Sample records for ms uo uo

  1. UoS Motor Accident Report Form COMPANY DETAILS

    E-Print Network [OSTI]

    Sussex, University of

    UNIV01FL02 UoS Motor Accident Report Form COMPANY DETAILS INSURED: University of Sussex ADDRESS: LOCATION: DESCRIPTION OF HOW ACCIDENT HAPPENED: PLEASE DRAW A SKETCH OF THE ACCIDENT: #12;DRIVER DETAILS: PREVIOUS ACCIDENTS: ADDRESS: VEHICLE DETAILS DATE VEHICLE PURCHASED: MAKE/MODEL: REGISTRATION: MILEAGE

  2. UO Policy Library Resource for

    E-Print Network [OSTI]

    Oregon, University of

    UO Policy Library Resource for Policy Owners To ensure University- wide consistency in the formulation, review, approval, and implementation of policies, the Policy Library has provided a resource section for policy owners. It helps answer questions such as: Is this a policy or procedure? What

  3. UO

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

    success in this work will deepen our fundamental understanding of the nuclear energy materials. Background: The actinide (U, Np, Pu) oxides, nitrides, and carbides are of...

  4. OXYGEN DIFFUSION IN UO2-x

    E-Print Network [OSTI]

    Kim, K.C.

    2013-01-01T23:59:59.000Z

    ~ K.C. K:i.m, "Oxygen Diffusion in Hypostoichiometricsystem for enriching uo 2 in oxygen-18 or for stoichiometry+nal of Nuclear Materials OXYGEN DIFFUSION IN U0 2 _:x K.C.

  5. Crystal fields in UO2 - revisited

    SciTech Connect (OSTI)

    Nakotte, Heinz [Los Alamos National Laboratory; Rajatram, R [NMSU/UNIV OF N.C.; Kern, S [COLORADO STATE UNIV; Mcqueeney, R J [AMES LAB; Lander, G H [EUROPEAN COMMISIONS, JRC; Robinson, R A [BRAGG INSTITUTE

    2009-01-01T23:59:59.000Z

    We performed inelastic neutron scattering (INS) in order to re-investigate the crystal-field ground state and the level splitting in UO{sub 2}. Previous INS studies on UO{sub 2} by Amorelli et al. [Physical Review B 15, 1989, 1856] uncovered four excitations at low temperatures in the 150-180 meV range. Considering the dipole-allowed transitions, only three of these transitions could be explained by the published crystal-field model. Our INS results on a different UO{sub 2} sample revealed that the unaccounted peak at about 180 meV is a spurious one, and thus not intrinsic to UO{sub 2}. In good agreement with Amoretti's results, we corroborated that the ground-state of UO{sub 2} is the {Lambda}{sub 5} triplet, and we computed that the fourth- and six-order crystal field parameters are V{sub 4} = -116 meV and V{sub 6} = 26 meV, respectively. We also studied the INS response of the non-magnetic U{sub 0.4}Th{sub 0.6}O{sub 2}. The splitting for this thorium-doped compound is similar to the one of UO{sub 2}, which orders antiferromagnetically at low temperatures. Therefore, we can conclude that magnetic interactions only weakly perturb the energy level splitting, which is dominated by strong crystal fields.

  6. Spectroscopic Studies of the Several Isomers of UO3

    SciTech Connect (OSTI)

    Sweet, Lucas E.; Reilly, Dallas D.; Abrecht, David G.; Buck, Edgar C.; Meier, David E.; Su, Yin-Fong; Brauer, Carolyn S.; Schwantes, Jon M.; Tonkyn, Russell G.; Szecsody, James E.; Blake, Thomas A.; Johnson, Timothy J.

    2013-09-26T23:59:59.000Z

    Uranium trioxide is known to adopt seven different structural forms. While these structural forms have been well characterized using x-ray or neutron diffraction techniques, little work has been done to characterize their spectroscopic properties, particularly of the pure phases. Since the structural isomers of UO3 all have similar thermodynamic stabilities and most tend to hydrolyze under open atmospheric conditions, mixtures of UO3 phases and the hydrolysis products are common. Much effort went into isolating pure phases of UO3. Utilizing x-ray diffraction as a sample identification check, UV/Vis/NIR spectroscopic signatures of ?-UO3, ?-UO3, ?-UO3 and UO2(OH)2 products were obtained. The spectra of the pure phases can now be used to characterize typical samples of UO3, which are often mixtures of isomers.

  7. Investigations into the Polymorphs and Hydration Products of UO3

    SciTech Connect (OSTI)

    Sweet, Lucas E.; Buck, Edgar C.; Henager, Charles H.; Hu, Shenyang Y.; Meier, David E.; Peper, Shane M.; Schwantes, Jon M.; Su, Yin-Fong; Sams, Robert L.; Blake, Thomas A.; Johnson, Timothy J.; Kulp, Thomas J.; Sommers, Ricky L.; Sugar, Joshua D.; Chames, Jeffrey D.

    2012-04-27T23:59:59.000Z

    This work focuses on progress in gaining a better understanding of the polymorphic nature of the UO{sub 3} and UO{sub 3}-water system; one of several important materials associated with the nuclear fuel cycle. The UO{sub 3}-water system is complex and has not been fully characterized, even though these species are common throughout the fuel cycle. For example, most production schemes for UO{sub 3} result in a mixture of up to six different polymorphic phases, and small differences in these conditions will affect phase genesis that ultimately results in measureable changes to the end product. Here we summarize our efforts to better characterize the UO{sub 3}-water system with optical techniques for the purpose of developing some predictive capability of estimating process history and utility, e.g. for polymorphic phases of unknown origin. Specifically, we have investigated three industrially relevant production pathways of UO{sub 3} and discovered a previously unknown low temperature route to {beta}-UO{sub 3}. Powder x-ray diffraction and optical spectroscopies were utilized in our characterization of the UO{sub 3}-water system. Pure phases of UO{sub 3}, its hydrolysis products and starting materials were used to establish optical spectroscopic signatures for these compounds. Preliminary aging studies were conducted on the {alpha}- and {gamma}-phases of UO{sub 3}.

  8. advanced doped uo2: Topics by E-print Network

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

    N. Creton1,a Physics Websites Summary: layer during the anionic oxidation of UO2 pellets induced very important mechanical stresses due to the crystallographic lattice...

  9. First-principles study of defects and phase transition in UO2...

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

    defects and phase transition in UO2. First-principles study of defects and phase transition in UO2. Abstract: The electronic properties, structure and phase transformation of UO2...

  10. advanced uo2 fuel: Topics by E-print Network

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

    Last Page Topic Index 1 Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets CERN Preprints Summary: A transversal mapping of the Gd concentration was measured in...

  11. PUREX/UO{sub 3} deactivation project management plan

    SciTech Connect (OSTI)

    Washenfelder, D.J.

    1993-12-01T23:59:59.000Z

    From 1955 through 1990, the Plutonium-Uranium Extraction Plant (PUREX) provided the United States Department of Energy Hanford Site with nuclear fuel reprocessing capability. It operated in sequence with the Uranium Trioxide (UO{sub 3}) Plant, which converted the PUREX liquid uranium nitrate product to solid UO{sub 3} powder. Final UO{sub 3} Plant operation ended in 1993. In December 1992, planning was initiated for the deactivation of PUREX and UO{sub 3} Plant. The objective of deactivation planning was to identify the activities needed to establish a passively safe, environmentally secure configuration at both plants, and ensure that the configuration could be retained during the post-deactivation period. The PUREX/UO{sub 3} Deactivation Project management plan represents completion of the planning efforts. It presents the deactivation approach to be used for the two plants, and the supporting technical, cost, and schedule baselines. Deactivation activities concentrate on removal, reduction, and stabilization of the radioactive and chemical materials remaining at the plants, and the shutdown of the utilities and effluents. When deactivation is completed, the two plants will be left unoccupied and locked, pending eventual decontamination and decommissioning. Deactivation is expected to cost $233.8 million, require 5 years to complete, and yield $36 million in annual surveillance and maintenance cost savings.

