.000Z

116

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

117

E-Print Network 3.0 - analysing pb isotopes Sample Search Results  

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

Mobile Pb-isotopes in Proterozoic sedimentary basins as guides for exploration of uranium deposits... isotope ratios and associated trace element concentrations (U, Th and...

118

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.

119

Application of Fission Track Technique for the Analysis of Individual Particles Containing Uranium in Safeguard Swipe Samples  

Science Journals Connector (OSTI)

An effective method for isotope ratio analysis of individual particles containing uranium in safeguard swipe samples was developed by using a fission track (FT) technique combined with thermal ionization mass spectrometry (TIMS). The particles in the sample were directly recovered onto a polycarbonate membrane filter, which was set in a filtration system. After the particle recovery, the filter was dissolved to form a non coated FT detector film containing the particles. Individual particles containing uranium were then identified by the observation of fission tracks created by thermal neutron irradiation. By combining the FT technique with TIMS, isotope ratios of uranium for individual particles in the swipe sample prepared from a uranium standard reference material could be effectively determined.

Konomi T. Esaka; Fumitaka Esaka; Jun Inagawa; Kazunari Iguchi; Chi-Gyu Lee; Satoshi Sakurai; Kazuo Watanabe; Shigekazu Usuda

2004-01-01T23:59:59.000Z

120

Boron isotope geochemistry during diagenesis. Part I. Experimental determination of fractionation during illitization of smectite  

Science Journals Connector (OSTI)

Experiments were performed to measure the isotopic fractionation of boron between illite/smectite (I/S) clay minerals and water as a function of temperature (300° and 350°C) and degree of illitization. Corresponding changes in the oxygen isotopes were monitored as an indication of the approach to equilibrium. The kinetics of the B-isotope exchange follows the mineralogical restructuring of smectite as it recrystallizes to illite. An initial decline in ?11BI/S occurs when the I/S is randomly ordered (RO). The ?11BI/S values reach a plateau during R1 ordering of the I/S, representing a metastable condition. The greatest change in ?11BI/S is observed during long-range (R3) ordering of the I/S when neoformation occurs. Values of ?11BI/S measured on the equilibrium reaction products were used to construct a B-isotope fractionation curve. There is a linear correlation among data from these experiments and 1100°C basaltic melt-fluid fractionation experiments (Hervig and Moore, 2000) that can be extrapolated to include adsorption experiments at 25°C (Palmer et al., 1987). Unlike other stable isotopic systems (e.g., oxygen) there is no mineral-specific fractionation of B-isotopes, but rather a coordination dependence of the fractionation. Under diagenetic conditions B is predominantly in trigonal coordination in fluids but substitutes in tetrahedral sites of silicates. The preference of 10B for tetrahedral bonds is the major fractionating factor of B in silicates.

Lynda B Williams; Richard L Hervig; John R Holloway; Ian Hutcheon

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

A rapid and precise method for sampling and determining the oxygen isotope ratio of atmospheric  

E-Print Network [OSTI]

2002; Accepted 1 March 2002 A quantitative method for cryogenically sampling atmospheric water vapor recovery of a vaporized, known, 18 O water standard to 0.2% precision. Copyright # 2002 John Wiley & Sons differentially affect both the concentration and isotope ratio of atmospheric water vapor.5,8,9 Measurements

Ehleringer, Jim

122

Forward model calculations for determining isotopic compositions of materials used in a radiological dispersal device  

E-Print Network [OSTI]

for the multiple radial-region pin cell was 7 times that of the 2D pin cell. For this reason, the 2D pin cell was used to benchmark the isotopics with data from other reactors. The reactors from which the methodology was benchmarked were Calvert Cliffs Unit #1...

Burk, David Edward

2005-08-29T23:59:59.000Z

123

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),

124

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

125

Uranium dose assessment: a Bayesian approach to the problem of dietary background  

Science Journals Connector (OSTI)

......03-1.05 19.8-22.2 Depleted uranium 0.15-0.37 10-19...material is assumed to be depleted uranium, with an assumed isotopic...uranium lung clearance at a uranium processing plant. Health Phys (1995) 68:661-669......

Tom Little; Guthrie Miller; Raymond Guilmette; Luiz Bertelli

2007-11-01T23:59:59.000Z

126

Isotopic ratios and effective power determined by gamma-ray spectroscopy vs mass spectroscopy for molten salt extraction residues  

SciTech Connect (OSTI)

Impure plutonium metal is routinely processed by molten salt extraction (MSE) to reduce the amount of americium in the metal product. Throughput at various facilities where similar processes are performed has made it essential to evaluate uncertainties and possible discrepancies in the analyses of these difficult MSE materials. In an effort to evaluate the plutonium isotopic ratios and americium concentrations obtained from gamma-ray spectral data analyzed by the computer code GRPAUT, measurements were made on ten MSE salts as received and after pulverization and blending. These results were then compared to the specific powers obtained from isotopic ratios determined by mass spectrometry on these same ten samples. Americium values ranged from a few thousand parts-per-million of total plutonium to greater than 50,000 ppM. Our results indicate a small discrepancy between specific powers as determined by GRPAUT on as received'' vs pulverized and blended MSE salts. The specific powers obtained via GRPAUT on the pulverized salts agree somewhat better with specific powers obtained from the mass spectroscopy data. This work may indicate that a small discrepancy exists in the specific powers by using GRPAUT on heterogeneous, high americium samples. 5 refs., 6 tabs.

Longmire, V.L.; Cremers, T.L.; Sedlacek, W.A.; Long, S.M.; Scarborough, A.M.; Hurd, J.R.

1990-01-01T23:59:59.000Z

127

DETERMINATION OF 234U/238U, 235U/238U AND 236U/238U ISOTOPE RATIOS IN URINE USING SECTOR FIELD INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY  

Science Journals Connector (OSTI)

......aerosols of depleted uranium (DU) exhibit...uranium-related health effects(3-5...et al. Health effects of depleted uranium on exposed...Detection of depleted uranium (DU) in urines...Gulf War. Health Phys. (2004......

Ge Xiao; Robert L. Jones; David Saunders; Kathleen L. Caldwell

2014-02-01T23:59:59.000Z

128

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

129

Isotope correlations for determining the isotopic composition of plutonium produced in research and power reactors using the experimental data obtained by alpha and mass spectrometry  

Science Journals Connector (OSTI)

Correlations have been developed for obtaining the isotopic composition of Pu produced in Indian research (CIRUS, DHRUVA) and power (PHWR) reactors. The experimental data obtained on 238Pu/(239Pu + 240Pu) alpha activity ratio using alpha spectrometry and on 240Pu/239Pu, 241Pu/239Pu, 242Pu/239Pu atom ratios by thermal ionisation mass spectrometry were used for developing isotope correlations.

S.K. Aggarwal; D. Alamelu

2005-01-01T23:59:59.000Z

130

Multiple-Isotope Comparison for Determining Neutrinoless Double-Beta Decay Mechanisms  

E-Print Network [OSTI]

We present a technique for estimating the number of future neutrinoless double-beta decay results using several distinct nuclei to optimize the physics reach of upcoming experiments. We use presently available matrix element calculations and simulated sets of predicted neutrinoless double-beta decay measured rates in multiple isotopes to estimate the required precision and number of experiments to discern the underlying physics governing the mechanism of the process. Our results indicate that 3 (4) experimental results with total uncertainty (statistical, systematic, theoretical) of less than ~20% (~40%) can elucidate the underlying physics. If the theoretical (i.e. matrix element) uncertainty contribution is below ~18%, then 3-4 experimental results of ~20% precision (statistical and systematic) are required. These uncertainty goals can be taken as guidance for the upcoming theoretical and experimental programs.

V. M. Gehman; S. R. Elliott

2007-01-12T23:59:59.000Z

131

ISOTOPE FRACTIONATION Isotopes are atoms whose nuclei contain the same number of protons but a different number of neutrons. The  

E-Print Network [OSTI]

the most abundant isotope appears in the denominator: b R = b E / a E (stable boron isotopes = , [ ] [ ] [ ] [ ]OOCOOC2 OOCOOC2 O 16181616 16181818 CO 18 2 + + = . The isotopic composition, , of a sample, determined____________________________ ISOTOPE FRACTIONATION ____________________________ Isotopes are atoms

Zeebe, Richard E.

132

The use of post detonation analysis of stable isotope ratios to determine the type and production process of the explosive involved  

SciTech Connect (OSTI)

The detonation of a series of explosives was performed in a controlled manner to collect the resulting, solid residue or {open_quotes}soot.{close_quotes} This residue was examined to determine the ratios of the stable carbon, hydrogen, and nitrogen isotopes. The goal of the experiment was to determine if these ratios could be used to indicate, from the post detonation residues, the type and origin of the detonated explosive. The ratios of the stated stable isotopes in the undetonated explosive were also determined. Despite some reservations in the quality of the data resulting from contamination by nonexplosive components, certain trends can be discerned. (1) Carbon isotopes allow aromatic explosives to be distinguished from nonaromatic explosives. This trend seems to carry through the detonation so that the distinction might be made after the fact. (2) The amination process for TATB can be detected through the hydrogen and, to some extent, the nitrogen isotope ratios. Unfortunately, the data are not sufficiently good to determine if this differential carries through the detonation. (3) The relative magnitude and sign of the nitrogen isotope ratio seems to carry through the detonation: some exchange with atmospheric nitrogen is probable. Even though this set of experiments must also be viewed as preliminary, there is a definite indication that certain qualitative characteristics of explosives can be detected after the detonation. This {open_quotes}signature{close_quotes} could have application to both intelligence and counter terrorism.

McGuire, R.R.; Velsko, C.A.; Lee, C.G.; Raber, E.

1993-03-05T23:59:59.000Z

133

MGA: A gamma-ray spectrum analysis code for determining plutonium isotopic abundances. Volume 3, FORTRAN listing of the GA code  

SciTech Connect (OSTI)

Nondestructive measurements of x-ray and gamma-ray emissions can be used to determine the abundances of various actinides in a sample. Volume 1 of this report describes the methods and algorithms we have developed to determine the relative isotopic abundances of actinides in a sample, by analyzing gamma-ray spectra obtained using germanium detector systems. Volume 2 is a guide to using the MGA (Multiple Group Analysis) computer program we have written to perform plutonium isotopic analyses. This report contains a listing of the FORTRAN instructions of the code.

Gunnink, R

1991-09-01T23:59:59.000Z

134

Application of multivariate curve resolution-alternating least squares for the determination of boron isotope ratios by inductively coupled plasma-optical emission spectrometry  

Science Journals Connector (OSTI)

Abstract Multivariate curve resolution-alternating least squares (MCR-ALS) was applied to atomic emission data obtained from inductively coupled plasma-optical emission spectrometry analysis of boron for the quantification of 10B/11B ratios. The determination of isotopic composition of boron is based on the isotopic shift of 10B and 11B in the emission line of 208.957 nm. After recording of the emission spectra in the range of 208.940–208.970 nm, evaluation of isotopic composition of boron containing samples was performed with MCR-ALS algorithm. MCR-ALS was able to resolve the emission spectra of 10B and 11B mixtures. The performance of the proposed methods was tested by determination of 10B/11B ratios in synthetic mixtures and also water samples.

Ehsan Zolfonoun; Seyed Javad Ahmadi

2013-01-01T23:59:59.000Z

135

Validation of a Monte Carlo based depletion methodology via High Flux Isotope Reactor HEU post-irradiation examination measurements  

SciTech Connect (OSTI)

The purpose of this study is to validate a Monte Carlo based depletion methodology by comparing calculated post-irradiation uranium isotopic compositions in the fuel elements of the High Flux Isotope Reactor (HFIR) core to values measured using uranium mass-spectrographic analysis. Three fuel plates were analyzed: two from the outer fuel element (OFE) and one from the inner fuel element (IFE). Fuel plates O-111-8, O-350-1, and I-417-24 from outer fuel elements 5-O and 21-O and inner fuel element 49-I, respectively, were selected for examination. Fuel elements 5-O, 21-O, and 49-1 were loaded into HFIR during cycles 4, 16, and 35, respectively (mid to late 1960s). Approximately one year after each of these elements were irradiated, they were transferred to the High Radiation Level Examination Laboratory (HRLEL) where samples from these fuel plates were sectioned and examined via uranium mass-spectrographic analysis. The isotopic composition of each of the samples was used to determine the atomic percent of the uranium isotopes. A Monte Carlo based depletion computer program, ALEPH, which couples the MCNP and ORIGEN codes, was utilized to calculate the nuclide inventory at the end-of-cycle (EOC). A current ALEPH/MCNP input for HFIR fuel cycle 400 was modified to replicate cycles 4, 16, and 35. The control element withdrawal curves and flux trap loadings were revised, as well as the radial zone boundaries and nuclide concentrations in the MCNP model. The calculated EOC uranium isotopic compositions for the analyzed plates were found to be in good agreement with measurements, which reveals that ALEPH/MCNP can accurately calculate burn-up dependent uranium isotopic concentrations for the HFIR core. The spatial power distribution in HFIR changes significantly as irradiation time increases due to control element movement. Accurate calculation of the end-of-life uranium isotopic inventory is a good indicator that the power distribution variation as a function of space and time is accurately calculated, i.e. an integral check. Hence, the time dependent heat generation source terms needed for reactor core thermal hydraulic analysis, if derived from this methodology, have been shown to be accurate for highly enriched uranium (HEU) fuel.

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL

2010-01-01T23:59:59.000Z

136

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

E-Print Network [OSTI]

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

Varughese, Joseph Verghese

2012-06-07T23:59:59.000Z

137

DETERMINATION OF 234U/238U, 235U/238U AND 236U/238U ISOTOPE RATIOS IN URINE USING SECTOR FIELD INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY  

Science Journals Connector (OSTI)

......exposure of the US population to uranium through measurements of total uranium in urine using inductively...were exposed to aerosols of depleted uranium (DU) exhibit no clinically...effects that might result in cancer and birth defects remain......

Ge Xiao; Robert L. Jones; David Saunders; Kathleen L. Caldwell

2014-02-01T23:59:59.000Z

138

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

139

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

140

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

The extraction of uranium from groundwaters on iron surfaces  

Science Journals Connector (OSTI)

...mechanisms for subsurface remediation. Environ. Sci. Technol...observation of uranium remediation from groundwater onto...barriers geochemistry ground water hydrochemistry ion probe...isotopes radioactive waste remediation sorption spectra transport...

2005-01-01T23:59:59.000Z

142

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

143

Observation of the uranium 235 nuclear magnetic resonance signal (*)  

E-Print Network [OSTI]

before. We report here the first NMR observation of 23SU. The uranium hexafluoride has been chosenL-1017 Observation of the uranium 235 nuclear magnetic resonance signal (*) H. Le Bail, C. Chachaty signal de résonance magnétique nucléaire de l'isotope 235 de l'uranium est présentée. Elle a été

Paris-Sud XI, Université de

144

Geographic determination of coffee beans using multi-element analysis and isotope ratios of boron and strontium  

Science Journals Connector (OSTI)

Abstract This study aims to evaluate the feasibility of using chemical and isotopic compositions of coffee beans to identify their geographic origins. Twenty-one Coffea arabica beans collected from 14 countries in 3 major coffee-producing regions, Africa, America and Asia, were analysed for multi-element of B, Rb, Sr, Ba, Fe, Mn and Zn, as well as isotopic compositions of B and Sr. Our results demonstrate that the geographic origin of coffee beans could be classified based on concentrations of Rb, Sr and Ba. However, the isotope ratios of B and Sr provide more sensitive information for the growth localities. Combined with literature data, this study indicates that B and Sr isotopes are excellent indicators of the origin of coffee beans.

Hou-Chun Liu; Chen-Feng You; Chiou-Yun Chen; Yu-Ching Liu; Ming-Tsung Chung

2014-01-01T23:59:59.000Z

145

Domestic production of medical isotope Mo-99 moves a step closer  

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

Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 moves a step closer Irradiated uranium fuel has been recycled and reused for molybdenum-99...

146

Determination of boron isotope compositions of geological materials by laser ablation MC-ICP-MS using newly designed high sensitivity skimmer and sample cones  

Science Journals Connector (OSTI)

Abstract The effects of addition of nitrogen gas with use of three different combinations of sample and skimmer cones on the performance of LA-MC-ICP-MS for in situ B isotope ratio measurements were investigated in detail. Compared to the standard arrangement (H skimmer cone + standard sample cone), sensitivities of B isotopes were improved by a factor of 2.4 and 3.8 with use of X skimmer cone + standard sampler cone and the X skimmer cone + Jet sample cone, respectively. The best within-run precision (2 s) of 11B/10B was approximately 50 ppm for B4 reference material (B content = 31,400 ?g/g) with use of X skimmer cone + Jet sample cone. It was found that different cone combinations had significant effects on the instrument mass bias, but had little effect on the precisions of B isotope ratios. Addition of nitrogen (2–4 ml/min) in the central channel gas did not improve the sensitivity of B. However, significant wider ion axial distribution profile and more stable mass-bias for B isotope ratios were evident. Under selected optimum conditions, good agreements between the measured ?11B values and the reference values were obtained for the international reference minerals (B4, Dravite, Elbaite, IMMRB1 and Schorl), the NIST SRM 610–612 synthetic soda-lime glasses and the MPI-DING glasses (GOR-128-G, GOR-132-G, and StHs6/80). It was found that for low-B containing (11 ppm and 31 ppm) materials, the precisions (2 s) of 11B/10B can be improved by a factor of 2–10 by using the newly designed X-skimmer cone and Jet sample cone, compared to that of using the standard cones. The international reference mineral Danburite (?11B of ? 14.92 ± 6.77 2SD, n = 32) showed a significant non-uniformity of B isotope ratio distribution. Our first boron isotopic results from standards GSD-1G (?11B: 11.92 ± 1.03, n = 30), GSE-1G (?11B: 1.63 ± 0.32, n = 30), GP-4 (?11B: ? 5.85 ± 1.01, n = 40) and DD-1 (?11B: ? 13.21 ± 0.56, n = 35) showed these materials were fairly homogeneous in boron isotope ratios, making them as good candidates as reference materials. The proposed LA-MC-ICPMS method is suitable for the direct determination of B isotope ratio in a variety of geological materials.