  12. Spark Plasma Sintering of W-UO2 Cermets

    SciTech Connect (OSTI)

    R. C. O'Brien; N. D. Jerred

    2013-02-01T23:59:59.000Z

    About 50 vol.% 3 um depleted uranium dioxide (UO2) powder was encapsulated within a tungsten super alloy matrix produced from sub-micron tungsten powders using the Spark Plasma Sintering (SPS) process. An additive of 25 atom-percent (at.%) rhenium was included within the tungsten matrix to improve the ductility and fracture toughness of the ceramic–metallic (cermet) matrix. Cermet fabrication to 97.9% of the theoretical cermet density was achieved by sintering at 1500 degrees C with 40 MPa of applied pressure for 20 min. The results presented are from the first known trials of W–UO2 and nuclear cermet production via SPS.

  13. Thermal Reactions of Uranium Metal, UO2, U3O8, UF4, and UO2F2 with NF3 to Produce UF6

    SciTech Connect (OSTI)

    McNamara, Bruce K.; Scheele, Randall D.; Kozelisky, Anne E.; Edwards, Matthew K.

    2009-11-01T23:59:59.000Z

    he objective of this paper is to demonstrate that NF3 fluorinates uranium metal, UO2, UF4, UO3, U3O8, and UO2F2•2H2O to produce the volatile UF6 at temperatures between 100 and 500?C. Thermogravimetric reaction profiles are described that reflect changes in the uranium oxidation state and discrete chemical speciation. Differences in the onset temperatures for each system indicate that NF3-substrate interactions are important for the temperature at which NF3 reacts: U metal > UO3 > UO2 > UO2F2 > UF4 and in fact may indicate different fluorination mechanisms for these various substrates. These studies demonstrate that NF3 is a potential replacement fluorinating agent in the existing nuclear fuel cycle and in oft-proposed actinide volatility reprocessing.

  14. UO{sub 3} plant turnover - facility description document

    SciTech Connect (OSTI)

    Clapp, D.A.

    1995-01-01T23:59:59.000Z

    This document was developed to provide a facility description for those portions of the UO{sub 3} Facility being transferred to Bechtel Hanford Company, Inc. (BHI) following completion of facility deactivation. The facility and deactivated state condition description is intended only to serve as an overview of the plant as it is being transferred to BHI.

  15. In Situ TEM Observation of Dislocation Evolutionin Polycrystalline UO2

    SciTech Connect (OSTI)

    L. F. HE; 1 M. A. KIRK; Argonne National Laboratory; J. Gan; T. R. ALLEN

    2014-10-01T23:59:59.000Z

    In situ transmission electron microscopy observation of polycrystalline UO2 (with average grain size of about 5 lm) irradiated with Kr ions at 600C and 800C was conducted to understand the radiation-induced dislocation evolution under the influence of grain boundaries. The dislocation evolution in the grain interior of polycrystalline UO2 was similar under Kr irradiation at different ion energies and temperatures. As expected, it was characterized by the nucleation and growth of dislocation loops at low irradiation doses, followed by transformation to extended dislocation lines and tangles at high doses. For the first time, a dislocation-denuded zone was observed near a grain boundary in the 1-MeV Kr-irradiated UO2 sample at 800C. The denuded zone in the vicinity of grain boundary was not found when the irradiation temperature was at 600C. The suppression of dislocation loop formation near the boundary is likely due to the enhanced interstitial diffusion toward grain boundary at the high temperature.

  16. Molecular dynamics simulations of grain boundary thermal resistance in UO2

    SciTech Connect (OSTI)

    Tianyi Chen; Di Chen; Bulent H. Sencer; Lin Shao

    2014-09-01T23:59:59.000Z

    By means of molecular dynamics (MD) simulations, we have calculated Kaptiza resistance of UO2 with or without radiation damage. For coincident site lattice boundaries of different configurations, the boundary thermal resistance of unirradiated UO2 can be well described by a parameter-reduced formula by using boundary energies as variables. We extended the study to defect-loaded UO2 by introducing damage cascades in close vicinity to the boundaries. Following cascade annealing and defect migrations towards grain boundaries, the boundary energy increases and so does Kaptiza resistance. The correlations between these two still follow the same formula extracted from the unirradiated UO2. The finding will benefit multi-scale modeling of UO2 thermal properties under extreme radiation conditions by combining effects from boundary configurations and damage levels.

  17. PUREX/UO{sub 3} facilities deactivation lessons learned history

    SciTech Connect (OSTI)

    Hamrick, D.G.; Gerber, M.S.

    1995-01-01T23:59:59.000Z

    The Plutonium-Uranium Extraction (PUREX) Facility operated from 1956-1972, from 1983-1988, and briefly during 1989-1990 to produce for national defense at the Hanford Site in Washington State. The Uranium Trioxide (UO{sub 3}) Facility operated at the Hanford Site from 1952-1972, 1984-1988, and briefly in 1993. Both plants were ordered to permanent shutdown by the U.S. Department of Energy (DOE) in December 1992, thus initiating their deactivation phase. Deactivation is that portion of a facility`s life cycle that occurs between operations and final decontamination and decommissioning (D&D). This document details the history of events, and the lessons learned, from the time of the PUREX Stabilization Campaign in 1989-1990, through the end of the first full fiscal year (FY) of the deactivation project (September 30, 1994).

  18. Cation-Cation Interactions in [(UO2)2(OH)n](4-n) Complexes. ...

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

    and (UO2)2(OH)5- shows that the CCIs and bridging hydroxo between the dioxo-uranium units are mainly electrostatic in nature. Citation: Odoh SO, N Govind, G...

  19. INTERPRETATION OF TRACER SURFACE DIFFUSION EXPERIMENTS ON UO2 ROLES OF GAS AND SOLID TRANSPORT PROCESSES

    E-Print Network [OSTI]

    Olander, D.R.

    2013-01-01T23:59:59.000Z

    hydrogen. This extrapolation was made using Eq [2) and the values of the trans- port properties (hydrogen in the MK experiment means that the UO is probably not stoichiometric. That this transport property

  20. Modeling thermal conductivity in UO2 with BeO additions as a function of microstructure

    E-Print Network [OSTI]

    direction. Ó 2009 Elsevier B.V. All rights reserved. 1. Introduction Uranium dioxide (UO2) is the most gradients which affect heat removal and overall reactor performance. These thermal gradients strongly

  1. Etching of UO{sub 2} in NF{sub 3} RF Plasma Glow Discharge

    SciTech Connect (OSTI)

    John M. Veilleux

    1999-08-01T23:59:59.000Z

    A series of room temperature, low pressure (10.8 to 40 Pa), low power (25 to 210 W) RF plasma glow discharge experiments with UO{sub 2} were conducted to demonstrate that plasma treatment is a viable method for decontaminating UO{sub 2} from stainless steel substrates. Experiments were conducted using NF{sub 3} gas to decontaminate depleted uranium dioxide from stainless-steel substrates. Depleted UO{sub 2} samples each containing 129.4 Bq were prepared from 100 microliter solutions of uranyl nitrate hexahydrate solution. The amorphous UO{sub 2} in the samples had a relatively low density of 4.8 gm/cm{sub 3}. Counting of the depleted UO{sub 2} on the substrate following plasma immersion was performed using liquid scintillation counting with alpha/beta discrimination due to the presence of confounding beta emitting daughter products, {sup 234}Th and {sup 234}Pa. The alpha emission peak from each sample was integrated using a gaussian and first order polynomial fit to improve quantification. The uncertainties in the experimental measurement of the etched material were estimated at about {+-} 2%. Results demonstrated that UO{sub 2} can be completely removed from stainless-steel substrates after several minutes processing at under 200 W. At 180 W and 32.7 Pa gas pressure, over 99% of all UO{sub 2} in the samples was removed in just 17 minutes. The initial etch rate in the experiments ranged from 0.2 to 7.4 {micro}m/min. Etching increased with the plasma absorbed power and feed gas pressure in the range of 10.8 to 40 Pa. A different pressure effect on UO{sub 2} etching was also noted below 50 W in which etching increased up to a maximum pressure, {approximately}23 Pa, then decreased with further increases in pressure.

  2. Benchmarking of Graphite Reflected Critical Assemblies of UO2

    SciTech Connect (OSTI)

    Margaret A. Marshall; John D. Bess

    2011-11-01T23:59:59.000Z

    A series of experiments were carried out in 1963 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for use in space reactor research programs. A core containing 93.2% enriched UO2 fuel rods was used in these experiments. The first part of the experimental series consisted of 253 tightly-packed fuel rods (1.27 cm triangular pitch) with graphite reflectors [1], the second part used 253 graphite-reflected fuel rods organized in a 1.506 cm triangular pitch [2], and the final part of the experimental series consisted of 253 beryllium-reflected fuel rods with a 1.506 cm triangular pitch. [3] Fission rate distribution and cadmium ratio measurements were taken for all three parts of the experimental series. Reactivity coefficient measurements were taken for various materials placed in the beryllium reflected core. The first part of this experimental series has been evaluated for inclusion in the International Reactor Physics Experiment Evaluation Project (IRPhEP) [4] and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbooks, [5] and is discussed below. These experiments are of interest as benchmarks because they support the validation of compact reactor designs with similar characteristics to the design parameters for a space nuclear fission surface power systems. [6

  3. PUREX/UO3 Facilities deactivation lessons learned history

    SciTech Connect (OSTI)

    Gerber, M.S.

    1996-09-19T23:59:59.000Z

    Disconnecting the criticality alarm permanently in June 1996 signified that the hazards in the PUREX (plutonium-uranium extraction) plant had been so removed and reduced that criticality was no longer a credible event. Turning off the PUREX criticality alarm also marked a salient point in a historic deactivation project, 1 year before its anticipated conclusion. The PUREX/UO3 Deactivation Project began in October 1993 as a 5-year, $222.5- million project. As a result of innovations implemented during 1994 and 1995, the project schedule was shortened by over a year, with concomitant savings. In 1994, the innovations included arranging to send contaminated nitric acid from the PUREX Plant to British Nuclear Fuels, Limited (BNFL) for reuse and sending metal solutions containing plutonium and uranium from PUREX to the Hanford Site tank farms. These two steps saved the project $36.9- million. In 1995, reductions in overhead rate, work scope, and budget, along with curtailed capital equipment expenditures, reduced the cost another $25.6 million. These savings were achieved by using activity-based cost estimating and applying technical schedule enhancements. In 1996, a series of changes brought about under the general concept of ``reengineering`` reduced the cost approximately another $15 million, and moved the completion date to May 1997. With the total savings projected at about $75 million, or 33.7 percent of the originally projected cost, understanding how the changes came about, what decisions were made, and why they were made becomes important. At the same time sweeping changes in the cultural of the Hanford Site were taking place. These changes included shifting employee relations and work structures, introducing new philosophies and methods in maintaining safety and complying with regulations, using electronic technology to manage information, and, adopting new methods and bases for evaluating progress. Because these changes helped generate cost savings and were accompanied by and were an integral part of sweeping ``culture changes,`` the story of the lessons learned during the PUREX Deactivation Project are worth recounting. Foremost among the lessons is recognizing the benefits of ``right to left`` project planning. A deactivation project must start by identifying its end points, then make every task, budget, and organizational decision based on reaching those end points. Along with this key lesson is the knowledge that project planning and scheduling should be tied directly to costing, and the project status should be checked often (more often than needed to meet mandated reporting requirements) to reflect real-time work. People working on a successful project should never be guessing about its schedule or living with a paper schedule that does not represent the actual state of work. Other salient lessons were learned in the PUREX/UO3 Deactivation Project that support these guiding principles. They include recognizing the value of independent review, teamwork, and reengineering concepts; the need and value of cooperation between the DOE, its contractors, regulators, and stakeholders; and the essential nature of early and ongoing communication. Managing a successful project also requires being willing to take a fresh look at safety requirements and to apply them in a streamlined and sensible manner to deactivating facilities; draw on the enormous value of resident knowledge acquired by people over years and sometimes decades of working in old plants; and recognize the value of bringing in outside expertise for certain specialized tasks.This approach makes possible discovering the savings that can come when many creative options are pursued persistently and the wisdom of leaving some decisions to the future. The essential job of a deactivation project is to place a facility in a safe, stable, low-maintenance mode, for an interim period. Specific end points are identified to recognize and document this state. Keeping the limited objectives of the project in mind can guide decisions that reduce risks with minimal manipul

  4. Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets

    E-Print Network [OSTI]

    D. Tobia; E. L. Winkler; J. Milano; A. Butera; R. Kempf; L. Bianchi; F. Kaufmann

    2014-02-28T23:59:59.000Z

    A transversal mapping of the Gd concentration was measured in UO2-Gd2O3 nuclear fuel pellets by electron paramagnetic resonance spectroscopy (EPR). The quantification was made from the comparison with a Gd2O3 reference sample. The nominal concentration in the pellets is UO2: 7.5 % Gd2O3. A concentration gradient was found, which indicates that the Gd2O3 amount diminishes towards the edges of the pellets. The concentration varies from (9.3 +/- 0.5)% in the center to (5.8 +/- 0.3)% in one of the edges. The method was found to be particularly suitable for the precise mapping of the distribution of Gd3+ ions in the UO2 matrix.

  5. Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets

    E-Print Network [OSTI]

    Tobia, D; Milano, J; Butera, A; Kempf, R; Bianchi, L; Kaufmann, F

    2014-01-01T23:59:59.000Z

    A transversal mapping of the Gd concentration was measured in UO2-Gd2O3 nuclear fuel pellets by electron paramagnetic resonance spectroscopy (EPR). The quantification was made from the comparison with a Gd2O3 reference sample. The nominal concentration in the pellets is UO2: 7.5 % Gd2O3. A concentration gradient was found, which indicates that the Gd2O3 amount diminishes towards the edges of the pellets. The concentration varies from (9.3 +/- 0.5)% in the center to (5.8 +/- 0.3)% in one of the edges. The method was found to be particularly suitable for the precise mapping of the distribution of Gd3+ ions in the UO2 matrix.

  6. 12/21/2011 KWarden UO Policy Library Policy Revision and Update Guidelines

    E-Print Network [OSTI]

    Oregon, University of

    12/21/2011 ­ KWarden UO Policy Library Policy Revision and Update Guidelines Any Responsible Office, Policy Statement: Development and Management. The policy refers to two types of revisions: substantive: Development and Management, which is found in the Policy Library. Minor Revision or Update A minor revision

  7. Radiation-Induced Decomposition of U(VI) Phase to Nanocrystals of UO2

    SciTech Connect (OSTI)

    S. Utsunomiya; R.C. Ewing; L. Wang

    2005-06-13T23:59:59.000Z

    U{sup 6+}-phases are common alteration products, under oxidizing conditions, of uraninite and the UO{sub 2} in spent nuclear fuel. These U{sup 6+}-phases are subjected to a radiation field caused by the {alpha}-decay of U, or in the case of spent nuclear fuel, incorporated actinides, such as {sup 239}Pu and {sup 237}Np. In order to evaluate the effects of {alpha}-decay events on the stability of the U{sup 6+}-phases, we report, for the first time, the results of ion beam irradiations (1.0 MeV Kr{sup 2+}) of U{sup 6+}-phases. The heavy-particle irradiations are used to simulate the ballistic interactions of the recoil-nucleus of an {alpha}-decay event with the surrounding structure. The Kr{sup 2+}-irradiation decomposed the U{sup 6+}-phases to UO{sub 2} nanocrystals at doses as low as 0.006 displacements per atom (dpa). U{sup 6+}-phases accumulate substantial radiation doses ({approx}1.0 displacement per atom) within 100,000 years if the concentration of incorporated {sup 239}Pu is as high as 1 wt%. Similar nanocrystals of UO{sub 2} were observed in samples from the natural fission reactors at Oklo, Gabon. Multiple cycles of radiation-induced decomposition to UO{sub 2} followed by alteration to U{sup 6+}-phases provide a mechanism for the remobilization of incorporated radionuclides.

  8. additives doped-uo2 pellets: Topics by E-print Network

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

    additives doped-uo2 pellets First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Journal of Nuclear...