Lin Lin; Zhaochu Hu; Lu Yang; Wen Zhang; Yongsheng Liu; Shan Gao; Shenghong Hu

2014-01-01T23:59:59.000Z

147

Clinical diagnostic indicators of renal and bone damage in rats intramuscularly injected with depleted uranium  

Science Journals Connector (OSTI)

......Abou-Donia, M. Depleted and natural uranium: chemistry...Environ. Health B Crit...et al. Health effects of embedded depleted uranium. Mil. Med...determinations in depleted uranium exposed Gulf...veterans. Health Phys. 77......

S. Fukuda; M. Ikeda; M. Chiba; K. Kaneko

2006-06-01T23:59:59.000Z

148

Development of an on-line isotope dilution laser ablation inductively coupled plasma mass spectrometry (LA–ICP-MS) method for determination of boron in silicon wafers  

Science Journals Connector (OSTI)

A method has been developed based on an on-line isotope dilution technique couple with laser ablation/inductively coupled plasma mass spectrometry (LA–ICP-MS), for the determination of boron in p-type silicon wafers. The laser-ablated sample aerosol was mixed on-line with an enriched boron aerosol supplied continuously using a conventional nebulization system. Upon mixing the two aerosol streams, the isotope ratio of boron changed rapidly and was then recorded by the ICP-MS system for subsequent quantification based on the isotope dilution principle. As an on-line solid analysis method, this system accurately quantifies boron concentrations in silicon wafers without the need for an internal or external solid reference standard material. Using this on-line isotope dilution technique, the limit of detection for boron in silicon wafers is 2.8 × 1015 atoms cm?3. The analytical results obtained using this on-line methodology agree well with those obtained using wet chemical digestion methods for the analysis of p-type silicon wafers containing boron concentrations ranging from 1.0 × 1016 to 9.6 × 1018 atoms cm?3.

Chao-Kai Yang; Po-Hsiang Chi; Yong-Chine Lin; Yuh-Chang Sun; Mo-Hsiung Yang

2010-01-01T23:59:59.000Z

149

Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies  

SciTech Connect (OSTI)

The French Atomic Energy Commission has carried out several experiments including the mini-INCA (INcineration of Actinides) project for the study of minor-actinide transmutation processes in high intensity thermal neutron fluxes, in view of proposing solutions to reduce the radiotoxicity of long-lived nuclear wastes. In this context, a Cm sample enriched in {sup 248}Cm ({approx}97 %) was irradiated in thermal neutron flux at the High Flux Reactor (HFR) of the Laue-Langevin Institute (ILL). This work describes a quadrupole ICP-MS (ICP-QMS) analytical procedure for precise and accurate isotopic composition determination of Cm before sample irradiation and of Cm and Cf after sample irradiation. The factors that affect the accuracy and reproducibility of isotopic ratio measurements by ICP-QMS, such as peak centre correction, detector dead time, mass bias, abundance sensitivity and hydrides formation, instrumental background, and memory blank were carefully evaluated and corrected. Uncertainties of the isotopic ratios, taking into account internal precision of isotope ratio measurements, peak tailing, and hydrides formations ranged from 0.3% to 1.3%. This uncertainties range is quite acceptable for the nuclear data to be used in transmutation studies.

Gourgiotis, A.; Isnard, H.; Aubert, M.; Dupont, E.; AlMahamid, I.; Cassette, P.; Panebianco, S.; Letourneau, A.; Chartier, F.; Tian, G.; Rao, L.; Lukens, W.

2011-02-01T23:59:59.000Z

150

A neutronic feasibility study for LEU conversion of the high flux isotope reactor (HFIR).  

SciTech Connect (OSTI)

A neutronic feasibility study was performed to determine the uranium densities that would be required to convert the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) from HEU (93%) to LEU (<20%)fuel. The LEU core that was studied is the same as the current HEU core, except for potential changes in the design of the fuel plates. The study concludes that conversion of HFIR from HEU to LEU fuel would require an advanced fuel with a uranium density of 6-7 gU/cm{sup 3} in the inner fuel element and 9-10 gU/cm{sup 3} in the outer fuel element to match the cycle length of the HEU core. LEU fuel with uranium density up to 4.8 gU/cm{sup 3} is currently qualified for research reactor use. Modifications in fuel grading and burnable poison distribution are needed to produce an acceptable power distribution.

Mo, S. C.

1998-01-14T23:59:59.000Z

151

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

E-Print Network [OSTI]

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

Samuel-Nakamura, Christine

2013-01-01T23:59:59.000Z

152

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

153

Use of EIChroM`s TRU resin in the determination of americium, plutonium and uranium in air filter and water samples  

SciTech Connect (OSTI)

TRU Resin, an extraction chromatographic material (octyl (phenyl)-N,Ndiisobutylcarbamoyl-methylphosphene oxide (CMPO) dissolved in tributyl phosphate (TBP)) manufactured by EIChroM Industries, was tested for its actinide sorption and desorption characteristics. A study was initiated to demonstrate the effectiveness of extracting plutonium, americium and uranium from water and air filter samples from the Environmental Measurements Laboratory`s Quality Assessment Program (QAP), and the effectiveness of subsequent desorption of one chemical species at a time in order to prepare each of them for a spectrometry. Crossover of plutonium into the americium fraction with the TRU Resin was observed and could not be eliminated while using TRU Resin only. However, prior extraction of plutonium using an anion exchange resin can overcome this problem. A method for the determination of americium is proposed which combines the extraction of plutonium onto Bio-Rad AG 1-X8 anion exchange resin with the extraction of americium using the TRU Resin. This method was tested on three triplicate sets of QAP air filters and two triplicate sets of QAP water samples. The recoveries ranged from 70 to 90 percent, and the results were identical to those obtained by the existing methods. The time required to perform the analysis for americium was shortened from 5 weeks to 1 week.

Berne, A.

1995-12-01T23:59:59.000Z

154

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

155

Experimental determination of dynamic Young's modulus and mechanical damping, and theoretical prediction of dislocation density for depleted uranium-0.75 wt% titanium using the PUCOT  

Science Journals Connector (OSTI)

Dynamic Young's modulus (E) and mechanical damping (Q ?1) measurements were made for three microstructures (?, ? + ?, and ??) of a depleted uranium-0.75 wt% titanium alloy. The...E and Q ...

K. H. Keene; A. Wolfenden; G. M. Ludtka

1988-08-01T23:59:59.000Z

156

Determination of the dynamic Young's modulus, shear modulus, and internal friction as a function of temperature and microstructure in Uranium - 2.4wt% Niobium  

E-Print Network [OSTI]

's ratio o = maximum value of a resulting from an alternating stress 0 1/25 I. INTRODUCTION One of the secondary benefits of the nuclear energy industry is the application of depleted uranium (U-238) by-products as engineering materials for structural... used as storage containers, radiation shields, counter weights and armor piercing projectiles [3]. The most effective tank destroying projectile in the U. S. Army arsenal has a depleted uranium penetrator. To apply these engineering materials better...

Chancellor, Wayne Morrow

2012-06-07T23:59:59.000Z

157

Precise and accurate determination of boron isotope ratios by multiple collector ICP-MS: origin of boron in the Ngawha geothermal system, New Zealand  

Science Journals Connector (OSTI)

A new technique has been developed for the measurement of boron isotope ratios in fluids using a double focusing multiple collector inductively coupled plasma (ICP) mass spectrometer. Sample introduction using a direct injection nebuliser was found to eliminate memory problems that are common where spray chambers are involved. The 4–9% mass bias can be corrected for by bracketing sample measurements with standards. As matrices were found to affect the mass bias all samples must be purified and that sample and standard solutions must be similar. A new purification technique was developed that yields adequately purified samples. Using this technique, it is possible to make rapid measurements (4 min) from samples containing 250 ng B to a precision of ±0.2‰. This analytical technique has been applied to the Ngawha geothermal system in New Zealand in an attempt to determine the source of B in geothermal fluids where the B concentrations can exceed 100 mmol/l. The ?11B values range between ?3.1‰ and ?3.9‰ indicating that no seawater sources are involved and that the elevated B concentrations can only be accounted for by low water/rock ratios with the B being derived from basement greywacke/argillite. The similarity of B isotope ratios for hydrothermal fluids that have been diluted and cooled with groundwaters indicates that isotope fractionation due to adsorption is unlikely to occur in cool geothermal fluids (<40 °C).

J.K. Aggarwal; D. Sheppard; K. Mezger; E. Pernicka

2003-01-01T23:59:59.000Z

158

A general moment NRIXS approach to the determination of equilibrium Fe isotopic fractionation factors: application to goethite and jarosite  

E-Print Network [OSTI]

We measured the reduced partition function ratios for iron isotopes in goethite FeO(OH), potassium-jarosite KFe3(SO4)2(OH)6, and hydronium-jarosite (H3O)Fe3(SO4)2(OH)6, by Nuclear Resonant Inelastic X-Ray Scattering (NRIXS, also known as Nuclear Resonance Vibrational Spectroscopy -NRVS- or Nuclear Inelastic Scattering -NIS) at the Advanced Photon Source. These measurements were made on synthetic minerals enriched in 57Fe. A new method (i.e., the general moment approach) is presented to calculate {\\beta}-factors from the moments of the NRIXS spectrum S(E). The first term in the moment expansion controls iron isotopic fractionation at high temperature and corresponds to the mean force constant of the iron bonds, a quantity that is readily measured and often reported in NRIXS studies.

Dauphas, N; Alp, E E; Golden, D C; Sio, C K; Tissot, F L H; Hu, M; Zhao, J; Gao, L; Morris, R V

2012-01-01T23:59:59.000Z

159

Chemical, multi-isotopic (Li-B-Sr-U-H-O) and thermal characterization of Triassic formation waters from the Paris Basin  

E-Print Network [OSTI]

of around 45 to 50°C. The study of uranium activity ratios for these Triassic formation waters allows us, uranium isotopes, oxygen isotopes, hydrogen isotopes, geothermometry, Trias, Paris Basin 1 hal-00563924,version1-7Feb2011 Author manuscript, published in "Chemical Geology 283, 3-4 (2011) 226-241" DOI : 10

Boyer, Edmond

160

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

E-Print Network [OSTI]

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

Cai, Long

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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.

162

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

163

Measurements of daily urinary uranium excretion in German peacekeeping personnel and residents of the Kosovo region to assess potential intakes of depleted uranium (DU)  

Science Journals Connector (OSTI)

Following the end of the Kosovo conflict, in June 1999, a study was instigated to evaluate whether there was a cause for concern of health risk from depleted uranium (DU) to German peacekeeping personnel serving in the Balkans. In addition, the investigations were extended to residents of Kosovo and southern Serbia, who lived in areas where DU ammunitions were deployed. In order to assess a possible DU intake, both the urinary uranium excretion of volunteer residents and water samples were collected and analysed using inductively coupled plasma-mass spectrometry (ICP-MS). More than 1300 urine samples from peacekeeping personnel and unexposed controls of different genders and age were analysed to determine uranium excretion parameters. The urine measurements for 113 unexposed subjects revealed a daily uranium excretion rate with a geometric mean of 13.9 ng/d (geometric standard deviation (GSD) = 2.17). The analysis of 1228 urine samples from the peacekeeping personnel resulted in a geometric mean of 12.8 ng/d (GSD = 2.60). It follows that both unexposed controls and peacekeeping personnel excreted similar amounts of uranium. Inter-subject variation in uranium excretion was high and no significant age-specific differences were found. The second part of the study monitored 24 h urine samples provided by selected residents of Kosovo and adjacent regions of Serbia compared to controls from Munich, Germany. Total uranium and isotope ratios were measured in order to determine DU content. 235U/238U ratios were within ± 0.3% of the natural value, and 236U/238U was less than 2 × 10? 7, indicating no significant DU in any of the urine samples provided, despite total uranium excretion being relatively high in some cases. Measurements of ground and tap water samples from regions where DU munitions were deployed did not show any contamination with DU, except in one sample. It is concluded that both peacekeeping personnel and residents serving or living in the Balkans, respectively, were not exposed to significant amounts of DU.

U. Oeh; N.D. Priest; P. Roth; K.V. Ragnarsdottir; W.B. Li; V. Höllriegl; M.F. Thirlwall; B. Michalke; A. Giussani; P. Schramel; H.G. Paretzke

2007-01-01T23:59:59.000Z

164

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

165

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

Science Journals Connector (OSTI)

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

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

2007-10-01T23:59:59.000Z

166

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.

167

Isotope Analysis  

Science Journals Connector (OSTI)

Naturally occurring oxygen includes three stable isotopes,16O,17O, and18O, with the relative abundances of 99.763%, 0.0375%, and 0.1995%, respectively. Isotopic analysis does not consider the absolute abundances ...

Tandong Yao; Wusheng Yu; Huabiao Zhao…

2014-08-01T23:59:59.000Z

168

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

169

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

170

Research with fast radioactive isotope beams at RIKEN  

Science Journals Connector (OSTI)

......moments of neutron-rich boron isotopes were measured by the...many neutron-rich isotopes. To exploit fully the...most straightforward determination of the charge distribution...called KISS (KEK isotope separation system......

Tohru Motobayashi; Hiroyoshi Sakurai

2012-01-01T23:59:59.000Z

171

Nuclear isotope thermometry  

Science Journals Connector (OSTI)

We discuss different aspects which might influence temperatures deduced from experimental isotopic yields in the multifragmentation process. It is shown that fluctuations due to the finite size of the system and distortions due to the decay of hot primary fragments conspire to blur the temperature determination in multifragmentation reactions. These facts suggest that caloric curves obtained through isotope thermometers, which were taken as evidence for a first-order phase transition in nuclear matter, should be investigated very carefully.

S. R. Souza, W. P. Tan, R. Donangelo, C. K. Gelbke, W. G. Lynch, and M. B. Tsang

2000-11-10T23:59:59.000Z

172

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,

173

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

174

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

175

Manhattan Project: Early Uranium Research, 1939-1941  

Office of Scientific and Technical Information (OSTI)

Ernest Lawrence, Arthur Compton, Vannevar Bush, and James Conant discuss uranium research, Berkeley, March 29, 1940. EARLY URANIUM RESEARCH Ernest Lawrence, Arthur Compton, Vannevar Bush, and James Conant discuss uranium research, Berkeley, March 29, 1940. EARLY URANIUM RESEARCH (1939-1941) Events > Early Government Support, 1939-1942 Einstein's Letter, 1939 Early Uranium Research, 1939-1941 Piles and Plutonium, 1939-1941 Reorganization and Acceleration, 1940-1941 The MAUD Report, 1941 A Tentative Decision to Build the Bomb, 1941-1942 President Franklin D. Roosevelt responded to the call for government support of uranium research quickly but cautiously. He appointed Lyman J. Briggs, director of the National Bureau of Standards, head of the Advisory Committee on Uranium, which met for the first time on October 21, 1939. The committee, including both civilian and military representation, was to coordinate its activities with Alexander Sachs and look into the current state of research on uranium to recommend an appropriate role for the federal government. In early 1940, only months after the outbreak of war in Europe, the Uranium Committee recommended that the government fund limited research on isotope separation as well as Enrico Fermi's and Leo Szilard's work on fission chain reactions at Columbia University (below).

176

Determining flow, recharge, and vadose zonedrainage in anunconfined aquifer from groundwater strontium isotope measurements, PascoBasin, WA  

SciTech Connect (OSTI)

Strontium isotope compositions (87Sr/86Sr) measured in groundwater samples from 273 wells in the Pasco Basin unconfined aquifer below the Hanford Site show large and systematic variations that provide constraints on groundwater recharge, weathering rates of the aquifer host rocks, communication between unconfined and deeper confined aquifers, and vadose zone-groundwater interaction. The impact of millions of cubic meters of wastewater discharged to the vadose zone (103-105 times higher than ambient drainage) shows up strikingly on maps of groundwater 87Sr/86Sr. Extensive access through the many groundwater monitoring wells at the site allows for an unprecedented opportunity to evaluate the strontium geochemistry of a major aquifer, hosted primarily in unconsolidated sediments, and relate it to both long term properties and recent disturbances. Groundwater 87Sr/86Sr increases systematically from 0.707 to 0.712 from west to east across the Hanford Site, in the general direction of groundwater flow, as a result of addition of Sr from the weathering of aquifer sediments and from diffuse drainage through the vadose zone. The lower 87Sr/86Sr groundwater reflects recharge waters that have acquired Sr from Columbia River Basalts. Based on a steady-state model of Sr reactive transport and drainage, there is an average natural drainage flux of 0-1.4 mm/yr near the western margin of the Hanford Site, and ambient drainage may be up to 30 mm/yr in the center of the site assuming an average bulk rock weathering rate of 10-7.5 g/g/yr.

mjsingleton@lbl.gov

2004-06-29T23:59:59.000Z

177

CX-010117: Categorical Exclusion Determination | Department of Energy  

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

17: Categorical Exclusion Determination 17: Categorical Exclusion Determination CX-010117: Categorical Exclusion Determination Analytical Methods for Radiochemical Measurements CX(s) Applied: B3.6 Date: 03/28/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office This EEC covers analytical methods to be performed in 773-A Labs B-003, B-046, B-138, B-142, B-145, B-154 and B-155. Methods include separation of Alpha-emitting isotopes (Plutonium, Neptunium, Uranium and Americium) for the purpose of measurements, Gamma Sample Preparation and Analysis, Gross Alpha-Beta Determination and Analysis by liquid scintillation, distillation of environmental samples for Tritium analysis, Technicium-99 by extraction chromatography, Strontium-90 analysis, Nickel-59 and -63 analysis, CF-Isotopics Content by Chemical separation.

178

Carbon Isotopes  

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

Atmospheric Trace Gases » Carbon Isotopes Atmospheric Trace Gases » Carbon Isotopes Carbon Isotopes Gateway Pages to Isotopes Data Modern Records of Carbon and Oxygen Isotopes in Atmospheric Carbon Dioxide and Carbon-13 in Methane 800,000 Deuterium Record and Shorter Records of Various Isotopic Species from Ice Cores Carbon-13 13C in CO Measurements from Niwot Ridge, Colorado and Montana de Oro, California (Tyler) 13C in CO2 NOAA/CMDL Flask Network (White and Vaughn) CSIRO GASLAB Flask Network (Allison, Francey, and Krummel) CSIRO in situ measurements at Cape Grim, Tasmania (Francey and Allison) Scripps Institution of Oceanography (Keeling et al.) 13C in CH4 NOAA/CMDL Flask Network (Miller and White) Northern & Southern Hemisphere Sites (Quay and Stutsman) Northern & Southern Hemisphere Sites (Stevens)

179

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

180

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

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181

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

182

Microwave Determination of the Structure of Borine Carbonyl and of the Nuclear Moments of the Stable Boron Isotopes  

Science Journals Connector (OSTI)

From measurements on the J=1?2 and the J=2?3 rotational transitions of borine carbonyl its molecular structure has been determined as follows: dBH=1.194A, dBC=1.540A, dCO=1.131A, and ?HBH = 113°52?. The moments of inertia (which assume h=6.6242×10-27 erg. sec.) in g cm2×10-40 are: 93.4266 for B10H3C12O, 96.9092 for B11H3C12O, 111.4113 for B10D3C12O, and 114.3540 for B11D3C12O. Nuclear quadrupole couplings determined are 3.36±0.10 mc/sec. for B10 and 1.55±0.08 mc/sec. for B11. Approximate values of the nuclear quadrupole moments are 0.06×10-24 cm2 for B10 and 0.03×10-24 cm2 for B11. The nuclear spin of B10 is determined as 3 and that of B11 as 3/2.

Walter Gordy; Harold Ring; Anton B. Burg

1950-06-01T23:59:59.000Z

183

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

SciTech Connect (OSTI)

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

Forsberg, C.W.

1997-02-19T23:59:59.000Z

184

Sampling Plan for Assaying Plates Containing Depleted or Normal Uranium  

SciTech Connect (OSTI)

This paper describes the rationale behind the proposed method for selecting a 'representative' sample of uranium metal plates, portions of which will be destructively assayed at the Y-12 Security Complex. The total inventory of plates is segregated into two populations, one for Material Type 10 (depleted uranium (DU)) and one for Material Type 81 (normal [or natural] uranium (NU)). The plates within each population are further stratified by common dimensions. A spreadsheet gives the collective mass of uranium element (and isotope for DU) and the piece count of all plates within each stratum. These data are summarized in Table 1. All plates are 100% uranium metal, and all but approximately 60% of the NU plates have Kel-F{reg_sign} coating. The book inventory gives an overall U-235 isotopic percentage of 0.22% for the DU plates, ranging from 0.19% to 0.22%. The U-235 ratio of the NU plates is assumed to be 0.71%. As shown in Table 1, the vast majority of the plates are comprised of depleted uranium, so most of the plates will be sampled from the DU population.

Ivan R. Thomas

2011-11-01T23:59:59.000Z

185

Analyzing Nuclear Fuel Cycles from Isotopic Ratios of Waste Products Applicable to Measurement by Accelerator Mass Spectrometry  

SciTech Connect (OSTI)

An extensive study was conducted to determine isotopic ratios of nuclides in spent fuel that may be utilized to reveal historical characteristics of a nuclear reactor cycle. This forensic information is important to determine the origin of unknown nuclear waste. The distribution of isotopes in waste products provides information about a nuclear fuel cycle, even when the isotopes of uranium and plutonium are removed through chemical processing. Several different reactor cycles of the PWR, BWR, CANDU, and LMFBR were simulated for this work with the ORIGEN-ARP and ORIGEN 2.2 codes. The spent fuel nuclide concentrations of these reactors were analyzed to find the most informative isotopic ratios indicative of irradiation cycle length and reactor design. Special focus was given to long-lived and stable fission products that would be present many years after their creation. For such nuclides, mass spectrometry analysis methods often have better detection limits than classic gamma-ray spectroscopy. The isotopic ratios {sup 151}Sm/{sup 146}Sm, {sup 149}Sm/{sup 146}Sm, and {sup 244}Cm/{sup 246}Cm were found to be good indicators of fuel cycle length and are well suited for analysis by accelerator mass spectroscopy.

Biegalski, S R; Whitney, S M; Buchholz, B

2005-08-24T23:59:59.000Z

186

E-Print Network 3.0 - age sm-nd isotopic Sample Search Results  

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

Sm-Nd isotopic study of the Martian meteorite Zagami LARS E. BORG,1, * JENNIFER E... --Uranium-lead, Rb-Sr, and Sm-Nd ... Source: Asmerom, Yemane - Department of Earth and...

187

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

188

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

189

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

190

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

191

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

192

Comparison between IRMS and CRDS methods in the determination of isotopic ratios {sup 2}H/{sup 1}H and {sup 18}O/{sup 16}O in water  

SciTech Connect (OSTI)

Traditionally, the method used for measuring the isotope ratios is the Isotope Ratio Mass Spectrometers (IRMS). A new method has been used to determine the isotopic abundances, the Cavity Ring-Down Spectroscopy (CRDS). It consists of a technique of direct absorption, of high sensitivity, which is based on measuring the absorption ratio, as a function of time, of the light confined in a high finesse optical cavity, instead of the magnitude of light beam absorption. The values of {sup 18}O/{sup 16}O and D/H ratios are determined with respect to international standards VSMOW, GISP and SLAP from the International Atomic Energy Agency (IAEA). In this work, the IRMS and CRDS techniques are compared, verifying that the CRDS technique is promising and has some advantages compared to IRMS. It uses a smaller amount of sample, the isotope measurements are made simultaneously from the steam, reducing the analysis time. It also shows good reproducibility and accuracy, and it does not require a preliminary sample preparation.

Santos, T. H. R.; Zucchi, M. R.; Lemaire, T.; Azevedo, A. E. G. [University Federal of Bahia (UFBA), Institute of Physic, Salvador, Bahia (Brazil)

2013-05-06T23:59:59.000Z

193

Stand Up of Uranium Capability for Swipe Analysis  

SciTech Connect (OSTI)

The INL has established the capability to process and analyze swipe samples to determine if the amount of U and Pu present on equipment and facilities are at the level typical for natural background, to quantify their isotopic composition and to determine if any off-normal isotopic ratio present in the sample is statistically relevant. A previous report detailed this capability for Pu and preliminarily for U; this report describes the measurements and analysis that were performed to demonstrate the INL capability for U. To establish that a piece of equipment is not contaminated with the element to be sampled, a fabric swipe is used to collect a sample of the materials present on the surface. The swipes are then processed and analyzed to determine if Pu and U are present on the sample at levels above what is accepted as natural background and, for the case of U, whether the isotope ratios deviate from the accepted natural background levels. Both the method applied for chemical processing of the swipes to remove and isolate the U and Pu and the method used to analyze the extracts influences the sensitivity and specificity. Over the years various methods have been developed for processing and analyzing these types of samples; the gold standard for these measurements involves a lengthy and complex separation process followed by analysis using thermal ionization mass spectrometry (TIMS). However, this method is expensive and time consuming, thus driving a need for a less complicated and more efficient method that provides the necessary level of sensitivity and specificity. Advances in Inductively Coupled Plasma Mass Spectrometry (ICPMS) over the last decade have enabled analyses of U and Pu that rival that of TIMS. This, coupled with the potential for simplifying the extraction and separation process required for an ICPMS analysis, prompted the INL’s development of methods that provide the analysis of swipes in a timely and efficient manner. U is present in the blank swipe material at nanogram (~2 x 10-9 g) levels for a typical sample, a level easily detected with ICPMS. The abundance of the isotopes ranges over 4 orders of magnitude for the naturally occurring 234U, 235U and 238U and a goal was set to be able to detect the presence of 236U at 6 orders of magnitude lower than the 238U. The 236U measurement is particularly important because the presence of 236U is a strong indicator that the uranium as been in a nuclear reactor. To demonstrate these capabilities the following sample types were used: blank swipe material, blank process reagents, swipe material spiked with a natural abundance U isotope standard, swipe material spiked with an environmental standard (Columbia River sediment), and swipes taken at various locations within the processing laboratories and the INL environment. This report summarizes the method used to extract the U from the swipe material, the ICPMS analyses that demonstrate the limit of detection (LOD) and the limit of quantification (LOQ) for the U isotopes of interest, the precision of the measured isotope ratios and the dependence of precision on the quantity of U present, and the method proposed to determine if an off-normal ratio is statistically relevant.

Matthew Watrous; Anthony Appelhans; Robert Hague; Tracy Houghton; John Olson

2013-11-01T23:59:59.000Z

194

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.

195

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

196

Laser Isotope Enrichment for Medical and Industrial Applications  

SciTech Connect (OSTI)

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

Leonard Bond

2006-07-01T23:59:59.000Z

197

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

198

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

199

Radioactive Kr Isotopes  

Science Journals Connector (OSTI)

A radioactive isotope of 1.1-hour half-life has been produced in krypton by alpha-particle bombardment of Se74, enriched electromagnetically from 0.9 percent to 14.1 percent. Assignment of the isotope is made to Kr77. Aluminum absorption measurements indicate a positron end point of 1.7 Mev. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se74(?,n) reaction is computed as 2.6. The krypton 1.42-day isotope has been produced by an ?,n reaction on electromagnetically enriched Se76. The isotope is located as Kr79 and its half-life confirmed. A positron end point of 1.0 Mev is determined by aluminum absorption measurements. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se76(?,n) reaction is computed to be 50. The cross-section ratio for formation of Kr77 compared to Kr79 by alpha-particle bombardment of selenium is computed as 1.4. The 4.6-hour Kr85 isotope has been produced by a Se(?,n) reaction.

L. L. Woodward; D. A. Mccown; M. L. Pool

1948-10-01T23:59:59.000Z

200

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...

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

202

Preliminary study: isotopic safeguards techniques (IST) LMFBR fuel cycles  

SciTech Connect (OSTI)

This memorandum presents the preliminary results of the effort to investigate the applicability of isotope correlation techniques (ICT), formulated for the LWR system, to the LMFBR fuel cycle. The detailed isotopic compositional changes with burnup developed for the CRBR was utilized as the reference case. This differs from the usual LMFBR design studies in that the core uranium is natural uranium rather than depleted. Nevertheless, the general isotopic behavior should not differ significantly and does allow an initial insight into the expected behavior of isotopic correlations for the LMFBR power systems such as: the U.K. PFR and reprocessing plant; the French Phenix and Superphenix; and the US reference conceptual design studies (CDS) of homogeneous and heterogeneous LMFBR systems as they are developed.

Persiani, P.J.; Kroc, T.K.

1980-06-01T23:59:59.000Z

203

MONTE-CARLO BURNUP CALCULATION UNCERTAINTY QUANTIFICATION AND PROPAGATION DETERMINATION  

SciTech Connect (OSTI)

MONTEBURNS is a Monte-Carlo depletion routine utilizing MCNP and ORIGEN 2.2. Uncertainties exist in the MCNP transport calculation, but this information is not passed to the depletion calculation in ORIGEN or saved. To quantify this transport uncertainty and determine how it propagates between burnup steps, a statistical analysis of a multiple repeated depletion runs is performed. The reactor model chosen is the Oak Ridge Research Reactor (ORR) in a single assembly, infinite lattice configuration. This model was burned for a 25.5 day cycle broken down into three steps. The output isotopics as well as effective multiplication factor (k-effective) were tabulated and histograms were created at each burnup step using the Scott Method to determine the bin width. It was expected that the gram quantities and k-effective histograms would produce normally distributed results since they were produced from a Monte-Carlo routine, but some of results do not. The standard deviation at each burnup step was consistent between fission product isotopes as expected, while the uranium isotopes created some unique results. The variation in the quantity of uranium was small enough that, from the reaction rate MCNP tally, round off error occurred producing a set of repeated results with slight variation. Statistical analyses were performed using the {chi}{sup 2} test against a normal distribution for several isotopes and the k-effective results. While the isotopes failed to reject the null hypothesis of being normally distributed, the {chi}{sup 2} statistic grew through the steps in the k-effective test. The null hypothesis was rejected in the later steps. These results suggest, for a high accuracy solution, MCNP cell material quantities less than 100 grams and greater kcode parameters are needed to minimize uncertainty propagation and minimize round off effects.

Nichols, T.; Sternat, M.; Charlton, W.

2011-05-08T23:59:59.000Z

204

The uranium cylinder assay system for enrichment plant safeguards  

SciTech Connect (OSTI)

Safeguarding sensitive fuel cycle technology such as uranium enrichment is a critical component in preventing the spread of nuclear weapons. A useful tool for the nuclear materials accountancy of such a plant would be an instrument that measured the uranium content of UF{sub 6} cylinders. The Uranium Cylinder Assay System (UCAS) was designed for Japan Nuclear Fuel Limited (JNFL) for use in the Rokkasho Enrichment Plant in Japan for this purpose. It uses total neutron counting to determine uranium mass in UF{sub 6} cylinders given a known enrichment. This paper describes the design of UCAS, which includes features to allow for unattended operation. It can be used on 30B and 48Y cylinders to measure depleted, natural, and enriched uranium. It can also be used to assess the amount of uranium in decommissioned equipment and waste containers. Experimental measurements have been carried out in the laboratory and these are in good agreement with the Monte Carlo modeling results.

Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Rael, Carlos D [Los Alamos National Laboratory; Iwamoto, Tomonori [JNFL; Tamura, Takayuki [JNFL; Aiuchi, Syun [JNFL

2010-01-01T23:59:59.000Z

205

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

206

Estimation of uranium GI absorption fractions for children and adults  

Science Journals Connector (OSTI)

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

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

2011-03-01T23:59:59.000Z

207

Adsorption study for uranium in Rocky Flats groundwater  

SciTech Connect (OSTI)

Six adsorbents were studied to determine their effectiveness in removing uranium in Rocky Flats groundwater. The bench column and batch (Kd) tests showed that uranium can be removed (>99.9%) by four adsorbents. Bone Charcoal (R1O22); F-1 Alumina (granular activated alumina); BIOFIX (immobilized biological agent); SOPBPLUS (mixed metal oxide); Filtrasorb 300 (granular activated carbon); and Zeolite (clinoptilolite).

Laul, J.C.; Rupert, M.C. [EG and G Rocky Flats, Inc., Golden, CO (United States); Harris, M.J. [Science Applications International Corp., Golden, CO (United States); Duran, A. [Environmental Protection Agency, Denver, CO (United States)

1995-01-01T23:59:59.000Z

208

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...

209

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,

210

Isotope studies in photosynthesis  

Science Journals Connector (OSTI)

Isotope studies in photosynthesis ... Examines the use of isotopic oxygen, hydrogen, carbon, and phosphorus in the study of photosynthesis. ...

J. A. Bassham; A. A. Benson; Melvin Calvin

1953-01-01T23:59:59.000Z

211

US developments in technology for uranium enrichment  

SciTech Connect (OSTI)

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

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

1982-01-01T23:59:59.000Z

212

Isotope Effects on the Enzymatic and Nonenzymatic Reactions of Chorismate  

Science Journals Connector (OSTI)

The isotopic composition of the latter was determined by isotope ratio mass spectrometry, enabling determination of isotope effects at the mechanistically interesting key positions O7, C1, and C9. ... Heavy atom isotope effects on the nonenzymatic Claisen rearrangement to give prephenate, 18k1 and 13k1, were determined at 60 °C as described for the enzymatic reactions and calculated from the following relationship: where xk1 is the apparent isotope effect, expressed as a ratio of the rate constants for the light and heavy (x) isotopes. ...

S. Kirk Wright; Michael S. DeClue; Ajay Mandal; Lac Lee; Olaf Wiest; W. Wallace Cleland; Donald Hilvert

2005-08-27T23:59:59.000Z

213

DUSCOBS - a depleted-uranium silicate backfill for transport, storage, and disposal of spent nuclear fuel  

SciTech Connect (OSTI)

A Depleted Uranium Silicate COntainer Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside storage, transport, and repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill all void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (1) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (2) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. In addition, the DUSCOBS improves the integrity of the package by acting as a packing material and ensures criticality control for the package during SNF storage and transport. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments.

Forsberg, C.W.; Pope, R.B.; Ashline, R.C.; DeHart, M.D.; Childs, K.W.; Tang, J.S.

1995-11-30T23:59:59.000Z

214

Determination of oxygen self-diffusion in akermanite, anorthite, diopside, and spinel: Implications for oxygen isotopic anomalies and the thermal histories of Ca-Al-rich inclusions  

SciTech Connect (OSTI)

Oxygen self-diffusion coefficients have been measured for three natural diopsidic clinopyroxenes, a natural anorthite, a synthetic magnesium aluminate spinel, and a synthetic akermanite for oxygen fugacities ranging from the NNO to IW buffers. The oxygen diffusion data are used to evaluate the effects of three different types of thermal histories upon the oxygen isotopic compositions of minerals found in Type B Ca-Al-rich inclusions (CAIBs) in carbonaceous chondrites: (1) gas-solid exchange during isothermal heating, (2) gas-solid exchange as a function of cooling rate subsequent to instantaneous heating, and (3) isotopic exchange with a gaseous reservoir during partial melting and recrystallization. With the assumptions that the mineral compositions within a CAIB were uniformly enriched in [sup 16]O prior to any thermal processing, that effective diffusion dimensions may be estimated from observed grain sizes, and that diffusion in diopside is similar to that in fassaitic clinopyroxene, none of the above scenarios can reproduce the relative oxygen isotopic anomalies observed in CAIBs without improbably long or unrealistically intense thermal histories relative to current theoretical models of nebular evolution. The failure of these simple models, coupled with recent observations of disturbed magnesium isotopic abundances and correlated petrographic features in anorthite and melilite indicative of alteration and recrystallization, suggests that the oxygen isotopic compositions of these phases may have also been modified by alteration and recrystallization possibly interspersed with multiple melting events. Because the modal abundance of spinel remains relatively constant for plausible melting scenarios, and its relatively sluggish diffusion kinetics prevent substantial equilibration, Mg-Al spinel is the most reliable indicator of the oxygen isotopic composition of precursor material which formed Type B CAIs.