  9. UO Retirement Recognition Reception Pap Reception Hall, J.S. Museum of Art

    E-Print Network [OSTI]

    Oregon, University of

    UO Retirement Recognition Reception Papé Reception Hall, J.S. Museum of Art Thursday, June 16, 2011 Information Services 29½ Years Richard Edwards Early Childhood CARES 11 Years Kayla Hinds Architecture will not be attending the retirement reception. They asked that we announce their retirement. Robert Barton Theatre Arts

  10. f Fk66iCOP-] NBSIR 86-3422 uoL_ i 1

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    f Fk66iCOP-] NBSIR 86-3422 uoL_ i 1 The Performance of A Conventional Residential Sized Heat Pump RESIDENTIAL SIZED HEAT PUMP OPERATING WITH A NONAZEOTROPIC BINARY REFRIGERANT MIXTURE William Mulroy David unmodified residential heat pump designed for R22 when charged with a nonazeotropic refrigerant mixture (NARM

  11. UNIVERSITY OF OREGON SOLAR MONITORING LABORATORY The University of Oregon (UO) Solar Moni-

    E-Print Network [OSTI]

    Oregon, University of

    i UNIVERSITY OF OREGON SOLAR MONITORING LABORATORY The University of Oregon (UO) Solar Moni- toring Laboratory has been measuring incident solar radiation since 1975. Current support for this work comes from the Regional Solar Radiation Monitoring Project (RSRMP), a utility consortium project including the Bon

  12. Criticality experiments with low enriched UO/sub 2/ fuel rods in water containing dissolved gadolinium

    SciTech Connect (OSTI)

    Bierman, S.R.; Murphy, E.S.; Clayton, E.D.; Keay, R.T.

    1984-02-01T23:59:59.000Z

    The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. (BNFL) under contract with the United States Department of Energy (USDOE) are presented in this report along with a complete description of the experiments. The experiments involved low enriched UO/sub 2/ and PuO/sub 2/-UO/sub 2/ fuel rods in water containing dissolved gadolinium, and are in direct support of BNFL plans to use soluble compounds of the neutron poison gadolinium as a primary criticality safeguard in the reprocessing of low enriched nuclear fuels. The experiments were designed primarily to provide data for validating a calculation method being developed for BNFL design and safety assessments, and to obtain data for the use of gadolinium as a neutron poison in nuclear chemical plant operations - particularly fuel dissolution. The experiments program covers a wide range of neutron moderation (near optimum to very under-moderated) and a wide range of gadolinium concentration (zero to about 2.5 g Gd/l). The measurements provide critical and subcritical k/sub eff/ data (1 greater than or equal to k/sub eff/ greater than or equal to 0.87) on fuel-water assemblies of UO/sub 2/ rods at two enrichments (2.35 wt % and 4.31 wt % /sup 235/U) and on mixed fuel-water assemblies of UO/sub 2/ and PuO/sub 2/-UO/sub 2/ rods containing 4.31 wt % /sup 235/U and 2 wt % PuO/sub 2/ in natural UO/sub 2/ respectively. Critical size of the lattices was determined with water containing no gadolinium and with water containing dissolved gadolinium nitrate. Pulsed neutron source measurements were performed to determine subcritical k/sub eff/ values as additional amounts of gadolinium were successively dissolved in the water of each critical assembly. Fission rate measurements in /sup 235/U using solid state track recorders were made in each of the three unpoisoned critical assemblies, and in the near-optimum moderated and the close-packed poisoned assemblies of this fuel.

  13. Strong electron correlation in UO{sub 2}{sup ?}: A photoelectron spectroscopy and relativistic quantum chemistry study

    SciTech Connect (OSTI)

    Li, Wei-Li; Jian, Tian; Lopez, Gary V.; Wang, Lai-Sheng, E-mail: lai-sheng-wang@brown.edu [Department of Chemistry, Brown University, Providence, Rhode Island 02912 (United States)] [Department of Chemistry, Brown University, Providence, Rhode Island 02912 (United States); Su, Jing [Department of Chemistry and Key Laboratory of Organic Optoelectronics and Molecular Engineering of Ministry of Education, Tsinghua University, Beijing 100084 (China) [Department of Chemistry and Key Laboratory of Organic Optoelectronics and Molecular Engineering of Ministry of Education, Tsinghua University, Beijing 100084 (China); Division of Nuclear Materials Science and Engineering, Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China and Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Chinese Academy of Sciences, Shanghai 201800 (China); Hu, Han-Shi; Cao, Guo-Jin; Li, Jun, E-mail: junli@tsinghua.edu.cn [Department of Chemistry and Key Laboratory of Organic Optoelectronics and Molecular Engineering of Ministry of Education, Tsinghua University, Beijing 100084 (China)] [Department of Chemistry and Key Laboratory of Organic Optoelectronics and Molecular Engineering of Ministry of Education, Tsinghua University, Beijing 100084 (China)

    2014-03-07T23:59:59.000Z

    The electronic structures of actinide systems are extremely complicated and pose considerable challenges both experimentally and theoretically because of significant electron correlation and relativistic effects. Here we report an investigation of the electronic structure and chemical bonding of uranium dioxides, UO{sub 2}{sup ?} and UO{sub 2}, using photoelectron spectroscopy and relativistic quantum chemistry. The electron affinity of UO{sub 2} is measured to be 1.159(20) eV. Intense detachment bands are observed from the UO{sub 2}{sup ?} low-lying (7s?{sub g}){sup 2}(5f?{sub u}){sup 1} orbitals and the more deeply bound O2p-based molecular orbitals which are separated by a large energy gap from the U-based orbitals. Surprisingly, numerous weak photodetachment transitions are observed in the gap region due to extensive two-electron transitions, suggesting strong electron correlations among the (7s?{sub g}){sup 2}(5f?{sub u}){sup 1} electrons in UO{sub 2}{sup ?} and the (7s?{sub g}){sup 1}(5f?{sub u}){sup 1} electrons in UO{sub 2}. These observations are interpreted using multi-reference ab initio calculations with inclusion of spin-orbit coupling. The strong electron correlations and spin-orbit couplings generate orders-of-magnitude more detachment transitions from UO{sub 2}{sup ?} than expected on the basis of the Koopmans’ theorem. The current experimental data on UO{sub 2}{sup ?} provide a long-sought opportunity to arbitrating various relativistic quantum chemistry methods aimed at handling systems with strong electron correlations.

  14. UO{sub 2} corrosion in high surface-area-to-volume batch experiments.

    SciTech Connect (OSTI)

    Bates, J. K.; Finch, R. J.; Hanchar, J. M.; Wolf, S. F.

    1997-12-08T23:59:59.000Z

    Unsaturated drip tests have been used to investigate the alteration of unirradiated UO{sub 2} and spent UO{sub 2} fuel in an unsaturated environment such as may be expected in the proposed repository at Yucca Mountain. In these tests, simulated groundwater is periodically injected onto a sample at 90 C in a steel vessel. The solids react with the dripping groundwater and water condensed on surfaces to form a suite of U(VI) alteration phases. Solution chemistry is determined from leachate at the bottom of each vessel after the leachate stops interacting with the solids. A more detailed knowledge of the compositional evolution of the leachate is desirable. By providing just enough water to maintain a thin film of water on a small quantity of fuel in batch experiments, we can more closely monitor the compositional changes to the water as it reacts to form alteration phases.

  15. UO2 CORROSION IN HIGH SURFACE-AREA-TO-VOLUME BATCH EXPERIMENTS

    SciTech Connect (OSTI)

    Finch, Robert J.; Wolf, Stephen F.; Hanchar, John M.; Bates, John K.

    1998-05-11T23:59:59.000Z

    Unsaturated drip tests have been used to investigate the alteration of unirradiated UO{sub 2} and spent UO{sub 2} fuel in an unsaturated environment, such as may be expected in the proposed repository at Yucca Mountain. In these tests, simulated groundwater is periodically injected onto a sample at 90 C in a steel vessel. The solids react with the dripping groundwater and water condensed on surfaces to form a suite of U(VI) alteration phases. Solution chemistry is determined from leachate at the bottom of each vessel after the leachate stops interacting with the solids. A more detailed knowledge of the compositional evolution of the leachate is desirable. By providing just enough water to maintain a thin film of water on a small quantity of fuel in batch experiments, we can more closely monitor the compositional changes to the water as it reacts to form alteration phases.