Ryerson, F.J. (Lawrence Livermore National Lab., CA (United States)); McKeegan, K.D. (Univ. of California, Los Angeles, CA (United States))

1994-09-01T23:59:59.000Z

215

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

Science Journals Connector (OSTI)

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

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

1971-02-01T23:59:59.000Z

216

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

SciTech Connect (OSTI)

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

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

2009-11-01T23:59:59.000Z

217

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

Science Journals Connector (OSTI)

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

I. Kuleff; P. Petrov; K. Kostadinov

1980-01-01T23:59:59.000Z

218

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

219

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

Science Journals Connector (OSTI)

Uranium oxide particles were dispersed into the environment from a factory in Colonie (NY, USA) by prevailing winds during the 1960s and '70s. Uranium concentrations and isotope ratios from bulk soil samples have been accurately measured using inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) without the need for analyte separation chemistry. The natural range of uranium concentrations in the Colonie soils has been estimated as 0.7–2.1 ?g g? 1, with a weighted geometric mean of 1.05 ?g g? 1; the contaminated soil samples comprise uranium up to 500 ± 40 ?g g? 1. A plot of 236U/238U against 235U/238U isotope ratios describes a mixing line between natural uranium and depleted uranium (DU) in bulk soil samples; scatter from this line can be accounted for by heterogeneity in the DU particulate. The end-member of DU compositions aggregated in these bulk samples comprises (2.05 ± 0.06) × 10? 3 235U/238U, (3.2 ± 0.1) × 10? 5 236U/238U, and (7.1 ± 0.3) × 10? 6 234U/238U. The analytical method is sensitive to as little as 50 ng g? 1 DU mixed with the natural uranium occurring in these soils. The contamination footprint has been mapped northward from site, and at least one third of the uranium in a soil sample from the surface 5 cm, collected 5.1 km NNW of the site, is DU. The distribution of contamination within the surface soil horizon follows a trend of exponential decrease with depth, which can be approximated by a simple diffusion model. Bioturbation by earthworms can account for dispersal of contaminant from the soil surface, in the form of primary uranium oxide particulates, and uranyl species that are adsorbed to organic matter. Considering this distribution, the total mass of uranium contamination emitted from the factory is estimated to be c. 4.8 tonnes.

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

2009-01-01T23:59:59.000Z

220

RIB Production with Photofission of Uranium  

E-Print Network [OSTI]

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

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

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

222

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

SciTech Connect (OSTI)

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

NONE

1995-07-05T23:59:59.000Z

223

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

224

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...

225

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...

226

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....

227

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...

228

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

229

U.S. Department of Energy Categorical Exclusion Determination Form  

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

Analytical Methods for Radiochemical Measurements Analytical Methods for Radiochemical Measurements Savannah River Site Aiken/Aiken/South Carolina This EEC covers analytical methods to be performed in 773-A Labs B-003, B-046, B-138, B-142, B-145, B-154 and B-155. Methods include separation of Alpha-emitting isotopes (Plutonium, Neptunium, Uranium, and Americium) for the purpose of measurements, Gamma Sample Preparation and analysis, Gross Alpha Beta Determination and Analysis by liquid scintillation, distillation of environmental samples for Tritium analysis, Technitium-99 by extraction chromatography, Strontium-90 analysis, Nickel-59 and -63 analysis, CF-Isotopics Content by Chemical separation. This EEC details a project to measure the distribution of selected lanthanide and actinide elements between HDEHP (bis-(2-

230

U.S. Department of Energy Categorical Exclusion Determination Form  

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

Analytical Methods for Radiochemical Measurements Analytical Methods for Radiochemical Measurements Savannah River Site Aiken/Aiken/South Carolina This EEC covers analytical methods to be performed in 773-A Labs B-003, B-046, B-138, B-142, B-145, B-154 and B-155. Methods include separation of Alpha-emitting isotopes (Plutonium, Neptunium, Uranium and Americium) for the purpose of measurements, Gamma Sample Preparation and Analysis, Gross Alpha-Beta Determination and Analysis by liquid scintillation, distillation of environmental samples for Tritium analysis, Technicium-99 by extraction chromatography, Strontium-90 analysis, Nickel-59 and -63 analysis, CF-Isotopics Content by Chemical separation. Rev.1: Extended the Activity End date from 2/28/2013 to 3/28/15 B3.6 - Small-scale research and development, laboratory operations, and pilot projects

231

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

232

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

233

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

234

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.

235

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

E-Print Network [OSTI]

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

Kim, C K; Park, H D

2002-01-01T23:59:59.000Z

236

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

237

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

Office of Scientific and Technical Information (OSTI)

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

238

EIS-0198: Uranium Mill Tailings Remedial Action Groundwater Project |  

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

198: Uranium Mill Tailings Remedial Action Groundwater Project 198: Uranium Mill Tailings Remedial Action Groundwater Project EIS-0198: Uranium Mill Tailings Remedial Action Groundwater Project SUMMARY This EIS assesses the potential programmatic impacts of conducting the Ground Water Project, provides a method for determining the site-specific ground water compliance strategies, and provides data and information that can be used to prepare site-specific environmental impacts analyses more efficiently. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 28, 1997 EIS-0198: Record of Decision Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project (April 1997) December 1, 1996 EIS-0198: Programmatic Environmental Impact Statement Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project

239

Analytical electron microscopy characterization of uranium-contaminated soils from the Fernald Site, FY1993 report  

SciTech Connect (OSTI)

A combination of optical microscopy, scanning electron microscopy with backscattered electron detection (SEM/BSE), and analytical electron microscopy (AEM) is being used to determine the nature of uranium in soils from the Fernald Environmental Management Project. The information gained from these studies is being used to develop and test remediation technologies. Investigations using SEM have shown that uranium is contained within particles that are typically 1 to 100 {mu}m in diameter. Further analysis with AEM has shown that these uranium-rich regions are made up of discrete uranium-bearing phases. The distribution of these uranium phases was found to be inhomogeneous at the microscopic level.

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

1994-10-01T23:59:59.000Z

240

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

242

CX-005504: Categorical Exclusion Determination | Department of Energy  

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

504: Categorical Exclusion Determination 504: Categorical Exclusion Determination CX-005504: Categorical Exclusion Determination Analytical Methods for Radiochemical Measurements CX(s) Applied: B3.6 Date: 02/24/2011 Location(s): Aiken, South Carolina Office(s): Environmental Management, Savannah River Operations Office This EEC covers analytical methods to be performed in 773-A Labs B-003, B-046, B-138, B-142, B-145, B-154 and B-155. Methods include separation of Alpha emitting isotopes (Plutonium, Neptunium, Uranium and Americium) for the purpose of measurements, Gamma Sample Preparation and analysis, Gross Alpha Beta Determination and Analysis by liquid scintillation, distillation of environmental samples for Tritium analysis, Technicium-99 by extraction chromatography, Strontium-90 analysis, Nickel 59 and 63 analysis,

243

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

244

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...

245

lead-isotope dating  

Science Journals Connector (OSTI)

lead-isotope dating, lead-lead dating, lead-isotope age measurement, lead-lead age measurement ? Blei-Isotopen(-Alters)bestimmung, f, Blei-Isotopen-Datierung

2014-08-01T23:59:59.000Z

246

isotopic ratio | EMSL  

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

isotopic ratio isotopic ratio Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

247

Electromagnetic Isotope Separation Lab (EMIS) | ORNL  

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

Electromagnetic Isotope Separation Lab Electromagnetic Isotope Separation Lab May 30, 2013 ORNL established the Stable Isotope Enrichment Laboratory (SIEL) as part of a project funded by the DOE Office of Science, Nuclear Physics Program to develop a modernized electromagnetic isotope separator (EMIS), optimized for separation of a wide range of stable isotopes. The SIEL is located in the Building 6010 Shield Test Station, space formerly allocated to the Oak Ridge Electron Linear Accelerator, on the main campus of ORNL. ORNL staff have designed and built a nominal 10 mA ion current EMIS (sum of all isotopes at the collector) in the SIEL. This EMIS is currently being tested to determine basic performance metrics such as throughput and enrichment factor per pass. This EMIS unit and space will be used to

248

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

249

Uranium speciation in glass corrosion layers: An XAFS study  

SciTech Connect (OSTI)

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

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

1997-12-31T23:59:59.000Z

250

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

251

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

252

Evaluation of Uranium Measurements in Water by Various Methods - 13571  

SciTech Connect (OSTI)

In December 2000, EPA amended its drinking water regulations for radionuclides by adding a Maximum Contaminant Level (MCL) for uranium (so called MCL Rule)[1] of 30 micrograms per liter (?g/L). The MCL Rule also included MCL goals of zero for uranium and other radionuclides. Many radioactively contaminated sites must test uranium in wastewater and groundwater to comply with the MCL rule as well as local publicly owned treatment works discharge limitations. This paper addresses the relative sensitivity, accuracy, precision, cost and comparability of two EPA-approved methods for detection of total uranium: inductively plasma/mass spectrometry (ICP-MS) and alpha spectrometry. Both methods are capable of measuring the individual uranium isotopes U-234, U- 235, and U-238 and both methods have been deemed acceptable by EPA. However, the U-238 is by far the primary contributor to the mass-based ICP-MS measurement, especially for naturally-occurring uranium, which contains 99.2745% U-238. An evaluation shall be performed relative to the regulatory requirement promulgated by EPA in December 2000. Data will be garnered from various client sample results measured by ALS Laboratory in Fort Collins, CO. Data shall include method detection limits (MDL), minimum detectable activities (MDA), means and trends in laboratory control sample results, performance evaluation data for all methods, and replicate results. In addition, a comparison will be made of sample analyses results obtained from both alpha spectrometry and the screening method Kinetic Phosphorescence Analysis (KPA) performed at the U.S. Army Corps of Engineers (USACE) FUSRAP Maywood Laboratory (UFML). Many uranium measurements occur in laboratories that only perform radiological analysis. This work is important because it shows that uranium can be measured in radiological as well as stable chemistry laboratories and it provides several criteria as a basis for comparison of two uranium test methods. This data will indicate which test method is the most accurate and most cost effective. This paper provides a benefit to Formerly Utilized Sites Remedial Action Program (FUSRAP) and other Department of Defense (DOD) programs that may be performing uranium measurements. (authors)

Tucker, Brian J. [Shaw Environmental and Infrastructure Group, 150 Royall Street, Canton, MA (United States)] [Shaw Environmental and Infrastructure Group, 150 Royall Street, Canton, MA (United States); Workman, Stephen M. [ALS Laboratory Group, Environmental Division, 225 Commerce Drive, Fort Collins, CO 80524 (United States)] [ALS Laboratory Group, Environmental Division, 225 Commerce Drive, Fort Collins, CO 80524 (United States)

2013-07-01T23:59:59.000Z

253

Qualitative sims analysis of28,29,30Si isotope concentration in silicon using a Tof.Sims-5 Setup  

Science Journals Connector (OSTI)

The possibility of quantitative SIMS determination of28-30Si isotope concentrations in silicon samples using a TOF.SIMS-5 spectrometer is shown. Th e isotope...28Si isotope (deposited on natural Si substrates), a...

M. N. Drozdov; Yu. N. Drozdov…

2010-01-01T23:59:59.000Z

254

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

255

Isotope Science and Production  

E-Print Network [OSTI]

of Energy National Isotope Program http://www.nuclear.energy.gov/isotopes/nelsotopes2a.html Isotopes for Environmental Science Isotopes produced at Los Alamos National Laboratory are used as environmental tracers change and its effects. Los Alamos National Laboratory can produce Si-32 needed for oceanographic tracing

256

Stable isotope studies  

SciTech Connect (OSTI)

The research has been in four general areas: (1) correlation of isotope effects with molecular forces and molecular structures, (2) correlation of zero-point energy and its isotope effects with molecular structure and molecular forces, (3) vapor pressure isotope effects, and (4) fractionation of stable isotopes. 73 refs, 38 figs, 29 tabs.

Ishida, T.

1992-01-01T23:59:59.000Z

257

Nuclear Proliferation Using Laser Isotope Separation -- Verification Options  

SciTech Connect (OSTI)

Two levels of nonproliferation verification exist. Signatories of the basic agreements under the Nuclear Non-proliferation Treaty (NPT) agree to open their nuclear sites to inspection by the IAEA. A more detailed and intrusive level was developed following the determination that Iraq had begun a nuclear weapons development program that was not detected by the original level of verification methods. This level, referred to as 93+2 and detailed in model protocol INFCIRC/540, allows the IAEA to do environmental monitoring of non-declared facilities that are suspected of containing proliferation activity, and possibly further inspections, as well as allowing more detailed inspections of declared sites. 56 countries have signed a Strengthened Safeguards Systems Additional Protocol as of 16 July 2001. These additional inspections can be done on the instigation of the IAEA itself, or after requests by other parties to the NPT, based on information that they have collected. Since information able to cause suspicion of proliferation could arrive at any country, it is important that countries have procedures in place that will assist them in making decisions related to these inspections. Furthermore, IAEA inspection resources are limited, and therefore care needs to be taken to make best use of these resources. Most of the nonproliferation verification inspections may be concentrated on establishing that diversion of nuclear materials is not occurring, but some fraction will be related to determining if undeclared sites have nuclear materials production taking place within them. Of these, most suspicions will likely be related to the major existing technologies for uranium enrichment and reprocessing for plutonium extraction, as it would seem most likely that nations attempting proliferation would use tested means of producing nuclear materials. However, as technology continues to advance and new methods of enrichment and reprocessing are developed, inspection-related procedures will need to be adapted to keep up with them. In order to make 93+2 inspections more useful, a systematic way of finding clues to nuclear proliferation would be useful. Also, to cope with the possible use of newer technology for proliferation, the list of clues might need to be expanded. This paper discusses the development and recognition of such clues. It concentrates on laser isotope separation (LIS) as a new proliferation technology, and uses Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) as an example of LIS that is well known.

Erickson, S A

2001-10-15T23:59:59.000Z

258

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

259

Uranium (VI) solubility in carbonate-free ERDA-6 brine  

SciTech Connect (OSTI)

When present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is the most prevalent actinide component by mass, with about 647 metric tons to be placed in the repository. Therefore, the chemistry of uranium, and especially its solubility in the WIPP conditions, needs to be well determined. Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pC{sub H+} values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brines and a lack of amphotericity. At the expected pC{sub H+} in the WIPP ({approx} 9.5), measured uranium solubility approached 10{sup -7} M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines.

Lucchini, Jean-francois [Los Alamos National Laboratory; Khaing, Hnin [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

260

In situ boron isotope measurements of natural geological materials by LA-MC-ICP-MS  

Science Journals Connector (OSTI)

There are two main methods to determine boron isotopic composition. One is the solution method, in which boron is purified after the samples are dissolved in solution and the boron isotope ratios are determined b...

KeJun Hou; YanHe Li; YingKai Xiao; Feng Liu; YouRong Tian

2010-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

262

High Flux Isotope Reactor (HFIR) | Nuclear Science | ORNL  

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

High Flux Isotope Reactor High Flux Isotope Reactor May 30, 2013 The High Flux Isotope Reactor (HFIR) first achieved criticality on August 25, 1965, and achieved full power in August 1966. It is a versatile 85-MW isotope production, research, and test reactor with the capability and facilities for performing a wide variety of irradiation experiments and a world-class neutron scattering science program. HFIR is a beryllium-reflected, light water-cooled and moderated flux-trap type swimming pool reactor that uses highly enriched uranium-235 as fuel. HFIR typically operates seven 23-to-27 day cycles per year. Irradiation facility capabilities include Flux trap positions: Peak thermal flux of 2.5X1015 n/cm2/s with similar epithermal and fast fluxes (Highest thermal flux available in the

263

Neutron scattering length of lithium and boron and their isotopes  

Science Journals Connector (OSTI)

Coherent neutron scattering lengths and free cross sections were measured in order to determine the spin dependent scattering lengths of the isotopes of Li and B.

L. Koester; K. Knopf; W. Waschkowski

1983-01-01T23:59:59.000Z

264

Neutron capture cross sections for neutron-rich isotopes  

Science Journals Connector (OSTI)

Average continuum (Hauser-Feshbach) and resonance (Breit-Wigner) neutron capture rates for neutron-rich isotopes, determined on the basis of...

B. Leist; W. Ziegert; M. Wiescher…

1985-01-01T23:59:59.000Z

265

Isotopic Analysis- Fluid At Roosevelt Hot Springs Geothermal...  

Open Energy Info (EERE)

and literature review of the Roosevelt Hot Springs Geothermal Area. Notes Stable isotope analysis of thermal fluids determined meteoric origin primarily from the Mineral...

266

UW Cosmogenic Isotopes Al-Be 1 EXTRACTION OF Al & Be FROM QUARTZ FOR ISOTOPIC ANALYSIS  

E-Print Network [OSTI]

UW Cosmogenic Isotopes Al-Be 1 EXTRACTION OF Al & Be FROM QUARTZ FOR ISOTOPIC ANALYSIS Summary This method is used to separate Al and Be for AMS analysis from pure quartz samples. After adding Be carrier, quartz is dissolved in HF. The solution is sub-sampled for determination of total Al content, then dried

Stone, John

267

Secretarial Determination Pursuant to USEC Privatization Act...  

Energy Savers [EERE]

Pursuant to USEC Privatization Act for the Sale or Transfer of Low-Enriched Uranium Secretarial Determination Pursuant to USEC Privatization Act for the Sale or Transfer of...

268

CX-004808: Categorical Exclusion Determination | Department of...  

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

Exclusion Determination Flowsheet Evaluation for the Neutralization of High Aluminum ? Low Uranium Used Nuclear Fuel (UNF) Solution CX(s) Applied: B3.6 Date: 11292010...

269

Selection of Isotopes and Elements for Fuel Cycle Analysis  

SciTech Connect (OSTI)

Fuel cycle system analysis simulations examine how the selection among fuel cycle options for reactors, fuel, separation, and waste management impact uranium ore utilization, waste masses and volumes, radiotoxicity, heat to geologic repositories, isotope-dependent proliferation resistance measures, and so forth. Previously, such simulations have tended to track only a few actinide and fission product isotopes, those that have been identified as important to a few criteria from the standpoint of recycled material or waste, taken as a whole. After accounting for such isotopes, the residual mass is often characterized as “fission product other” or “actinide other”. However, detailed assessment of separation and waste management options now require identification of key isotopes and residual mass for Group 1A/2A elements (Rb, Cs, Sr, Ba), inert gases (Kr, Xe), halogens (Br, I), lanthanides, transition metals, transuranic (TRU), uranium, actinide decay products. The paper explains the rationale for a list of 81 isotopes and chemical elements to better support separation and waste management assessment in dynamic system analysis models such as Verifiable Fuel Cycle Simulation (VISION)

Steven J. Piet

2009-04-01T23:59:59.000Z

270

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...

271

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

272

Laser Ablation Molecular Isotopic Spectrometry: Parameter influence on boron isotope measurements  

Science Journals Connector (OSTI)

Laser Ablation Molecular Isotopic Spectrometry (LAMIS) was recently reported for optical isotopic analysis of condensed samples in ambient air and at ambient pressure. LAMIS utilizes molecular emissions which exhibit larger isotopic spectral shits than in atomic transitions. For boron monoxide 10BO and 11BO, the isotopic shifts extend from 114 cm?1 (0.74 nm) to 145–238 cm?1 (5–8 nm) at the B 2?+ (v = 0) ? X 2?+ (v = 2) and A 2?i (v = 0) ? X 2?+ (v = 3) transitions, respectively. These molecular isotopic shifts are over two orders of magnitude larger than the maximum isotopic shift of approximately 0.6 cm?1 in atomic boron. This paper describes how boron isotope abundance can be quantitatively determined using LAMIS and how atomic, ionic, and molecular optical emission develops in a plasma emanating from laser ablation of solid samples with various boron isotopic composition. We demonstrate that requirements for spectral resolution of the measurement system can be significantly relaxed when the isotopic abundance ratio is determined using chemometric analysis of spectra. Sensitivity can be improved by using a second slightly delayed laser pulse arriving into an expanding plume created by the first ablation pulse.

Xianglei Mao; Alexander A. Bol'shakov; Dale L. Perry; Osman Sorkhabi; Richard E. Russo

2011-01-01T23:59:59.000Z

273

Isotopically pumped isotopic CF4 laser  

Science Journals Connector (OSTI)

Single-mode optical pumping of CF4 to generate 16-µm frequencies has been extended to include the isotopic species 12CF4,...

Eckhardt, Roger; Telle, John; Haynes, Larry

1982-01-01T23:59:59.000Z

274

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

275

Inhalation class for depleted uranium at a major uranium applications facility  

SciTech Connect (OSTI)

A primary concern in determining internal dose from inhalation of radioactive material is the half-time of the material within the human body. Inhalation classes have been established by the ICRP for radioactive materials with half-times of a few days (Class D), several weeks (Class W), or periods up to one year (Class Y). Bioassay data at a facility using large quantities of depleted uranium have been collected for several years. These data have been analyzed to estimate the first order decay constant. From the decay constant, the half-time for retention (biological half-life) is determined. This half-time is used to identify the inhalation class for depleted uranium and its oxides. The data presented demonstrate that the retention half-time for depleted uranium and its oxides ranges from about 7 d to about 6 wk, depending on the quantity of material inhaled and the subject`s metabolism. This shows that the correct inhalation class for depleted uranium is Class W.

Barg, D.C.; Grewing, H.L. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1996-06-01T23:59:59.000Z

276

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.

277

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

278

I ISOTOPES  

Office of Legacy Management (LM)

mixed sample is analyzed in order to avoid the problem. 2.3 Analysis of Samples The U-238 content of soil was determined by gamma spectral analysis of the daughter product Th-234...

279

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

280

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

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

282

Measurement and Analysis of Fission Rates in a Spherical Mockup of Uranium and Polyethylene  

E-Print Network [OSTI]

Measurements of the reaction rate distribution were carried out using two kinds of Plate Micro Fission Chamber(PMFC). The first is a depleted uranium chamber and the second an enriched uranium chamber. The material in the depleted uranium chamber is strictly the same as the material in the uranium assembly. With the equation solution to conduct the isotope contribution correction, the fission rate of 238U and 235U were obtained from the fission rate of depleted uranium and enriched uranium. And then, the fission count of 238U and 235U in an individual uranium shell was obtained. In this work, MCNP5 and continuous energy cross sections ENDF/BV.0 were used for the analysis of fission rate distribution and fission count. The calculated results were compared with the experimental ones. The calculation of fission rate of DU and EU were found to agree with the measured ones within 10% except at the positions in polyethylene region and the two positions near the outer surface. Beacause the fission chamber was not co...

Tong-Hua, Zhu; Xin-Xin, Lu; Rong, Liu; Zi-Jie, Han; Li, Jiang; Mei, Wang

2013-01-01T23:59:59.000Z

283

Characteristics of Uranium and Its Compounds  

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

Symbol: U Symbol: U Atomic Number: 92 (protons in nucleus) Atomic Weight: 238 (naturally occurring) Radioactive Properties of Key Uranium Isotopes Isotope Half-Life Natural Abundance ( % ) Specific Activity (Ci/g) Decay Energy (MeV) U-234 248,000 yr 0.0055 6.2 × 10 -3 4.8 α U-235 700 million yr 0.72 2.2 × 10 -6 4. 4 α 0.21 γ U-238 4.5 billion yr 99.27 3.3 × 10 -7 4.2 α Specific activity is the activity in curies (Ci) or becquerels (Bq) per gram of material. For reference, 1 Ci is 3.7 × 10 10 disintegrations per second, and the specific activity of radium-226 is about 1 Ci/g. To convert specific activity expressed in curies to standard international units, multiply by 3.7 × 10 10 Bq/Ci. The decay energy represents the average energy associated with the dominant decay modes, which is essentially the kinetic energy of the alpha

284

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...

285

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...

286

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)....

287

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...

288

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

Science Journals Connector (OSTI)

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

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

1995-01-01T23:59:59.000Z

289

Isotope Geothermometry | Open Energy Information  

Open Energy Info (EERE)

Isotope Geothermometry Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotope Geothermometry Details Activities (0) Areas (0) Regions (0)...

290

Marathon/Vitro to seek uranium  

Science Journals Connector (OSTI)

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

1967-03-13T23:59:59.000Z

291

Final Uranium Leasing Program Programmatic Environmental Impact...  

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...

292

THE ISOTOPES OF AMERICIUM  

E-Print Network [OSTI]

spectrographic analysis of the americium samples. It is a48 J'---_I" THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.Elements THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.

Street, K.; Ghiroso, A.; Seaborg, G.T.

2008-01-01T23:59:59.000Z

293

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

294

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27T23:59:59.000Z

295

Electrochemical Isotope Effect and Lithium Isotope Separation  

Science Journals Connector (OSTI)

In a series of papers Kavner et al. (2005, 2008)(2, 3) derive an equation predicting isotopic fractionation due to an electrochemical isotope effect (?EIE), defined by the ratio of electron transfer rates (k?/k) for isotopically substituted species (prime for heavy isotopologues): where v, ?G, kB, T, m, ?eq, QP/QR, z, e, and ? denote collision frequency, activation free energy, Boltzmann’s constant, temperature, mass in motion, equilibrium fractionation factor, partition function ratio of abundant isotopologues of product (P) and reactant (R), number of electrons, charge of electron, and Marcus reorganization energy, respectively. ... fractional isotope evolution of Zn isotopes during an electroplating process which stepwise removes most of the Zn from the aq. ...

Jay R. Black; Grant Umeda; Bruce Dunn; William F. McDonough; Abby Kavner

2009-07-06T23:59:59.000Z

296

Perchlorate Isotope Forensics  

Science Journals Connector (OSTI)

In this study, comprehensive stable isotope analyses (37Cl/35Cl and 18O/17O/16O) of perchlorate from known synthetic and natural sources reveal systematic differences in isotopic characteristics that are related to the formation mechanisms. ... ?37Cl and ?18O are measures of mass-dependent fractionation of Cl and O isotopes by normal physical, chemical, or biological processes. ...

John Karl Böhlke; Neil C. Sturchio; Baohua Gu; Juske Horita; Gilbert M. Brown; W. Andrew Jackson; Jacimaria Batista; Paul B. Hatzinger

2005-11-04T23:59:59.000Z

297

Isotope Effect in Adhesion  

Science Journals Connector (OSTI)

Isotope Effect in Adhesion ... We report the first observation of an isotope effect in adhesion. ... The results are presented in Figure 3. Clearly, the isotope effect is very significant, substantiating the proposed H-bonding interactions between the PDMS and Si?OH(D) surfaces. ...

Gun Young Choi; Abraham Ulman; Yitzhak Shnidman; Walter Zurawsky; Cathy Fleischer

2000-05-25T23:59:59.000Z

298

Engineering analysis of low enriched uranium fuel using improved zirconium hydride cross sections  

E-Print Network [OSTI]

for the change out of the existing high enriched uranium fuel to this high-burnup, low enriched uranium fuel design. The codes MCNP and Monteburns were utilized for the neutronic analysis while the code PARET was used to determine fuel and cladding temperatures...

Candalino, Robert Wilcox

2006-10-30T23:59:59.000Z

299

Indirect NMR detection of 235U in gaseous uranium hexafluoride National Center for Physics, P.O. Box MG-6, Bucharest, Romania  

E-Print Network [OSTI]

L-493 Indirect NMR detection of 235U in gaseous uranium hexafluoride I. Ursu National Center provide a method to determine the presence of 23 5U in liquid uranium hexafluoride. The first proposed on physical properties of uranium hexa- fluoride molecule in the gas phase it is possible to predict [9

Paris-Sud XI, Université de

300

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

Standard specification for uranium oxides with a 235U content of less than 5 % for dissolution prior to conversion to nuclear-grade uranium dioxide  

E-Print Network [OSTI]

1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a 235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753. 1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller. 1.3 The scope of this specification does not comprehensively cover all provisions for prevent...

American Society for Testing and Materials. Philadelphia

2005-01-01T23:59:59.000Z

302

ARM - Measurement - Isotope ratio  

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

govMeasurementsIsotope ratio govMeasurementsIsotope ratio ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Isotope ratio Ratio of stable isotope concentrations. Categories Atmospheric Carbon, Atmospheric State Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. ARM Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Field Campaign Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Datastreams FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes

303

Magnesium Isotopes in Halo Stars  

E-Print Network [OSTI]

We have determined Mg isotope ratios in halo field dwarfs and giants in the globular cluster M71 based on high S/N high spectral resolution (R = 10$^5$) Keck HIRES spectra. Unlike previous claims of an important contribution from intermediate-mass AGB stars to the Galactic halo, we find that our $^{26}$Mg/$^{24}$Mg ratios can be explained by massive stars.

Jorge Melendez; Judith G. Cohen

2007-08-29T23:59:59.000Z

304

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

305

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

306

Isotope Program Transportation | Department of Energy  

Office of Environmental Management (EM)

Isotope Program Transportation Isotope Program Transportation Isotope Program Transportation More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project...

307

Micro-Scale Heterogeneity in Biogeochemical Uranium Cycling  

SciTech Connect (OSTI)

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

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

2009-06-04T23:59:59.000Z

308

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

309

Engineering assessment of inactive uranium mill tailings  

SciTech Connect (OSTI)

The Grand Junction site has been reevaluated in order to revise the October 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Grand Junction, Colorado. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 1.9 million tons of tailings at the Grand Junction site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The eight alternative actions presented herein range from millsite and off-site decontamination with the addition of 3 m of stabilization cover material (Option I), to removal of the tailings to remote disposal sites and decontamination of the tailings site (Options II through VIII). Cost estimates for the eight options range from about $10,200,000 for stabilization in-place to about $39,500,000 for disposal in the DeBeque area, at a distance of about 35 mi, using transportation by rail. If transportation to DeBeque were by truck, the cost estimated to be about $41,900,000. Three principal alternatives for the reprocessing of the Grand Junction tailings were examined: (a) heap leaching; (b) treatment at an existing mill; and (c) reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $200/lb by heap leach and $150/lb by conventional plant processes. The spot market price for uranium was $25/lb early in 1981. Therefore, reprocessing the tailings for uranium recovery appears not to be economically attractive.

Not Available

1981-07-01T23:59:59.000Z

310

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

311

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

E-Print Network [OSTI]

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

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

312

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

313

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

314

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

315

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

316

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

317

Metrological Determination of Natural Radioactive Isotopes {sup 226}Ra, {sup 228}Ra and {sup 210}Pb by Means of Ge Detector  

SciTech Connect (OSTI)

A metrological method to determine the activity per mass unity (activity concentration) of {sup 226}Ra and {sup 210}Pb ({sup 238}U decay series) and {sup 228}Ra ({sup 232}Th series) by gamma-ray spectrometers based on hyper-pure coaxial germanium detector was developed. In the soil the {sup 22}Ra (half-life = 1600 years) exhibits the same level of radioactivity as {sup 238}U (half-life 4.5x10{sup 9} years) because of a natural phenomenon called secular equilibrium. {sup 226}Ra decays into {sup 222}Rn (half-life = 3.8 days), a radioactive inert gas. After several days, the {sup 222}Rn naturally decays to {sup 218}Po (half-life = 3 minutes), where finally {sup 210}Pb (half-life = 22 years) is produced. The metrological capability of high-resolution gamma-ray spectrometry for naturally occurring radionuclides at environmental levels is showed, with emphasis on the use of 2 mL standard sources volume in a glass ampoule. Source preparation and calibration procedures are described. Radionuclide standards in an activity range of 10 to 250 Bq/g were produced which can be applied in a variety of environmental sample analysis (water, plant material, sediment, etc.). Uncertainties for {sup 226}Ra and {sup 210}Pb around 3% (k = 1) were obtained.

Almeida, Maria Candida M. de; Delgado, Jose U.; Poledna, Roberto; Oliveira, Estela Maria de; Silva, Ronaldo L. da [Laboratorio Nacional de Metrologia das Radiacoes Ionizantes, Instituto de Radioprotecao e Dosimetria, Comissao Nacional de Energia Nuclear(SEMRA/LNMRI/IRD/CNEN) Av. Salvador Allende s/n, Recreio, Rio de Janeiro, CEP 22780-160, RJ (Brazil)

2008-08-07T23:59:59.000Z

318

National Mining Association Experimental Determination  

E-Print Network [OSTI]

National Mining Association Experimental Determination of Radon Fluxes over Water #12;Introduction research funded by the National Mining Association (NMA) regarding radon fluxes from water surfaces surfaces at uranium recovery operations are insignificant and approximate background soil fluxes for most

319

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

320

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

Domestic production of medical isotope Mo-99 moves a step closer  

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

Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 Domestic production of medical isotope Mo-99 moves a step closer Irradiated uranium fuel has been recycled and reused for molybdenum-99 (Mo-99) production, with virtually no losses in Mo-99 yields or uranium recovery. May 13, 2013 From left, Los Alamos scientists Roy Copping, Sean Reilly, and Daniel Rios. Copping examines the Buchi Multivapor P-12 Evaporator, and Reilly and Rios are at the Agilent Technologies Cary 60 UV-Vis Spectrometer. From left, Los Alamos scientists Sean Reilly, Roy Copping, and Daniel Rios. Sean is looking at the Buchi Multivapor P-12 Evaporator, and Roy and Daniel are at the Agilent Technologies Cary 60 UV-Vis Spectrometer. Contact Nancy Ambrosiano Communications Office (505) 667-0471

322

Analysis of a Uranium Solution for Evaluating the Total Number of Fissions in the JCO Criticality Accident in Tokai-mura  

Science Journals Connector (OSTI)

......LMRI, France). Determination of the concentration...spectrometer) for isotope ratio measurements...obtain an accurate isotope ratio without any fractionation...calibrating the mass bias. Determination of boron and metal impurities......

Gunzo Uchiyama; Kazuo Watanabe; Masakatsu Miyauchi; Yoshihiro Togashi; Yoshinori Nakahara; Hiroyuki Fukaya; Jun Inagawa; Daiske Suzuki; Takashi Sonoda; Nobuaki Kohno; Katsubumi Gunji; Mitsuo Ito; Takeshi Sato

2001-09-01T23:59:59.000Z

323

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method is described for yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus. 2 figures.

Maya, J.

1991-06-18T23:59:59.000Z

324

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus.

Maya, Jakob (Brookline, MA)

1991-01-01T23:59:59.000Z

325

Precise and accurate determination of boron concentration in silicate rocks by direct isotope dilution ICP-MS: Insights into the B budget of the mantle and B behavior in magmatic systems  

Science Journals Connector (OSTI)

Abstract We determine the bulk boron concentration of silicate rocks using a new method that does not require sample evaporation. After spiking (10B enriched NIST SRM 952) and HF attack, the rock solution is directly aspirated into the ICP-MS, and B concentration is determined by isotopic dilution. This technique is applied to samples with B contents in the range of 0.1–30 ppm. The very low blank (boron during mantle melting and enrichment processes (i.e. metasomatism), and to estimate the primitive mantle B content (0.26 ± 0.04 ppm), while the lava data allows us to quantify B loss due to magmatic degassing (between 10 and 30%), using the composition of a primitive melt inclusion as the reference for an initial magma composition. Our knowledge of the degassing history of the samples allows us to quantify loss during lava emplacement and cooling (4–10%), continuous open-system degassing (10%) and shallow closed-system degassing (5–8%). Our results indicate that 1) B abundances of ocean island basalts are ca. 60–75% less than estimates based on elements with similar incompatibility (e.g., Nb and Ta), 2) this deficiency could reflect source depletion and/or magmatic degassing, and 3) magma degassing accounts for less than half of the inferred boron anomaly seen on primitive mantle-normalized patterns, implying that the mantle sources of ocean island basalts must be depleted in boron. The robust technique presented in this study could provide useful constraints on boron distribution within the Earth's mantle as well as on its behavior in magmatic systems.

G. Menard; I. Vlastélic; D.A. Ionov; E.F. Rose-Koga; J.-L. Piro; C. Pin

2013-01-01T23:59:59.000Z

326

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

327

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,

328

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

329

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

330

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...

331

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...

332

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...

333

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...

334

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...

335

Stable isotope enrichment  

SciTech Connect (OSTI)

Brian Egle is working to increase the nation's capacity to produce stable isotopes for use including medicine, industry and national security.

Egle, Brian

2014-07-14T23:59:59.000Z

336

EMSL - isotopic ratio  

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

isotopic-ratio en Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. http:www.emsl.pnl.govemslwebpublicationsmagnesium-behavior-and-structural-def...

337

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Determination of No Adverse Material Impact Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup March 2, 2012 - 4:30pm Addthis WASHINGTON, D.C. - Secretary of Energy Steven Chu announced today that the Department of Energy has issued a determination and market impact analysis authorizing uranium transfers to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, through the third quarter of calendar year 2013. The Determination finds that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. The determination authorizes the Department to conduct transfers on a quarterly basis, with no more than 450 metric tons (MTU) of natural uranium

338

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Determination of No Adverse Material Impact Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup March 2, 2011 - 12:00am Addthis WASHINGTON, D.C. - Secretary of Energy Steven Chu announced today that the Department of Energy has issued a determination and market impact analysis authorizing uranium transfers to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, through the third quarter of calendar year 2013. The Determination finds that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. The determination authorizes the Department to conduct transfers on a quarterly basis, with no more than 450 metric tons (MTU) of natural uranium

339

Long-term corrosion and leaching of depleted uranium (DU) in soil  

Science Journals Connector (OSTI)

Corrosion and leaching of depleted uranium (DU) was investigated for 3 years...238U was determined in the effluents by inductively coupled plasma mass spectrometry. In addition, 235U was measured occasionally to ...