  16. Bubble formation and Kr distribution in Kr-irradiated UO2

    SciTech Connect (OSTI)

    L.F. He; B. Valderrama; A.-R. Hassan; J. Yu; M. Gupta; J. Pakarinen; H.B. Henderson; J. Gan; M.A. Kirk; A.T. Nelson; M.V. Manuel; A. El-Azab; T.R. Allen

    2015-01-01T23:59:59.000Z

    In situ and ex situ transmission electron microscopy observation of small Kr bubbles in both single-crystal and polycrystalline UO2 were conducted to understand the inert gas bubble behavior in oxide nuclear fuel. The bubble size and volume swelling are shown as a weak function of ion dose but strongly depend on the temperature. The Kr bubble formation at room temperature was observed for the first time. The depth profiles of implanted Kr determined by atom probe tomography are in good agreement with the calculated profiles by SRIM, but the measured concentration of Kr is about 1/3 of calculated one. This difference is mainly due to low solubility of Kr in UO2 matrix, which has been confirmed by both density-functional theory calculations and chemical equilibrium analysis.

  17. Computational Investigation of the Formation of Hyper-stoichiometric Uranium Dioxide (UO{sub 2+x})

    SciTech Connect (OSTI)

    Skomurski, Frances; Becker, Udo; Ewing, Rodney [Geological Sciences, University of Michigan, 2534 C.C. Little Building, 1100 North University Ave., Ann Arbor, MI, 48109 (United States)

    2007-07-01T23:59:59.000Z

    Understanding the mechanisms behind the formation of hyper-stoichiometric UO{sub 2} phases is important because oxidation of uranium atoms upon the addition of excess oxygen to the UO{sub 2} structure leads to volume changes that increase the susceptibility of spent fuel to corrosion. While a variety of diffraction and spectroscopic studies have been used to investigate structural changes as UO{sub 2} oxidizes to U{sub 4}O{sub 9}, the effect of interstitial oxygen on the charge distribution of uranium in hyper-stoichiometric UO{sub 2} remains inconclusive. In this study, quantum mechanical techniques were used to model the effects of interstitial oxygen on the structure and charge distribution of atoms in a simplified U{sub 4}O{sub 9} unit cell. A density functional theory-based approach was used to optimize the geometry and charge distribution of a variety of U{sub 4}O{sub 9} starting models with different U{sup 4+}, U{sup 5+} and U{sup 6+} charge configurations. Results from our calculations suggest that the formation of one U{sup 5+} per addition of interstitial oxygen at a perpendicular bisector site is favorable; this oxidation event is accompanied by partial reduction of the interstitial oxygen atom. Deflection of two lattice oxygen atoms along the body diagonal of the cubic site surrounding the U{sup 5+} is also observed upon the addition of one interstitial oxygen atom. Structural and bond length data are compared with experimental data whenever possible. (authors)

  18. Sensitivity of UO2 Stability in a Reducing Environment on Radiolysis Model Parameters

    SciTech Connect (OSTI)

    Wittman, Richard S.; Buck, Edgar C.

    2012-09-01T23:59:59.000Z

    Results for a radiolysis model sensitivity study of radiolytically produced H2O2 are presented as they relate to Spent (or Used) Light Water Reactor uranium oxide (UO2) nuclear fuel (UNF) oxidation in a low oxygen environment. The model builds on previous reaction kinetic studies to represent the radiolytic processes occurring at the nuclear fuel surface. Hydrogen peroxide (H2O2) is the dominant oxidant for spent nuclear fuel in an O2-depleted water environment.

  19. Recovery of UO[sub 2]/PuO[sub 2] in IFR electrorefining process

    DOE Patents [OSTI]

    Tomczuk, Z.; Miller, W.E.

    1994-10-18T23:59:59.000Z

    A process is described for converting PuO[sub 2] and UO[sub 2] present in an electrorefiner to the chlorides, by contacting the PuO[sub 2] and UO[sub 2] with Li metal in the presence of an alkali metal chloride salt substantially free of rare earth and actinide chlorides for a time and at a temperature sufficient to convert the UO[sub 2] and PuO[sub 2] to metals while converting Li metal to Li[sub 2]O. Li[sub 2]O is removed either by reducing with rare earth metals or by providing an oxygen electrode for transporting O[sub 2] out of the electrorefiner and a cathode, and thereafter applying an emf to the electrorefiner electrodes sufficient to cause the Li[sub 2]O to disassociate to O[sub 2] and Li metal but insufficient to decompose the alkali metal chloride salt. The U and Pu and excess lithium are then converted to chlorides by reaction with CdCl[sub 2].

  20. Recovery of UO.sub.2 /Pu O.sub.2 in IFR electrorefining process

    DOE Patents [OSTI]

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

    1994-01-01T23:59:59.000Z

    A process for converting PuO.sub.2 and UO.sub.2 present in an electrorefiner to the chlorides, by contacting the PuO.sub.2 and UO.sub.2 with Li metal in the presence of an alkali metal chloride salt substantially free of rare earth and actinide chlorides for a time and at a temperature sufficient to convert the UO.sub.2 and PuO.sub.2 to metals while converting Li metal to Li.sub.2 O. Li.sub.2 O is removed either by reducing with rare earth metals or by providing an oxygen electrode for transporting O.sub.2 out of the electrorefiner and a cathode, and thereafter applying an emf to the electrorefiner electrodes sufficient to cause the Li.sub.2 O to disassociate to O.sub.2 and Li metal but insufficient to decompose the alkali metal chloride salt. The U and Pu and excess lithium are then converted to chlorides by reaction with CdCl.sub.2.

  1. Leaching patterns and secondary phase formation during unsaturated leaching of UO{sub 2} at 90{degrees}C

    SciTech Connect (OSTI)

    Wronkiewicz, D.J.; Bates, J.K.; Gerding, T.J.; Veleckis, E.; Tani, B.S.

    1991-11-01T23:59:59.000Z

    Experiments are being conducted that examine the reaction of UO{sub 2} with dripping oxygenated ground water at 90{degrees}C. The experiments are designed to identify secondary phases formed during UO{sub 2} alteration, evaluate parameters controlling U release, and act as scoping tests for studies with spent fuel. This study is the first of its kind that examines the alteration of UO{sub 2} under unsaturated conditions expected to exist at the proposed Yucca Mountain repository site. Results suggest the UO{sub 2} matrix will readily react within a few months after being exposed to simulated Yucca Mountain conditions. A pulse of rapid U release, combined with the formation of dehydrated schoepite on the UO{sub 2} surface, characterizes the reaction between one to two years. Rapid dissolution of intergrain boundaries and spallation of UO{sub 2} granules appears to be responsible for much of the U released. Differential release of the UO{sub 2} granules may be responsible for much of the variation observed between duplicate experiments. Less than 5 wt % of the released U remains in solution or in a suspended form, while the remaining settles out of solution as fine particles or is reprecipitated as secondary phases. Subsequent to the pulse period, U release rates decline and a more stable assemblage of uranyl silicate phases are formed by incorporating cations from the ground water leachant. Uranophane, boltwoodite, and sklodowskite appear as the final solubility limiting phases that form in these tests. This observed paragenetic sequence (from uraninite to schoepite-type phases to uranyl silicates) is identical to those observed in weathered zones of natural uraninite occurrences. The combined results indicate that the release of radionuclides from spent fuel may not be limited by U solubility constraints, but that spallation of particulate matter may be an important, if not the dominant release mechanism affecting release.

  2. Feasibility of Partial ZrO[subscript 2] Coatings on Outer Surface of Annular UO[subscript 2] Pellets to Control Gap Conductance

    E-Print Network [OSTI]

    Feinroth, H.

    The viability of depositing a thin porous coating of zirconia on the outer surface of an annular UO[subscript 2] pellet

  3. Identification of secondary phases formed during unsaturated reaction of UO{sub 2} with EJ-13 water

    SciTech Connect (OSTI)

    Bates, J.K.; Tani, B.S.; Veleckis, E.