W. Schimmack; U. Gerstmann; W. Schultz; G. Geipel

2007-08-01T23:59:59.000Z

340

Microstructure of depleted uranium under uniaxial strain conditions  

Science Journals Connector (OSTI)

Uranium samples of two different purities were used for spall strength measurements. Samples of depleted uranium were taken from very high purity material (38 ppm of carbon) and from material containing 280 ppm carbon. Experimental conditions were chosen to effectively arrest the microstructural damage at two places in the development to full spall separation. Samples were soft recovered and characterized with respect to the microstructure and the form of damage. This allowed determination of the dependence of spall mechanisms on stress level stress state and sample purity. This information is used in developing a model to predict the mode of fracture.

A. K. Zurek; J. D. Embury; A. Kelly; W. R. Thissell; R. L. Gustavsen; J. E. Vorthman; R. S. Hixson

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

342

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

343

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

344

Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors  

SciTech Connect (OSTI)

The ANSI/ANS 8.12 standard was first approved in July 1978. At that time, this edition was applicable to operations with plutonium-uranium oxide (MOX) fuel mixtures outside reactors and was limited to subcritical limits for homogeneous systems. The next major revision, ANSI/ANS-8.12-1987, included the addition of subcritical limits for heterogeneous systems. The standard was subsequently reaffirmed in February 1993. During late 1990s, substantial work was done by the ANS 8.12 Standard Working Group to re-examine the technical data presented in the standard using the latest codes and cross section sets. Calculations performed showed good agreement with the values published in the standard. This effort resulted in the reaffirmation of the standard in March 2002. The standard is currently in a maintenance mode. After 2002, activities included discussions to determine the future direction of the standard and to follow the MOX standard development by the International Standard Organization (ISO). In 2007, the Working Group decided to revise the standard to extend the areas of applicability by providing a wider range of subcritical data. The intent is to cover a wider domain of MOX fuel fabrication and operations. It was also decided to follow the ISO MOX standard specifications (related to MOX density and isotopics) and develop a new set of subcritical limits for homogeneous systems. This has resulted in the submittal (and subsequent approval) of the project initiation notification system form (PINS) in 2007.

Biswas, D; Mennerdahl, D

2008-06-23T23:59:59.000Z

345

Isotope hydrology of catchment basins: lithogenic and cosmogenic isotopic systems  

SciTech Connect (OSTI)

A variety of physical processes affect solute concentrations within catchment waters. The isotopic compositions of the solutes can indicate which processes have determined the observed concentrations. These processes together constitute the physical history of the water. Many solutes in natural waters are derived from the interaction between the water and the rock and/or soil within the system - these are termed `lithogenic` solutes. The isotopic compositions of these solutes provide information regarding rock-water interactions. Many other solutes have their isotopic compositions determined both within and outside of the catchment - i.e., in addition to being derived from catchment rock and soil, they are solutes that are also transported into the catchment. Important members of this group include solutes that have isotopic compositions produced by atomic particle interactions with other nuclides. The source of the atomic particles can be cosmic radiation (producing `cosmogenic` nuclides in the atmosphere and land surface), anthropogenic nuclear reactions (producing `thermonuclear` nuclides), or radioactive and fission decay of naturally-occurring elements, principally {sup 238}U (producing `in-situ` lithogenic nuclides in the deep subsurface). Current language usage often combines all of the atomic particle-produced nuclides under the heading `cosmogenic nuclides`, and for simplicity we will often follow that usage here, although always indicating which variety is being discussed. This paper addresses the processes that affect the lithogenic and cosmogenic solute concentrations in catchment waters, and how the isotopic compositions of the solutes can be used in integrative ways to identify these processes, thereby revealing the physical history of the water within a catchment system. The concept of a `system` is important in catchment hydrology. A catchment is the smallest landscape unit that can both participate in all of the aspects of the hydrologic cycle and also be treated as a mostly closed system for mass balance considerations. It is the near closure of the system that permits well- constrained chemical mass balance calculations to be made. These calculations generally focus of lithogenic solutes, and therefore in our discussions of lithogenic nuclides in the paper, the concept of chemical mass balance in a nearly dosed system will play an important role. Examination of the isotopic compositions of solutes provides a better understanding of the variety of processes controlling mass balance. It is with this approach that we examined the variety of processes occurring within the catchment system, such as weathering and soil production, generation of stormflow and streamflow (hydrograph separation), movement of soil pore water, groundwater flow, and the overall processes involved with basinal water balance. In this paper, the term `nuclide` will be used when referring to a nuclear species that contains a particular number of protons and neutrons. The term is not specific to any element. The term `isotope` will be used to distinguish nuclear species of a given element (atoms with the same number of protons). That is to say, there are many nuclides in nature - for example, {sup 36}Cl, {sup 87}Sr, {sup 238}U; the element has four naturally-occurring isotopes - {sup 87}Sr, and {sup 88}Sr. This paper will first discuss the general principles that underlie the study of lithogenic and cosmogenic nuclides in hydrology, and provide references to some of the more important studies applying these principles and nuclides. We then turn in the second section to a discussion of their specific applications in catchment- scale systems. The final section of this paper discusses new directions in the application of lithogenic and cosmogenic nuclides to catchment hydrology, with some thoughts concerning possible applications that still remain unexplored.

Nimz, G. J., LLNL

1998-06-01T23:59:59.000Z

346

Celebrating The Isotope  

Science Journals Connector (OSTI)

Celebrating The Isotope ... The notion of isotopes and the rest of Soddy’s lifetime body of work on radioactivity, the group displacement laws, the social responsibility of scientists, and the environment have had a profound effect on science and society. ...

GEORGE B. KAUFFMAN

2013-12-02T23:59:59.000Z

347

Isotope - based Quantum Information  

E-Print Network [OSTI]

This paper is brief review of three aspects of the isotope - based quantum information: computation, teleportation and cryptography. Our results demonstrate not only that entanglement exists in elementary excitation of isotope - mixed solids but also it can be used for quantum information processing.

Vladimir G. Plekhanov

2009-09-04T23:59:59.000Z

348

Influence of depleted uranium on hepatic cholesterol metabolism in apolipoprotein e-deficient mice  

Science Journals Connector (OSTI)

Depleted uranium (DU) is uranium with a lower content of the fissile isotope U-235 than natural uranium. It is a radioelement and a waste product from the enrichment process of natural uranium. Because of its very high density, it is used in the civil industry and for military purposes. DU exposure can affect many vital systems in the human body, because in addition to being weakly radioactive, uranium is a toxic metal. It should be emphasized that, to be exposed to radiation from DU, you have to eat, drink, or breathe it, or get it on your skin. This particular study is focusing on the health effects of DU for the cholesterol metabolism. Previous studies on the same issue have shown that the cholesterol metabolism was modulated at molecular level in the liver of laboratory rodents contaminated for nine months with DU. However, this modulation was not correlated with some effects at organs or body levels. It was therefore decided to use a “pathological model” such as hypercholesterolemic apolipoprotein E-deficient laboratory mice in order to try to clarify the situation. The purpose of the present study is to assess the effects of a chronic ingestion (during 3 months) of a low level DU-supplemented water (20 mg L?1) on the above mentioned mice in order to determine a possible contamination effect. Afterwards the cholesterol metabolism was studied in the liver especially focused on the gene expressions of cholesterol-catabolising enzymes (CYP7A1, CYP27A1 and CYP7B1), as well as those of associated nuclear receptors (LXR?, FXR, PPAR?, and SREBP 2). In addition, mRNA levels of other enzymes of interest were measured (ACAT 2, as well as \\{HMGCoA\\} Reductase and \\{HMGCoA\\} Synthase). The gene expression study was completed with SRB1 and LDLr, apolipoproteins A1 and B and membrane transporters ABC A1, ABC G5. The major effect induced by a low level of DU contamination in apo-E deficient mice was a decrease in hepatic gene expression of the enzyme CYP7B1 (?23%) and nuclear receptors LXR? (?24%), RXR (?32%), HNF4? (?21%) when compared to unexposed ones. These modifications on cholesterol metabolism did not lead to increased disturbances that are specific for apolipoprotein E-deficient mice, suggesting that chronic DU exposure did not worsen the pathology in this experimental model. In conclusion, the results of this study indicate that even for a sensitive pathologic model the exposure to a low dose of DU has no relevant impact. The results confirm the results of our first study carried out on healthy laboratory rodents where a sub-chronic contamination with low dose DU did not affect in vivo the metabolism of cholesterol.

M. Souidi; R. Racine; L. Grandcolas; S. Grison; J. Stefani; P. Gourmelon; P. Lestaevel

2012-01-01T23:59:59.000Z

349

Secretarial Determination Pursuant to the USEC Privatization Act  

Broader source: Energy.gov [DOE]

Secretary Steven Chu determined that such sales or transfers will not have an adverse material impact on the domestic uranium mining, conversion, or enrichment industries.

350

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

351

Isotopic Analysis- Fluid At Sierra Valley Geothermal Area (1990) | Open  

Open Energy Info (EERE)

Isotopic Analysis- Fluid At Sierra Valley Geothermal Area (1990) Isotopic Analysis- Fluid At Sierra Valley Geothermal Area (1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Sierra Valley Geothermal Area (1990) Exploration Activity Details Location Sierra Valley Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine the recharge of the area Notes Hydrogen and oxygen isotope data on waters of Coso thermal and nonthermal waters were studied. Hydrogen and oxygen isotopes do not uniquely define the recharge area for the Coso geothermal system but strongly suggest Sierran recharge with perhaps some local recharge. References Whelan, J. A. (1 September 1990) Water geochemistry study of

352

Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal Area  

Open Energy Info (EERE)

Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal Area Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal Area (1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal Area (1990) Exploration Activity Details Location Indian Valley Hot Springs Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine the recharge of the area Notes Hydrogen and oxygen isotope data on waters of Coso thermal and nonthermal waters were studied. Hydrogen and oxygen isotopes do not uniquely define the recharge area for the Coso geothermal system but strongly suggest Sierran recharge with perhaps some local recharge. References

353

Isotope Geochemistry Of Minerals And Fluids From Newberry Volcano, Oregon |  

Open Energy Info (EERE)

Isotope Geochemistry Of Minerals And Fluids From Newberry Volcano, Oregon Isotope Geochemistry Of Minerals And Fluids From Newberry Volcano, Oregon Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: Isotope Geochemistry Of Minerals And Fluids From Newberry Volcano, Oregon Details Activities (2) Areas (1) Regions (0) Abstract: Isotopic compositions were determined for hydrothermal quartz, calcite, and siderite from core samples of the Newberry 2 drill hole, Oregon. The Δ15O values for these minerals decrease with increasing temperatures. The values indicate that these hydrothermal minerals precipitated in isotopic equilibrium with water currently present in the reservoirs. The Δ18O values of quartz and calcite from the andesite and basalt flows (700-932 m) have isotopic values which require that the equilibrated water Δ18O values increase slightly (- 11.3 to -9.2‰) with

354

Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990) | Open  

Open Energy Info (EERE)

Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990) Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990) Exploration Activity Details Location Rose Valley Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine the recharge of the area Notes Hydrogen and oxygen isotope data on waters of Coso thermal and nonthermal waters were studied. Hydrogen and oxygen isotopes do not uniquely define the recharge area for the Coso geothermal system but strongly suggest Sierran recharge with perhaps some local recharge. References Whelan, J. A. (1 September 1990) Water geochemistry study of

355

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.

356

X-ray spectroscopic studies of microbial transformations of uranium  

SciTech Connect (OSTI)

Several uranium compounds U-metal ({alpha}-phase), UO{sub 2}, U{sub 3}O{sub 8}, {gamma}-UO{sub 3}, uranyl acetate, uranyl nitrate, uranyl sulfate, aqueous and solid forms of 1:1 U:citric acid and 1:1:2 U:Fe:citric acid mixed-metal complexes, and a precipitate obtained by photodegradation of the U-citrate complex were characterized by X-ray spectroscopy using XPS, XANES, and EXAFS. XPS and XANES were used to determine U oxidation states. Spectral shifts were obtained at the U 4f{sub 7/2} and U 4f{sub 5/2} binding energies using XPS, and at the uranium M{sub V} absorption edge using XANES. The magnitude of the energy shift with oxidation state, and the ability to detect mixed-valent forms make these ideal techniques for determining uranium speciation in wastes subjected to bacterial action. The structure of 1:1 U:citric acid complex in both the aqueous and solid state was determined by EXAFS analysis of hexavalent uranium at the L{sub M} absorption edge and suggests the presence of a binuclear complex with a (UO{sub 2}){sub 2}({mu},{eta}{sup 2} {minus}citrato){sub 2} core with a U-U distance of 5.2 {angstrom}. The influence of Fe on the structure of U-citrate complex was determined by EXAFS and the presence of a binuclear mixed-metal citrate complex with a U-Fe distance of 4.8 {angstrom} was confirmed. The precipitate resulting from photodegradation of U-citrate complex was identified as an amorphous form of uranium trioxide by XPS and EXAS.

Dodge, C.J.; Francis, A.J. [Brookhaven National Lab., Upton, NY (United States); Clayton, C.R. [SUNY at Stony Brook, Stony Brook, NY (United States). Dept. of Materials Science and Engineering

1995-10-01T23:59:59.000Z

357

Experimental Plan: Uranium Stabilization Through Polyphosphate Injection 300 Area Uranium Plume Treatability Demonstration Project  

SciTech Connect (OSTI)

This Test Plan describes a laboratory-testing program to be performed at Pacific Northwest National Laboratory (PNNL) in support of the 300-FF-5 Feasibility Study (FS). The objective of the proposed treatability test is to evaluate the efficacy of using polyphosphate injections to treat uranium contaminated groundwater in situ. This study will be used to: (1) Develop implementation cost estimates; (2) Identify implementation challenges; and (3) Investigate the technology's ability to meet remedial objectives These activities will be conducted in parallel with a limited field investigation, which is currently underway to more accurately define the vertical extent of uranium in the vadose zone, and in the capillary fringe zone laterally throughout the plume. The treatability test will establish the viability of the method and, along with characterization data from the limited field investigation, will provide the means for determining how best to implement the technology in the field. By conducting the treatability work in parallel with the ongoing Limited Field Investigation, the resulting Feasibility Study (FS) will provide proven, site-specific information for evaluating polyphosphate addition and selecting a suitable remediation strategy for the uranium plume within the FS time frame at an overall cost savings.

Wellman, Dawn M.; Fruchter, Jonathan S.; Vermeul, Vince R.

2006-09-20T23:59:59.000Z

358

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

359

Hydrogen isotope fractionation in freshwater algae: I. Variations among lipids and species  

E-Print Network [OSTI]

Hydrogen isotope fractionation in freshwater algae: I. Variations among lipids and species Zhaohui in media containing different concentrations of deuterium. The hydrogen isotopic ratios of lipids that lipid dD values can be used to determine water dD values, hydrogen isotope fractionation was found

Sachs, Julian P.

360

2012 Domestic Uranium Production Report  

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

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

362

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 

363

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

364

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

365

The Next Generation Safeguards Initiative s High-Purity Uranium-233 Preservation Effort  

SciTech Connect (OSTI)

High-purity 233U serves as a crucial reference material for accurately quantifying and characterizing uranium. The most accurate analytical results which can be obtained only with high-purity 233U certified reference material (CRM) are required when used to confirm compliance with international safeguards obligations and international nonproliferation agreements. The U.S. supply of 233U CRM is almost depleted, and existing domestic stocks of this synthetic isotope are scheduled to be down-blended for disposition with depleted uranium beginning in 2015. Down blending batches of high-purity 233U will permanently eliminate the value of this material as a CRM. Furthermore, no replacement 233U stocks are expected to be produced in the future due to a lack of operating production capability and the high cost of replacing such capability. Therefore, preserving select batches of high-purity 233U is of great value and will assist in retaining current analytical capabilities for uranium-bearing samples. Any organization placing a priority on accurate results of uranium analyses, or on the confirmation of trace uranium in environmental samples, has a vested interest in preserving this material. This paper describes the need for high-purity 233U, the consequences organizations and agencies face if this material is not preserved, and the progress and future plans for preserving select batches of the purest 233U materials from disposition. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

Krichinsky, Alan M [ORNL] [ORNL; Bostick, Debra A [ORNL] [ORNL; Giaquinto, Joseph [ORNL] [ORNL; Bayne, Charles [Hazelwood Services and Manufacturing] [Hazelwood Services and Manufacturing; Goldberg, Dr. Steven A. [DOE SC - Chicago Office] [DOE SC - Chicago Office; Humphrey, Dr. Marc [U.S. Department of Energy, NNSA] [U.S. Department of Energy, NNSA; Hutcheon, Dr. Ian D. [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Sobolev, Taissa [U.S. Department of Energy, NNSA] [U.S. Department of Energy, NNSA

2012-01-01T23:59:59.000Z

366

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

367

Performance and safety parameters for the high flux isotope reactor  

SciTech Connect (OSTI)

A Monte Carlo depletion model for the High Flux Isotope Reactor (HFIR) Cycle 400 and its use in calculating parameters of relevance to the reactor performance and safety during the reactor cycle are presented in this paper. This depletion model was developed to serve as a reference for the design of a low-enriched uranium (LEU) fuel for an ongoing study to convert HFIR from high-enriched uranium (HEU) to LEU fuel; both HEU and LEU depletion models use the same methodology and ENDF/B-VII nuclear data as discussed in this paper. The calculated HFIR Cycle 400 parameters, which are compared with measurement data from critical experiments performed at HFIR, data included in the HFIR Safety Analysis Report (SAR), or data reported by previous calculations, provide a basis for verification or updating of the corresponding SAR data. (authors)

Ilas, G. [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831-6172 (United States); Primm III, T. [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831-6172 (United States); Primm Consulting, LLC, 945 Laurel Hill Road, Knoxville, TN 37923 (United States)

2012-07-01T23:59:59.000Z

368

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

369

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

370

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

371

Investigation of Neutron Characteristics for Salt Blanket Models; Integral Fission Cross Section Measurements of Neptunium, Plutonium, Americium and Curium Isotopes  

E-Print Network [OSTI]

Neutron characteristics of salt blanket micromodels containing mixtures of sodium, zirconium and uranium sulphides were measured on FKBN-2M, BIGR and MAKET installations. The effective fission cross sections of neptunium, plutonium, americium and curium isotopes were measured on the neutron spectra formed by micromodels.