    1989-11-01T23:59:59.000Z

    A set of experiments, wherein UO{sub 2} has been contacted by dripping water, has been conducted over a period of 182.5 weeks. The experiments are being conducted to develop procedures to study spent fuel reaction under unsaturated conditions that are expected to exist over the lifetime of the proposed Yucca Mountain repository site. One half of the experiments have been terminated, while one half are ongoing. Analyses of solutions that have dripped from the reacted UO{sub 2} have been performed for all experiments, while the reacted UO{sub 2} surfaces have been examined for the terminated experiments. A pulse of uranium release from the UO{sub 2} solid, combined with the formation of schoepite on the surface of the UO{sub 2}, was observed between 39 and 96 weeks of reaction. Thereafter, the uranium release decreased and a second set of secondary phases was observed. The latter phases incorporated cations from the EJ-13 water and included boltwoodite, uranophane, sklodowskite, compreignacite, and schoepite. The experiments are continuing to monitor whether additional changes in solution chemistry or secondary phase formation occurs. 6 refs., 2 figs., 2 tabs.

  4. Identification of secondary phases formed during unsaturated reaction of UO{sub 2} with EJ-13 water

    SciTech Connect (OSTI)

    Bates, J.K.; Tani, B.S.; Veleckis, E.; Wronkiewicz, D.J. [Argonne National Lab., IL (USA)

    1990-12-31T23:59:59.000Z

    A set of experiments, wherein UO{sub 2} has been contacted by dripping water, has been conducted over a period of 182.5 weeks. The experiments are being conducted to develop procedures to study spent fuel reaction under unsaturated conditions that are expected to exist over the lifetime of the proposed Yucca Mountain repository site. One half of the experiments have been terminated, while one half are ongoing. Analyses of solutions that have dripped from the reacted UO{sub 2} have been performed for all experiments, while reacted UO{sub 2} surfaces have been examined for the terminated experiments. A pulse of uranium release from the UO{sub 2} solid, combined with the formation of schoepite on the surface of the UO{sub 2}, was observed between 39 and 96 weeks of reaction. Thereafter, the uranium release decreased and a second set of secondary phases was observed. The latter phases incorporated cations from the EJ-13 water and include boltwoodite, uranophane, sklodowskite, compreignacite, and schoepite. The experiments are continuing to monitor whether additional changes in solution chemistry or secondary phase formation occurs.

  5. Assessment of structures and stabilities of defect clusters and surface energies predicted by nine interatomic potentials for UO2

    SciTech Connect (OSTI)

    Stephen A. Taller; Xian-Ming Bai

    2013-11-01T23:59:59.000Z

    The irradiation in nuclear reactors creates many point defects and defect clusters in uranium dioxide (UO2) and their evolution severely degrades the thermal and mechanical properties of the nuclear fuels. Previously many empirical interatomic potentials have been developed for modeling defect production and evolution in UO2. However, the properties of defect clusters and extended defects are usually not fitted into these potentials. In this work nine interatomic potentials for UO2 are examined by using molecular statics and molecular dynamics to assess their applicability in predicting the properties of various types of defect clusters in UO2. The binding energies and structures for these defect clusters have been evaluated for each potential. In addition, the surface energies of voids of different radii and (1 1 0) flat surfaces predicted by these potentials are also evaluated. It is found that both good agreement and significant discrepancies exist for these potentials in predicting these properties. For oxygen interstitial clusters, these potentials predict significantly different defect cluster structures and stabilities; For defect clusters consisting of both uranium and oxygen defects, the prediction is in better agreement; The surface energies predicted by these potentials have significant discrepancies, and some of them are much higher than the experimentally measured values. The results from this work can provide insight on interpreting the outcome of atomistic modeling of defect production using these potentials and may provide guidelines for choosing appropriate potential models to study problems of interest in UO2.

  6. Excited States and Luminescent Properties of UO2F2 and Its Solvated Complexes in Aqueous Solution

    SciTech Connect (OSTI)

    Su, Jing; Wang, Zheming; Pan, Duoqiang; Li, Jun

    2014-08-20T23:59:59.000Z

    The electronic absorption and emission spectra of free UO2F2 and its water solvated complexes below 32,000 cm?1 are investigated at the levels of ab initio CASPT2 and CCSD(T) with inclusion of scalar relativistic and spin-orbit coupling effects. The influence of the water coordination on the electronic spectra of UO2F2 is explored by investigating the excited states of solvated complexes (H2O)nUO2F2 (n = 1?3). In these uranyl-complexes, water coordination is found to have appreciable influence on the 3? (? = 1g) character of the luminescent state and on the electronic spectral shape. The simulated luminescence spectral curves based on the calculated spectral parameters of (H2O)nUO2F2 from CCSD(T) approach agree well with experimental spectra in aqueous solution at both near liquid helium temperature and room temperature. The possible luminescence spectra of free UO2F2 in gas phase are predicted based on CASPT2 and CCSD(T) results, respectively, by considering three symmetric vibration modes. The effect of competition between spin-orbital coupling and ligand field repulsion on the luminescent state properties is discussed.

  7. Vibrational Spectroscopy of Mass Selected [UO2(ligand)n]2+ Complexes in the Gas Phase

    SciTech Connect (OSTI)

    Gary S. Groenewold; Anita Gianotto; Michael Vanstipdonk; Kevin C. Cossel; David T. Moore,; Nick Polfer; Jos Oomens

    2006-03-01T23:59:59.000Z

    The gas-phase infrared spectra of discrete uranyl ([UO2]2+) complexes ligated with acetone and/or acetonitrile were used to evaluate systematic trends of ligation on the position of the O=U=O stretch, and to enable rigorous comparison with the results of computational studies. Ionic uranyl complexes isolated in a Fourier transform ion cyclotron resonance mass spectrometer were fragmented via infrared multiphoton dissociation using a free electron laser scanned over the mid-IR wavelengths. The asymmetric O=U=O stretching frequency was measured at 1017 cm-1 for [UO2(CH3COCH3)2]2+, and was systematically red shifted to 1000 and 988 cm-1 by the addition of a third and fourth acetone ligands, respectively, which was consistent with more donation of electron density to the uranium center in complexes with higher coordination number. The experimental measurements were in good agreement with values generated computationally using LDA, B3LYP, and ZORA-PW91 approaches. In contrast to the uranyl frequency shifts, the carbonyl frequencies of the acetone ligands were progressively blue shifted as the number of ligands increased from 2 to 4, and approached that of free acetone. This observation was consistent with the formation of weaker noncovalent bonds between uranium and the carbonyl oxygen as the extent of ligation increases. Similar trends were observed for [UO2(CH3CN)n]2+ complexes although the magnitude of the red shift in the uranyl frequency upon addition more acetonitrile ligands was smaller than for acetone, consistent with the more modest nucleophilic nature of acetonitrile. This conclusion was amplified by the uranyl stretching frequencies measured for mixed acetone/acetonitrile complexes, which showed that substitution of one acetone for one acetonitrile produced a modest red shift of 3 to 6 cm-1.

  8. Solar and Photovoltaic Data from the University of Oregon Solar Radiation Monitoring Laboratory (UO SRML)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    The UO SRML is a regional solar radiation data center whose goal is to provide sound solar resource data for planning, design, deployment, and operation of solar electric facilities in the Pacific Northwest. The laboratory has been in operation since 1975. Solar data includes solar resource maps, cumulative summary data, daily totals, monthly averages, single element profile data, parsed TMY2 data, and select multifilter radiometer data. A data plotting program and other software tools are also provided. Shade analysis information and contour plots showing the effect of tilt and orientation on annual solar electric system perfomance make up a large part of the photovoltaics data.(Specialized Interface)

  9. An Overview of Current and Past W-UO[2] CERMET Fuel Fabrication Technology

    SciTech Connect (OSTI)

    Douglas E. Burkes; Daniel M. Wachs; James E. Werner; Steven D. Howe

    2007-06-01T23:59:59.000Z

    Studies dating back to the late 1940s performed by a number of different organizations and laboratories have established the major advantages of Nuclear Thermal Propulsion (NTP) systems, particularly for manned missions. A number of NTP projects have been initiated since this time; none have had any sustained fuel development work that appreciably contributed to fuel fabrication or performance data from this era. As interest in these missions returns and previous space nuclear power researchers begin to retire, fuel fabrication technologies must be revisited, so that established technologies can be transferred to young researchers seamlessly and updated, more advanced processes can be employed to develop successful NTP fuels. CERMET fuels, specifically W-UO2, are of particular interest to the next generation NTP plans since these fuels have shown significant advantages over other fuel types, such as relatively high burnup, no significant failures under severe transient conditions, capability of accommodating a large fission product inventory during irradiation and compatibility with flowing hot hydrogen. Examples of previous fabrication routes involved with CERMET fuels include hot isostatic pressing (HIPing) and press and sinter, whereas newer technologies, such as spark plasma sintering, combustion synthesis and microsphere fabrication might be well suited to produce high quality, effective fuel elements. These advanced technologies may address common issues with CERMET fuels, such as grain growth, ductile to brittle transition temperature and UO2 stoichiometry, more effectively than the commonly accepted ‘traditional’ fabrication routes. Bonding of fuel elements, especially if the fabrication process demands production of smaller element segments, must be investigated. Advanced brazing techniques and compounds are now available that could produce a higher quality bond segment with increased ease in joining. This paper will briefly address the history of CERMET fuel fabrication technology as related to the GE 710 and ANL Nuclear Rocket Programs, in addition to discussing future plans, viable alternatives and preliminary investigations for W-UO2 CERMET fuel fabrication. The intention of the talk is to provide the brief history and tie in an overview of current programs and investigations as related to NTP based W-UO2 CERMET fuel fabrication, and hopefully peak interest in advanced fuel fabrication technologies.

  10. Nuclear data uncertainties by the PWR MOX/UO{sub 2} core rod ejection benchmark

    SciTech Connect (OSTI)

    Pasichnyk, I.; Klein, M.; Velkov, K.; Zwermann, W.; Pautz, A. [Boltzmannstr. 14, D-85748 Garching b. Muenchen (Germany)

    2012-07-01T23:59:59.000Z

    Rod ejection transient of the OECD/NEA and U.S. NRC PWR MOX/UO{sub 2} core benchmark is considered under the influence of nuclear data uncertainties. Using the GRS uncertainty and sensitivity software package XSUSA the propagation of the uncertainties in nuclear data up to the transient calculations are considered. A statistically representative set of transient calculations is analyzed and both integral as well as local output quantities are compared with the benchmark results of different participants. It is shown that the uncertainties in nuclear data play a crucial role in the interpretation of the results of the simulation. (authors)

  11. Grain boundary corrosion and alteration phase formation during the oxidative dissolution of UO{sub 2} pellets

    SciTech Connect (OSTI)

    Wronkiewicz, D.J.; Buck, E.C.; Bates, J.K.

    1996-12-31T23:59:59.000Z

    Alteration behavior of UO{sub 2} pellets following reaction under unsaturated drip-test conditions at 90 C for up to 10 years was examined by solid phase and leachate analyses. Sample reactions were characterized by preferential dissolution of grain boundaries between the original press-sintered UO{sub 2} granules comprising the samples, development of a polygonal network of open channels along the intergrain boundaries, and spallation of surface granules that had undergone severe grain boundary corrosion. The development of a dense mat of alteration phases after 2 years of reaction trapped loose granules, resulting in reduced rates of particulate U release. The paragenetic sequence of alteration phases that formed on the present samples was similar to that observed in surficial weathering zones of natural uraninite (UO{sub 2}) deposits, with alkali and alkaline earth uranyl silicates representing the long-term solubility-limiting phases for U in both systems.

  12. Evaluation of Heterogeneous Options: Effects of MgO versus UO2 Matrix Selection for Minor Actinide Targets in a Sodium Fast Reactor

    SciTech Connect (OSTI)

    M. Pope; S. Bays; R. Ferrer

    2008-03-01T23:59:59.000Z

    The primary focus of this work was to compare MgO with UO2 as target matrix material options for burning minor actinides in a transmutation target within a sodium fast reactor. This analysis compared the transmutation performance of target assemblies having UO2 matrix to those having specifically MgO inert matrix.

  13. Dissolution characteristics of mixed UO{sub 2} powders in J-13 water under saturated conditions

    SciTech Connect (OSTI)

    Veleckis, E.; Hoh, J.C.

    1991-03-01T23:59:59.000Z

    The Yucca Mountain Project/Spent Fuel program at Argonne National Laboratory is designed to determine radionuclide release rates by exposing high-level waste to repository-relevant groundwater. To gain experience for the tests with spent fuel, a scoping experiment was conducted at room temperature to determine the uranium release rate from an unirradiated UO{sub 2} powder mixture (14.3 wt % enrichment in {sup 235}U) to J-13 water under saturated conditions. Another goal set for the experiment was to develop a method for utilizing isotope dilution techniques to determine whether the dissolution rate of UO{sub 2} matrix is in accordance with an existing kinetic model. Results of these analyses revealed unequal uranium dissolution rates from the enriched and depleted portions of the powder mixture because of undisclosed differences between them. Although the presence of this inhomogeneity has precluded the application of the kinetic model, it also provided an opportunity to elaborate on the utilization of isotope dilution data in recognizing and quantifying such conditions. Detailed listings of uranium release and solution chemistry data are presented. Other problems commonly associated with spent fuel, such as the effectiveness of filtering media, the existence of uranium concentration peaks during early stages of the leach tests, the need for concentration corrections due to water replenishments of sample volumes, and experience derived from isotope dilution data are discussed in the context of the present results. 10 refs., 5 figs., 7 tabs.

  14. High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication

    E-Print Network [OSTI]

    Naramore, Michael J

    2010-08-03T23:59:59.000Z

    The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxide (UO2) is a very effective nuclear fuel, but it’s performance is limited by its low thermal conductivity. The fuel concept considered here is a...

  15. High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication 

    E-Print Network [OSTI]

    Naramore, Michael J

    2010-08-03T23:59:59.000Z

    The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxide (UO2) is a very effective nuclear fuel, but it’s performance is limited by its low thermal conductivity. The fuel concept considered here is a...

  16. Forest transitions and ecosystem services in Zimbabwe Supervisors: Dr Casey Ryan (UoE), Dr Isla Grundy (University of Zimbabwe)

    E-Print Network [OSTI]

    Forest transitions and ecosystem services in Zimbabwe Supervisors: Dr Casey Ryan (UoE), Dr Isla and a variety of other ecosystem services. However the expansion of agricultural land and the curing of tobacco is accelerating deforestation and forest degradation rates. These structural changes to the ecosystem threaten

  17. A Study of UO2 Grain Boundary Structure and Thermal Resistance Change under Irradiation using Molecular Dynamics Simulations 

    E-Print Network [OSTI]

    Chen, Tianyi

    2013-08-02T23:59:59.000Z

    showing formation of intermetallic phases ........................................................................................................... 12 Figure 2.1 The thermal conductivity of UO2 as a function on temperature .................... 15... in the fissile materials creates localized heating in the fuel element, which is transferred to a coolant, and then be used to produce mechanical energy and ultimately electricity. Understanding the properties and behaviors of these fissile material compounds...

  18. THE ELECTRON AFFINITY OF UO E.B. Rudnyi, E.A. Kaibicheva, L.N. Sidorov

    E-Print Network [OSTI]

    Rudnyi, Evgenii B.

    THE ELECTRON AFFINITY OF UO 3 * E.B. Rudnyi, E.A. Kaibicheva, L.N. Sidorov Department of Chemistry keywords - negative ions, uranium oxide, electron affinity, ion - molecule equilibria, high temperature stronger than fluorides. The uranium oxide lies aside from other molecules in -1 table 1. High electron

  19. NEAMS FPL M2 Milestone Report: Development of a UO? Grain Size Model using Multicale Modeling and Simulation

    SciTech Connect (OSTI)

    Michael R Tonks; Yongfeng Zhang; Xianming Bai

    2014-06-01T23:59:59.000Z

    This report summarizes development work funded by the Nuclear Energy Advanced Modeling Simulation program's Fuels Product Line (FPL) to develop a mechanistic model for the average grain size in UO? fuel. The model is developed using a multiscale modeling and simulation approach involving atomistic simulations, as well as mesoscale simulations using INL's MARMOT code.

  20. Fire hazards analysis for the uranium oxide (UO{sub 3}) facility

    SciTech Connect (OSTI)

    Wyatt, D.M.