E. Fomushkin

2002-08-30T23:59:59.000Z

372

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

373

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

374

Atomic vapor laser isotope separation at Lawrence Livermore National Laboratory: a status report  

SciTech Connect (OSTI)

The field of laser induced chemistry began in earnest early in the 1970's with the initiation of major efforts in laser isotope separation (LIS) of uranium. Though many specialized, small-scale photochemical and diagnostic applications have been identified and evaluated experimentally, and continue to show promise, currently the only high payoff, large-scale applications remain LIS of special elements. Aspects of the physical scaling, technology status and economic basis of uranium LIS are examined with special emphasis on the effort at LLNL.

Davis, J.I.

1980-01-01T23:59:59.000Z

375

Comparison of NTIMS and ICP-OES methods for the determination of boron concentrations in natural fresh and saline waters  

Science Journals Connector (OSTI)

Determination of B concentrations in natural fresh and ... the NTIMS (Negative Thermal Ionization Mass Spectrometry) isotope dilution technique which is virtually unaffected by such effects. NTIMS isotope diluti...

S. Barth

1997-07-01T23:59:59.000Z

376

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"

377

ISOTOPES IN WATER  

Science Journals Connector (OSTI)

The study of isotopic prosies ha two different though related basic aims: an understanding of the way in which the water cycle in linked to alterations in climate, and how the carbon cycle has responded to the...

W. GEORGE DARLING; ADRIAN H. BATH…

2006-01-01T23:59:59.000Z

378

Isotopic Analysis- Gas At Long Valley Caldera Geothermal Area...  

Open Energy Info (EERE)

Kennedy at the University of California at Berkeley, CA. Isotopic ratios of helium and CO2 determined for gases sampled at LVEW were 3.66 Ra (3He4He ratio) and -6.4 %o (delta...

379

The socioeconomic effects of uranium development in south Texas: a human ecological approach  

E-Print Network [OSTI]

and organizational effects of such developments. Finally, through a combination of participant observation and inter- viewing of community leaders, an attempt will be made to determine the socioeconomic ramifications of uranium de- velopments on communities...THE SOCIOECONOMIC FFFECTS OF URANIUM DEVELOPMENT IN SOUTH TEXAS: A HUMAN ECOLOGICAL APPROACH A Thesis by PAMELA CHRIS HOPKINS Submitted to tne Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree...

Hopkins, Pamela Chris

2012-06-07T23:59:59.000Z

380

Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report  

SciTech Connect (OSTI)

Overview Fast reactors were evaluated to enable the transmutation of transuranic isotopes generated by nuclear energy systems. The motivation for this was that TRU isotopes have high radiotoxicity and relatively long half-lives, making them unattractive for disposal in a long-term geologic repository. Fast reactors provide an efficient means to utilize the energy content of the TRUs while destroying them. An enabling technology that requires research and development is the fabrication metallic fuel containing TRU isotopes using powder metallurgy methods. This project focused upon developing a powder metallurgical fabrication method to produce U-Zr-transuranic (TRU) alloys at relatively low processing temperatures (500ºC to 600ºC) using either hot extrusion or alpha-phase sintering for charecterization. Researchers quantified the fundamental aspects of both processing methods using surrogate metals to simulate the TRU elements. The process produced novel solutions to some of the issues relating to metallic fuels, such as fuel-cladding chemical interactions, fuel swelling, volatility losses during casting, and casting mold material losses. Workscope There were two primary tasks associated with this project: 1. Hot working fabrication using mechanical alloying and extrusion • Design, fabricate, and assemble extrusion equipment • Extrusion database on DU metal • Extrusion database on U-10Zr alloys • Extrusion database on U-20xx-10Zr alloys • Evaluation and testing of tube sheath metals 2. Low-temperature sintering of U alloys • Design, fabricate, and assemble equipment • Sintering database on DU metal • Sintering database on U-10Zr alloys • Liquid assisted phase sintering on U-20xx-10Zr alloys Appendices Outline Appendix A contains a Fuel Cycle Research & Development (FCR&D) poster and contact presentation where TAMU made primary contributions. Appendix B contains MSNE theses and final defense presentations by David Garnetti and Grant Helmreich outlining the beginning of the materials processing setup. Also included within this section is a thesis proposal by Jeff Hausaman. Appendix C contains the public papers and presentations introduced at the 2010 American Nuclear Society Winter Meeting. Appendix A—MSNE theses of David Garnetti and Grant Helmreich and proposal by Jeff Hausaman A.1 December 2009 Thesis by David Garnetti entitled “Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.2 September 2009 Presentation by David Garnetti (same title as document in Appendix B.1) A.3 December 2010 Thesis by Grant Helmreich entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.4 October 2010 Presentation by Grant Helmreich (same title as document in Appendix B.3) A.5 Thesis Proposal by Jeffrey Hausaman entitled “Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors” Appendix B—External presentations introduced at the 2010 ANS Winter Meeting B.1 J.S. Hausaman, D.J. Garnetti, and S.M. McDeavitt, “Powder Metallurgy of Alpha Phase Uranium Alloys for TRU Burning Fast Reactors,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.2 PowerPoint Presentation Slides from C.1 B.3 G.W. Helmreich, W.J. Sames, D.J. Garnetti, and S.M. McDeavitt, “Uranium Powder Production Using a Hydride-Dehydride Process,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.4. PowerPoint Presentation Slides from C.3 B.5 Poster Presentation from C.3 Appendix C—Fuel cycle research and development undergraduate materials and poster presentation C.1 Poster entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys” presented at the Fuel Cycle Technologies Program Annual Meeting C.2 April 2011 Honors Undergraduate Thesis by William Sames, Research Fellow, entitled “Uranium Metal Powder Production, Particle Dis

Sean M. McDeavitt

2011-04-29T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

382

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"

383

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-

384

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

385

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

386

Atomic line emission analyzer for hydrogen isotopes  

DOE Patents [OSTI]

Apparatus for isotopic analysis of hydrogen comprises a low pressure chamber into which a sample of hydrogen is introduced and then exposed to an electrical discharge to excite the electrons of the hydrogen atoms to higher energy states and thereby cause the emission of light on the return to lower energy states, a Fresnel prism made at least in part of a material anomalously dispersive to the wavelengths of interest for dispersing the emitted light, and a photodiode array for receiving the dispersed light. The light emitted by the sample is filtered to pass only the desired wavelengths, such as one of the lines of the Balmer series for hydrogen, the wavelengths of which differ slightly from one isotope to another. The output of the photodiode array is processed to determine the relative amounts of each isotope present in the sample. Additionally, the sample itself may be recovered using a metal hydride.

Kronberg, James W. (108 Independent Blvd., Aiken, SC 29801)

1993-01-01T23:59:59.000Z

387

Atomic line emission analyzer for hydrogen isotopes  

DOE Patents [OSTI]

Apparatus for isotopic analysis of hydrogen comprises a low pressure chamber into which a sample of hydrogen is introduced and then exposed to an electrical discharge to excite the electrons of the hydrogen atoms to higher energy states and thereby cause the emission of light on the return to lower energy states, a Fresnel prism made at least in part of a material anomalously dispersive to the wavelengths of interest for dispersing the emitted light, and a photodiode array for receiving the dispersed light. The light emitted by the sample is filtered to pass only the desired wavelengths, such as one of the lines of the Balmer series for hydrogen, the wavelengths of which differ slightly from one isotope to another. The output of the photodiode array is processed to determine the relative amounts of each isotope present in the sample. Additionally, the sample itself may be recovered using, a metal hydride.

Kronberg, J.W.

1991-05-08T23:59:59.000Z

388

Atomic line emission analyzer for hydrogen isotopes  

DOE Patents [OSTI]

Apparatus for isotopic analysis of hydrogen comprises a low pressure chamber into which a sample of hydrogen is introduced and then exposed to an electrical discharge to excite the electrons of the hydrogen atoms to higher energy states and thereby cause the emission of light on the return to lower energy states, a Fresnel prism made at least in part of a material anomalously dispersive to the wavelengths of interest for dispersing the emitted light, and a photodiode array for receiving the dispersed light. The light emitted by the sample is filtered to pass only the desired wavelengths, such as one of the lines of the Balmer series for hydrogen, the wavelengths of which differ slightly from one isotope to another. The output of the photodiode array is processed to determine the relative amounts of each isotope present in the sample. Additionally, the sample itself may be recovered using a metal hydride.

Kronberg, J.W.

1993-03-30T23:59:59.000Z

389

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Determination of No Adverse Material Impact Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup November 12, 2009 - 12:00am Addthis WASHINGTON, D.C. - Secretary Chu announced today that the Department of Energy has issued a final determination and market impact study for the proposed uranium transfer to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, which will create between 800 to 1,000 new jobs for the community. The market review and determination confirms that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. Under the determination, DOE's Office of Environmental Management will be

390

Secretary Chu Announces Determination of No Adverse Material Impact for  

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

Secretary Chu Announces Determination of No Adverse Material Impact Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup Secretary Chu Announces Determination of No Adverse Material Impact for Uranium Transfer to Fund Portsmouth Cleanup November 12, 2009 - 12:00am Addthis WASHINGTON, D.C. - Secretary Chu announced today that the Department of Energy has issued a final determination and market impact study for the proposed uranium transfer to fund accelerated cleanup activities at the Portsmouth Site in Piketon, Ohio, which will create between 800 to 1,000 new jobs for the community. The market review and determination confirms that the proposed transfer of uranium will not have an adverse material impact on the domestic uranium industries. Under the determination, DOE's Office of Environmental Management will be

391

Uranium and Neptunium Desorption from Yucca Mountain Alluvium  

SciTech Connect (OSTI)

Uranium and neptunium were used as reactive tracers in long-term laboratory desorption studies using saturated alluvium collected from south of Yucca Mountain, Nevada. The objective of these long-term experiments is to make detailed observations of the desorption behavior of uranium and neptunium to provide Yucca Mountain with technical bases for a more realistic and potentially less conservative approach to predicting the transport of adsorbing radionuclides in the saturated alluvium. This paper describes several long-term desorption experiments using a flow-through experimental method and groundwater and alluvium obtained from boreholes along a potential groundwater flow path from the proposed repository site. In the long term desorption experiments, the percentages of uranium and neptunium sorbed as a function of time after different durations of sorption was determined. In addition, the desorbed activity as a function of time was fit using a multi-site, multi-rate model to demonstrate that different desorption rate constants ranging over several orders of magnitude exist for the desorption of uranium from Yucca Mountain saturated alluvium. This information will be used to support the development of a conceptual model that ultimately results in effective K{sub d} values much larger than those currently in use for predicting radionuclide transport at Yucca Mountain.

C.D. Scism; P.W. Reimus; M. Ding; S.J. Chipera

2006-03-16T23:59:59.000Z

392

Relativistic calculations of the isotope shifts in highly charged Li-like ions  

E-Print Network [OSTI]

Relativistic calculations of the isotope shifts of energy levels in highly charged Li-like ions are performed. The nuclear recoil (mass shift) contributions are calculated by merging the perturbative and large-scale configuration-interaction Dirac-Fock-Sturm (CI-DFS) methods. The nuclear size (field shift) contributions are evaluated by the CI-DFS method including the electron-correlation, Breit, and QED corrections. The nuclear deformation and nuclear polarization corrections to the isotope shifts in Li-like neodymium, thorium, and uranium are also considered. The results of the calculations are compared with the theoretical values obtained with other methods.

Zubova, N A; Shabaev, V M; Tupitsyn, I I; Volotka, A V; Plunien, G; Brandau, C; Stöhlker, Th

2014-01-01T23:59:59.000Z

393

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

SciTech Connect (OSTI)

In this study, sediments collected from boreholes drilled in 2010 and 2011 as part of a remedial investigation/feasibility study were characterized. The wells, located within or around two process ponds and one process trench waste site, were characterized in terms of total uranium concentration, mobile fraction of uranium, particle size, and moisture content along the borehole depth. In general, the gravel-dominated sediments of the vadose zone Hanford formation in all investigated boreholes had low moisture contents. Based on total uranium content, a total of 48 vadose zone and periodically rewetted zone sediment samples were selected for more detailed characterization, including measuring the concentration of uranium extracted with 8 M nitric acid, and leached using bicarbonate mixed solutions to determine the liable uranium (U(VI)) contents. In addition, water extraction was conducted on 17 selected sediments. Results from the sediment acid and bicarbonate extractions indicated the total concentrations of anthropogenic labile uranium in the sediments varied among the investigated boreholes. The peak uranium concentration (114.84 µg/g, acid extract) in <2-mm size fractions was found in borehole 399 1-55, which was drilled directly in the southwest corner of the North Process Pond. Lower uranium concentrations (~0.3–2.5 µg/g, acid extract) in <2-mm size fractions were found in boreholes 399-1-57, 399-1-58, and 399-1-59, which were drilled either near the Columbia River or inland and upgradient of any waste process ponds or trenches. A general trend of “total” uranium concentrations was observed that increased as the particle size decreased when relating the sediment particle size and acid extractable uranium concentrations in two selected sediment samples. The labile uranium bicarbonate leaching kinetic experiments on three selected sediments indicated a two-step leaching rate: an initial rapid release, followed by a slow continual release of uranium from the sediment. Based on the uranium leaching kinetic results, quasi equilibrium can be assumed after 1000-h batch reaction time in this study.

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

2012-11-26T23:59:59.000Z

394

Ultrafiltration evaluation with depleted uranium oxide  

SciTech Connect (OSTI)

Scientists at the Los Alamos National Laboratory Plutonium Facility are using electrodissolution in neutral to alkaline solutions to decontaminate oralloy parts that have surface plutonium contamination. Ultrafiltration of the electrolyte stream removes precipitate so that the electrolyte stream to the decontamination fixture is precipitate free. This report describes small-scale laboratory ultrafiltration experiments that the authors performed to determine conditions necessary for full-scale operation of an ultrafiltration module. Performance was similar to what they observed in the ferric hydroxide system. At 12 psi transmembrane pressure, a shear rate of 12,000 sec{sup {minus}1} was sufficient to sustain membrane permeability. Ultrafiltration of uranium(VI) oxide appears to occur as easily as ultrafiltration of ferric hydroxide. Considering the success reported in this study, the authors plan to add ultrafiltration to the next decontamination system for oralloy parts.

Weisbrod, K.R.; Schake, A.R.; Morgan, A.N.; Purdy, G.M.; Martinez, H.E.; Nelson, T.O.

1998-03-01T23:59:59.000Z

395

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

SciTech Connect (OSTI)

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

NONE

1995-07-05T23:59:59.000Z

396

Assessment of depleted uranium in South-Western Iran  

Science Journals Connector (OSTI)

Abstract Depleted uranium (DU) has been used in a number of conflicts most notably during the Gulf War in Iraq and existence of it has been reported in Kuwait by IAEA experts. Due to heavy sand storms prevailing into the direction to South West of Iran transporting sand originating from Iraq, the probability that DU could be moved is considered high. Therefore it was decided to take some air and soil samples near border line and some nearest cities. The study was focused on finding DU in air and soil of these south-west provinces. 22 air samples and 20 soil samples were collected and analyzed on their contents of uranium isotopes by alpha, beta and gamma spectrometry. The air and soil samples have been measured by use of an alpha-beta counter and by a gamma spectrometer, respectively. Results showed that there is no radiation impact from DU and so no DU has been transported via sand storms since all results were obtained below the detection limit.

Hossein Yousefi; Abdullah Najafi

2013-01-01T23:59:59.000Z

397

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

398

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

SciTech Connect (OSTI)

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

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

2011-07-27T23:59:59.000Z

399

Isotope separation apparatus  

DOE Patents [OSTI]

Isotope separation apparatus consisting of a plurality of cells disposed adjacent to each other in an evacuated container. A common magnetic field is established extending through all of the cells. A source of energetic electrons at one end of the container generates electrons which pass through the cells along the magnetic field lines. Each cell includes an array of collector plates arranged in parallel or in tandem within a common magnetic field. Sets of collector plates are disposed adjacent to each other in each cell. Means are provided for differentially energizing ions of a desired isotope by applying energy at the cyclotron resonant frequency of the desired isotope. As a result, the energized desired ions are preferentially collected by the collector plates.

Arnush, Donald (Rancho Palos Verdes, CA); MacKenzie, Kenneth R. (Pacific Palisades, CA); Wuerker, Ralph F. (Palos Verdes Estates, CA)

1980-01-01T23:59:59.000Z

400

Environmental monitoring for detection of uranium enrichment operations: Comparison of LEU and HEU facilities  

SciTech Connect (OSTI)

In 1994, the International Atomic Energy Agency (IAEA) initiated an ambitious program of worldwide field trials to evaluate the utility of environmental monitoring for safeguards. Part of this program involved two extensive United States field trials conducted at the large uranium enrichment facilities. The Paducah operation involves a large low-enriched uranium (LEU) gaseous diffusion plant while the Portsmouth facilities include a large gaseous diffusion plant that has produced both LEU and high-enriched uranium (HEU) as well as an LEU centrifuge facility. As a result of the Energy Policy Act of 1992, management of the uranium enrichment operations was assumed by the US Enrichment Corporation (USEC). The facilities are operated under contract by Martin Marietta Utility Services. Martin Marietta Energy Systems manages the environmental restoration and waste management programs at Portsmouth and Paducah for DOE. These field trials were conducted. Samples included swipes from inside and outside process buildings, vegetation and soil samples taken from locations up to 8 km from main sites, and hydrologic samples taken on the sites and at varying distances from the sites. Analytical results from bulk analysis were obtained using high abundance sensitivity thermal ionization mm spectrometers (TIMS). Uranium isotopics altered from the normal background percentages were found for all the sample types listed above, even on vegetation 5 km from one of the enrichment facilities. The results from these field trials demonstrate that dilution by natural background uranium does not remove from environmental samples the distinctive signatures that are characteristic of enrichment operations. Data from swipe samples taken within the enrichment facilities were particularly revealing. Particulate analysis of these swipes provided a detailed ``history`` of both facilities, including the assays of the end product and tails for both facilities.

Hembree, D.M. Jr.; Carter, J.A.; Ross, H.H.

1995-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "uranium isotopic determination" 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

GENERATION OF RADIOXENON ISOTOPES  

SciTech Connect (OSTI)

With the continued population of the International Monitoring System (IMS) network and the certification of radioxenon laboratory systems it has become necessary to calibrate and test these systems using as many of the radioxenon isotopes as possible. Several very promising techniques have been explored recently that allow for convenient production of Xe-133, Xe-131m, the short-lived isotope Xe-135, and even the difficult to obtain Xe-133m. IMS national and international laboratories have traditionally obtained Xe-133 from medical isotope suppliers. The activity of these medical dose samples is extremely high (~ 740 MBq) and requires very careful fume hood work to dilute down to appropriate levels (~ 10 Bq). By waiting for 10 or more half-lives it is possible to reduce the handling regimen considerably, while also obtaining a strong Xe-131m signature due to its longer half-life (11.9 days). The short-lived isotope Xe-135 (9.14 hrs) and the longer lived parent nuclide Xe-133m (2.2 day half-life) are never present in these samples. To obtain these isotopes another source or technique is required. This paper will discuss the two techniques developed and implemented at Pacific Northwest National Lab (PNNL) and show the results obtained from each technique. The first is an in-house method that allows for on demand production of two of these isotopes, Xe-133 and Xe-135, using HEU and a modest flux neutron source. The second method uses a research reactor at the Pullman campus of Washington State University to produce Xe-133, Xe-133m and Xe-135.

McIntyre, Justin I.; Pratt, Sharon L.; Bowyer, Ted W.; Cooper, Matthew W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, Charles W.; Miley, Harry S.; Ripplinger, Mike D.

2008-09-23T23:59:59.000Z

402

New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities  

SciTech Connect (OSTI)

An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

Brim, Cornelia P.

2013-03-04T23:59:59.000Z

403

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

404

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"

405

:- : 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

406

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. _________________________

407

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

408

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"

409

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"

410

Isotope Effect of Mercury Diffusion in Air  

Science Journals Connector (OSTI)

Isotope fractionation describes the separation of a reservoir with one isotope composition into “fractions” with different isotope compositions due to small isotopic differences in equilibrium partitioning, rates of mass transfer, or rates of transformation. ... (29) ?202Hg is the value most frequently used to examine mass dependent fractionation of mercury isotopes as 202Hg is the heaviest mercury isotope without significant isobaric interferences. ...

Paul G. Koster van Groos; Bradley K. Esser; Ross W. Williams; James R. Hunt

2013-12-23T23:59:59.000Z

411

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:

412

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.

413

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

414

Isotopic Composition of Solar Wind Calcium: First in Situ Measurement by CELIAS/MTOF on Board SOHO  

E-Print Network [OSTI]

We present first results on the Ca isotopic abundances derived from the high resolution Mass Time-of-Flight (MTOF) spectrometer of the charge, element, and isotope analysis system (CELIAS) experiment on board the Solar and Heliospheric Observatory (SOHO). We obtain isotopic ratios 40Ca/42Ca = (128+-47) and 40Ca/44Ca = (50+-8), consistent with terrestrial values. This is the first in situ determination of the solar wind calcium isotopic composition and is important for studies of stellar modeling and solar system formation since the present-day solar Ca isotopic abundances are unchanged from their original isotopic composition in the solar nebula.

R. Kallenbach; F. M. Ipavich; P. Bochsler; S. Hefti; P. Wurz; M. R. Aellig; A. B. Galvin; J. Geiss; F. Gliem; G. Gloeckler; H. Grunwaldt; M. Hilchenbach; D. Hovestadt; B. Klecker

1998-02-07T23:59:59.000Z

415

Management of Heavy Isotope in the DOE Complex  

SciTech Connect (OSTI)

Currently each Department Of Energy (DOE) Program office manages its own nuclear materials through activities such as production, processing, storage, transportation, and disposition. However, recognizing the need to strengthen its strategic approach to the integrated life-cycle management of nuclear materials, DOE established the Nuclear Materials Management Stewardship Initiative (NMMSI) in January 2000. The NMMSI's first visible product was the Integrated Nuclear Material Management Plan in which it was generally recommended that DOE take a cross-cutting look at managing its nuclear materials, and specifically recommended that four Nuclear Material Management Groups (NMMGs) be formed. These groups were established to facilitate management of nuclear materials for which DOE has or may have responsibility, including many presently not in DOE's direct control. One of these NMMGs, the Heavy Isotope Management Group (HIMG) was established at Oak Ridge National Laboratory in Dec ember 2000, to facilitate management of (a) actinide and their decay products (except sealed sources) and (b) isotopically enriched stable and radioactive isotopes except uranium and lithium, but excluding thorium, uranium, spent fuel, and weapons or reactor grade plutonium which are addressed by other NMMGs. Despite its short duration and relatively limited funding, the HIMG has facilitated the disposition of heavy isotopes from Lawrence Berkeley National Laboratory (LBNL), Rocky Flats Environmental Technology Site (RFETS), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Lawrence Livermore National Laboratory (LLNL), and Idaho National Engineering and Environmental Laboratory (INEEL). The primary disposition options have been to facilitate reuse of valuable heavy isotopes by matching custodians of unwanted materials with other users that seek such materials for new applications. This approach has the dual advantages of avoiding custodian disposal costs plus cost to the user of obtaining newly produced material. The HIMG has also prepared issue papers on neptunium and americium/curium that identify the resources, potential uses, and disposal pathways for the materials across the DOE Complex. In the future the HIMG expects to comprehensively identify the status of the U.S. heavy isotope inventory, prepare additional issue papers and plans charting the future of this inventory, and to facilitate execution of the plan.

Canon, R.; Croff, A.; Boyd, L.

2002-02-27T23:59:59.000Z

416

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).

417

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

418

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

419

Recovery and Blend-Down Uranium for Beneficial use in Commercial Reactors - 13373  

SciTech Connect (OSTI)

In April 2001 the Department of Energy (DOE) and the Tennessee Valley Authority (TVA) signed an Interagency Agreement to transfer approximately 33 MT of off-specification (off-spec) highly enriched uranium (HEU) from DOE to TVA for conversion to commercial reactor fuel. Since that time additional surplus off-spec HEU material has been added to the program, making the total approximately 46 MT off-spec HEU. The disposition path for approximately half (23 MT) of this 46 MT of surplus HEU material, was down blending through the H-canyon facility at the Savannah River Site (SRS). The HEU is purified through the H-canyon processes, and then blended with natural uranium (NU) to form low enriched uranium (LEU) solution with a 4.95% U-235 isotopic content. This material was then transported to a TVA subcontractor who converted the solution to uranium oxide and then fabricated into commercial light water reactor (LWR) fuel. This fuel is now powering TVA reactors and supplying electricity to approximately 1 million households in the TVA region. There is still in excess of approximately 10 to 14 MT of off-spec HEU throughout the DOE complex or future foreign and domestic research reactor returns that could be recovered and down blended for use in either currently designed light water reactors, ?5% enriched LEU, or be made available for use in subsequent advanced 'fast' reactor fuel designs, ?19% LEU. (authors)

Magoulas, Virginia [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

420

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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

422

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

423

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

424

RAPID METHOD FOR DETERMINATION OF {sup 228}Ra IN WATER SAMPLES  

SciTech Connect (OSTI)

A new rapid method for the determination of {sup 228}Ra in natural water samples has been developed at the SRNL/EBL (Savannah River National Lab/ Environmental Bioassay Laboratory) that can be used for emergency response or routine samples. While gamma spectrometry can be employed with sufficient detection limits to determine {sup 228}Ra in solid samples (via {sup 228}Ac) , radiochemical methods that employ gas flow proportional counting techniques typically provide lower MDA (Minimal Detectable Activity) levels for the determination of {sup 228}Ra in water samples. Most radiochemical methods for {sup 228}Ra collect and purify {sup 228}Ra and allow for {sup 228}Ac daughter ingrowth for ~36 hours. In this new SRNL/EBL approach, {sup 228}Ac is collected and purified from the water sample without waiting to eliminate this delay. The sample preparation requires only about 4 hours so that {sup 228}Ra assay results on water samples can be achieved in < 6 hours. The method uses a rapid calcium carbonate precipitation enhanced with a small amount of phosphate added to enhance chemical yields (typically >90%), followed by rapid cation exchange removal of calcium. Lead, bismuth, uranium, thorium and protactinium isotopes are also removed by the cation exchange separation. {sup 228}Ac is eluted from the cation resin directly onto a DGA Resin cartridge attached to the bottom of the cation column to purify {sup 228}Ac. DGA Resin also removes lead and bismuth isotopes, along with Sr isotopes and {sup 90}Y. La is used to determine {sup 228}Ac chemical yield via ICP-MS, but {sup 133}Ba can also be used instead if ICP-MS assay is not available. Unlike some older methods, no lead or strontium holdback carriers or continual readjustment of sample pH is required.

Maxwell, S.

2012-09-05T23:59:59.000Z

425

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...

426

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...

427

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...

428

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...

429

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...

430

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

431

Fact Sheet: Facility For Rare Isotope Beams (FRIB) Applicant Selection |  

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

Facility For Rare Isotope Beams (FRIB) Applicant Facility For Rare Isotope Beams (FRIB) Applicant Selection Fact Sheet: Facility For Rare Isotope Beams (FRIB) Applicant Selection December 11, 2008 - 8:51am Addthis Based on the analyses and recommendations over the last decade, the U.S. Department of Energy (DOE) Office of Science determined that the establishment of a Facility for Rare Isotope Beams (FRIB) is a high priority for the future of U.S. nuclear science research. This determination and supporting rationale are reflected in the DOE/ National Science Foundation Nuclear Science Advisory Committee's 2007 Long Range Plan and the 2003 DOE report, "Facilities for the Future of Science: A Twenty-Year Outlook." A Funding Opportunity Announcement (FOA) was used to solicit applications for the conceptual design and establishment of FRIB in order

432

Radiological assessment of depleted uranium migration offsite from an ordnance range  

SciTech Connect (OSTI)

The military utilizes ordnance loaded with depleted uranium in order to maximize armor penetrating capabilities. These weapons are tested on open ranges where the weapons are fired through a cloth target and impact into the soil. This paper examines the potential environmental impact from use of depleted uranium in an open setting. A preliminary pathway analysis was performed to examine potential routes of exposure to nonhuman species in the vicinity and ultimately to man. Generic data was used in the study to estimate the isotopic mix and weight of the ordnance. Key factors in the analysis included analyzing the physics of weapon impact on soil, chemical changes in material upon impact, and mechanisms of offsite transport (including atmospheric and overland transport). Non-standard exposure scenarios were investigated, including the possibility of offsite contaminant transport due to range grassfires. Two radiological assessment codes, MEPAS (Multi media Environmental Pollutant Assessment System) and RESRAD were used to help analyze the scenarios.

Rynders, D.G. [Oregon State Univ., Corvallis, OR (United States)

1996-06-01T23:59:59.000Z

433

Extremely light Li in orogenic eclogites: The role of isotope fractionation during dehydration in subducted oceanic crust  

E-Print Network [OSTI]

,20] and boron [21,22], but the degree of Li isotope fractionation during dehydration reactions has yet to be determined. In this regard we measured Li isotopeExtremely light Li in orogenic eclogites: The role of isotope fractionation during dehydration

Rudnick, Roberta L.

434

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

435

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

436

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...

437

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...

438

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...

439

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

440

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

Note: This page contains sample records for the topic "uranium isotopic determination" 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

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...

442

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...

443

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:...

444

Investigation of Uranium Polymorphs  

SciTech Connect (OSTI)

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

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

2011-08-01T23:59:59.000Z

445

History of Uranium-233(sup233U)Processing at the Rocky Flats Plant. In support of the RFETS Acceptable Knowledge Program  

SciTech Connect (OSTI)

This report documents the processing of Uranium-233 at the Rocky Flats Plant (Rocky Flats Environmental Technology Site). The information may be used to meet Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC)and for determining potential Uranium-233 content in applicable residue waste streams.

Moment, R.L.; Gibbs, F.E.; Freiboth, C.J.

1999-04-01T23:59:59.000Z

446

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

SciTech Connect (OSTI)

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

Veinot, K. G.

2009-07-22T23:59:59.000Z

447

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

448

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

449

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

450

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

451

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

452

Four methods for determining the composition of trace radioactive surface contamination of low-radioactivity metal  

E-Print Network [OSTI]

Four methods for determining the composition of low-level uranium- and thorium-chain surface contamination are presented. One method is the observation of Cherenkov light production in water. In two additional methods a position-sensitive proportional counter surrounding the surface is used to make both a measurement of the energy spectrum of alpha particle emissions and also coincidence measurements to derive the thorium-chain content based on the presence of short-lived isotopes in that decay chain. The fourth method is a radiochemical technique in which the surface is eluted with a weak acid, the eluate is concentrated, added to liquid scintillator and assayed by recording beta-alpha coincidences. These methods were used to characterize two `hotspots' on the outer surface of one of the He-3 proportional counters in the Neutral Current Detection array of the Sudbury Neutrino Observatory experiment. The methods have similar sensitivities, of order tens of ng, to both thorium- and uranium-chain contamination.

O'Keeffe, H M; Cleveland, B T; Doucas, G; Gagnon, N; Jelley, N A; Kraus, C; Lawson, I T; Majerus, S; McGee, S R; Myers, A W; Poon, A W P; Rielage, K; Robertson, R G H; Rosten, R C; Stonehill, L C; VanDevender, B A; Van Wechel, T D

2011-01-01T23:59:59.000Z

453

Four methods for determining the composition of trace radioactive surface contamination of low-radioactivity metal  

E-Print Network [OSTI]

Four methods for determining the composition of low-level uranium- and thorium-chain surface contamination are presented. One method is the observation of Cherenkov light production in water. In two additional methods a position-sensitive proportional counter surrounding the surface is used to make both a measurement of the energy spectrum of alpha particle emissions and also coincidence measurements to derive the thorium-chain content based on the presence of short-lived isotopes in that decay chain. The fourth method is a radiochemical technique in which the surface is eluted with a weak acid, the eluate is concentrated, added to liquid scintillator and assayed by recording beta-alpha coincidences. These methods were used to characterize two `hotspots' on the outer surface of one of the He-3 proportional counters in the Neutral Current Detection array of the Sudbury Neutrino Observatory experiment. The methods have similar sensitivities, of order tens of ng, to both thorium- and uranium-chain contamination.

H. M. O'Keeffe; T. H. Burritt; B. T. Cleveland; G. Doucas; N. Gagnon; N. A. Jelley; C. Kraus; I. T. Lawson; S. Majerus; S. R. McGee; A. W. Myers; A. W. P. Poon; K. Rielage; R. G. H. Robertson; R. C. Rosten; L. C. Stonehill; B. A. VanDevender; T. D. Van Wechel

2011-03-29T23:59:59.000Z

454

Containment and storage of uranium hexafluoride at US Department of Energy uranium enrichment plants  

SciTech Connect (OSTI)

Isotopically depleted UF{sub 6} (uranium hexafluoride) accumulates at a rate five to ten times greater than the enriched product and is stored in steel vessels at the enrichment plant sites. There are approximately 55,000 large cylinders now in storage at Paducah, Kentucky; Portsmouth, Ohio; and Oak Ridge, Tennessee. Most of them contain a nominal 14 tons of depleted UF{sub 6}. Some of these cylinders have been in the unprotected outdoor storage environment for periods approaching 40 years. Storage experience, supplemented by limited corrosion data, suggests a service life of about 70 years under optimum conditions for the 48-in. diameter, 5/16-in.-wall pressure vessels (100 psi working pressure), using a conservative industry-established 1/4-in.-wall thickness as the service limit. In the past few years, however, factors other than atmospheric corrosion have become apparent that adversely affect the serviceability of small numbers of the storage containers and that indicate the need for a managed program to ensure maintenance ofcontainment integrity for all the cylinders in storage. The program includes periodic visual inspections of cylinders and storage yards with documentation for comparison with other inspections, a group of corrosion test programs to permit cylinder life forecasts, and identification of (and scheduling for remedial action) situations in which defects, due to handling damage or accelerated corrosion, can seriously shorten the storage life or compromise the containment integrity of individual cylinders. The program also includes rupture testing to assess the effects of certain classes of damage on overall cylinder strength, aswell as ongoing reviews of specifications, procedures, practices, and inspection results to effect improvements in handling safety, containment integrity, and storage life.

Barlow, C.R.; Alderson, J.H.; Blue, S.C.; Boelens, R.A.; Conkel, M.E.; Dorning, R.E.; Ecklund, C.D.; Halicks, W.G.; Henson, H.M.; Newman, V.S.; Philpot, H.E.; Taylor, M.S.; Vournazos, J.P. [Oak Ridge K-25 Site, TN (United States). UEO Enrichment Technical Operations Div.; Russell, J.R. [USDOE Oak Ridge Field Office, TN (United States); Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States); Ziehlke, K.T. [MJB Technical Associates (United States)

1992-07-01T23:59:59.000Z

455

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

456

Effect of Gadolinium Doping on the Air Oxidation of Uranium Dioxide  

SciTech Connect (OSTI)

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

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

2004-12-04T23:59:59.000Z

457

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.

458

A Strontium Isotopic Study Of Newberry Volcano, Central Oregon- Structural  

Open Energy Info (EERE)

Strontium Isotopic Study Of Newberry Volcano, Central Oregon- Structural Strontium Isotopic Study Of Newberry Volcano, Central Oregon- Structural And Thermal Implications Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: A Strontium Isotopic Study Of Newberry Volcano, Central Oregon- Structural And Thermal Implications Details Activities (2) Areas (1) Regions (0) Abstract: Ratios of 87Sr/86Sr were determined in twenty-seven basaltic rocks from Newberry. These ratios range from 0.70330 to 0.70414; most fall between 0.7035 and 0.7038. Covariance of Al2O3/FeO* ratio, TiO2 content, and Th content with 87Sr/86Sr suggests that some isotopic ratios reflect shallow crustal contamination, but the data also suggest that two mantle sources, a prominent one at 0.7036 and a less-prominent one at 0.7033 or less, are represented. The hypothesis of crustal contamination is supported

459

Isotopic Analysis- Fluid At Coso Geothermal Area (1990) | Open Energy  

Open Energy Info (EERE)

Analysis- Fluid At Coso Geothermal Area (1990) Analysis- Fluid At Coso Geothermal Area (1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Coso Geothermal Area (1990) Exploration Activity Details Location Coso Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine the recharge of the area Notes Hydrogen and oxygen isotope data on waters of Coso thermal and nonthermal waters were studied. Hydrogen and oxygen isotopes do not uniquely define the recharge area for the Coso geothermal system but strongly suggest Sierran recharge with perhaps some local recharge. References Whelan, J. A. (1 September 1990) Water geochemistry study of Indian Wells Valley, Inyo and Kern Counties, California. Supplement.