    1994-12-06T23:59:59.000Z

    The Fire Hazards Analysis (FHA) documents the deactivation end-point status of the UO{sub 3} complex fire hazards, fire protection and life safety systems. This FHA has been prepared for the Uranium Oxide Facility by Westinghouse Hanford Company in accordance with the criteria established in DOE 5480.7A, Fire Protection and RLID 5480.7, Fire Protection. The purpose of the Fire Hazards Analysis is to comprehensively and quantitatively assess the risk from a fire within individual fire areas in a Department of Energy facility so as to ascertain whether the objectives stated in DOE Order 5480.7, paragraph 4 are met. Particular attention has been paid to RLID 5480.7, Section 8.3, which specifies the criteria for deactivating fire protection in decommission and demolition facilities.

  1. D9 experiment: heat removal from stratified UO/sub 2/ debris

    SciTech Connect (OSTI)

    Ottinger, C A; Mitchell, G W; Lipinski, R J; Kelly, J E

    1985-04-01T23:59:59.000Z

    The D9 experiment investigated the coolability of a shallow (77 mm), stratified urania bed in sodium. The bed was fission heated in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories to simulate the effects of radioactive decay heating. It was the first stratified debris bed experiment to use an extended UO/sub 2/ particle size distribution (0.038 to 4.0 mm). Dryout occurred at powers ranging from 0.10 to 0.58 W/g, which was close to the incipient boiling power and before channels penetrated the subcooled zone in the bed, even with subcoolings as low as 80/sup 0/C. Channel penetration was observed after dryout began, but the bed became only moderately more coolable. All these observations agree with current models.

  2. The Effect Of Ion Implantation Of Selected Dopants On Some Of The Electrical Properties Of UO2

    SciTech Connect (OSTI)

    Haire, M. J.; von Roedern, R. J.; Meek, T. T.; Tesmer, J.; Wetteland, C.

    2003-02-25T23:59:59.000Z

    The United States Department of Energy (DOE) has {approx}1 billion pounds of surplus depleted uranium (i.e., uranium tails) from uranium gaseous diffusion enrichment facilities. Rather than treating this material as waste, DOE is investigating potential beneficial uses for this uranium. Of the many possible uses, uranium dioxide (UO2) has properties that make it an equal to or better than conventional photovoltaic (e.g., solar cell) materials. For example, the electronic bandgap of UO2 occurs at an efficiency equal to that of GaS and Si, and it has five radiation adsorption peaks instead of one. This paper describes the experimental work being conducted to develop urania photovoltaic devices.

  3. RADIATION-INDUCED DECOMPOSITION OF U(VI) ALTERATION PHASES OF UO2

    SciTech Connect (OSTI)

    S. Utsunomiya; R.C. Ewing

    2005-09-08T23:59:59.000Z

    U{sup 6+}-phases are common alteration products of spent nuclear fuel under oxidizing conditions, and they may potentially incorporate actinides, such as long-lived {sup 239}Pu and {sup 237}Np, delaying their transport to the biosphere. In order to evaluate the ballistic effects of {alpha}-decay events on the stability of the U{sup 6+}-phases, we report, for the first time, the results of ion beam irradiations (1.0 MeV Kr{sup 2+}) for six different structures of U{sup 6+}-phases: uranophane, kasolite, boltwoodite, saleeite, carnotite, and liebigite. The target uranyl-minerals were characterized by powder X-ray diffraction and identification confirmed by SAED (selected area electron diffraction) in TEM (transmission electron microscopy). The TEM observation revealed no initial contamination of uraninite in these U{sup 6+} phases. All of the samples were irradiated with in situ TEM observation using 1.0 MeV Kr{sup 2+} in the IVEM (intermediate-voltage electron microscope) at the IVEM-Tandem Facility of Argonne National Laboratory. The ion flux was 6.3 x 10{sup 11} ions/cm{sup 2}/sec. The specimen temperatures during irradiation were 298 and 673 K, respectively. The Kr{sup 2+}-irradiation decomposed the U{sup 6+}-phases to nanocrystals of UO{sub 2} at doses as low as 0.006 dpa. The cumulative doses for the pure U{sup 6+}-phases, e.g., uranophane, at 0.1 and 1 million years (m.y.) are calculated to be 0.009 and 0.09 dpa using SRIM2003. However, with the incorporation of 1 wt.% {sup 239}Pu, the calculated doses reach 0.27 and {approx}1.00 dpa in ten thousand and one hundred thousand years, respectively. Under oxidizing conditions, multiple cycles of radiation-induced decomposition to UO{sub 2} followed by alteration to U{sup 6+}-phases should be further investigated to determine the fate of trace elements that may have been incorporated in the U{sup 6+}-phases.

  4. A Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments

    SciTech Connect (OSTI)

    Phillippe, Aaron M [ORNL; Clarno, Kevin T [ORNL; Banfield, James E [ORNL; Ott, Larry J [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Hamilton, Steven P [ORNL

    2014-01-01T23:59:59.000Z

    The IFA-432 (Integrated Fuel Assessment) experiments from the International Fuel Performance Experiments (IFPE) database were designed to study the effects of gap size, fuel density, and fuel densification on fuel centerline temperature in light-water-reactor fuel. An evaluation of nuclear fuel pin heat transfer in the FRAPCON-3.4 and Exnihilo codes for uranium dioxide (UO$_2$) fuel systems was performed, with a focus on the densification stage (2.2 \\unitfrac{GWd}{MT(UO$_{2}$)}). In addition, sensitivity studies were performed to evaluate the effect of the radial power shape and approximations to the geometry to account for the thermocouple hole. The analysis demonstrated excellent agreement for rods 1, 2, 3, and 5 (varying gap thicknesses and density with traditional fuel), demonstrating the accuracy of the codes and their underlying material models for traditional fuel. For rod 6, which contained unstable fuel that densified an order of magnitude more than traditional, stable fuel, the magnitude of densification was over-predicted and the temperatures were outside of the experimental uncertainty. The radial power shape within the fuel was shown to significantly impact the predicted centerline temperatures, whereas modeling the fuel at the thermocouple location as either annular or solid was relatively negligible. This has provided an initial benchmarking of the pin heat transfer capability of Exnihilo for UO$_2$ fuel with respect to a well-validated nuclear fuel performance code.

  5. Development of an Innovative High-Thermal Conductivity UO2 Ceramic Composites Fuel Pellets with Carbon Nano-Tubes Using Spark Plasma Sintering

    SciTech Connect (OSTI)

    Subhash, Ghatu; Wu, Kuang-Hsi; Tulenko, James

    2014-03-10T23:59:59.000Z

    Uranium dioxide (UO2) is the most common fuel material in commercial nuclear power reactors. Despite its numerous advantages such as high melting point, good high-temperature stability, good chemical compatibility with cladding and coolant, and resistance to radiation, it suffers from low thermal conductivity that can result in large temperature gradients within the UO2 fuel pellet, causing it to crack and release fission gases. Thermal swelling of the pellets also limits the lifetime of UO2 fuel in the reactor. To mitigate these problems, we propose to develop novel UO2 fuel with uniformly distributed carbon nanotubes (CNTs) that can provide high-conductivity thermal pathways and can eliminate fuel cracking and fission gas release due to high temperatures. CNTs have been investigated extensively for the past decade to explore their unique physical properties and many potential applications. CNTs have high thermal conductivity (6600 W/mK for an individual single- walled CNT and >3000 W/mK for an individual multi-walled CNT) and high temperature stability up to 2800°C in vacuum and about 750°C in air. These properties make them attractive candidates in preparing nano-composites with new functional properties. The objective of the proposed research is to develop high thermal conductivity of UO2–CNT composites without affecting the neutronic property of UO2 significantly. The concept of this goal is to utilize a rapid sintering method (5–15 min) called spark plasma sintering (SPS) in which a mixture of CNTs and UO2 powder are used to make composites with different volume fractions of CNTs. Incorporation of these nanoscale materials plays a fundamentally critical role in controlling the performance and stability of UO2 fuel. We will use a novel in situ growth process to grow CNTs on UO2 particles for rapid sintering and develop UO2-CNT composites. This method is expected to provide a uniform distribution of CNTs at various volume fractions so that a high thermally conductive UO2-CNT composite is obtained with a minimal volume fraction of CNTs. The mixtures are sintered in the SPS facility at a range of temperatures, pressures, and time durations so as to identify the optimal processing conditions to obtain the desired microstructure of sintered UO2-CNT pellets. The second objective of the proposed work is to identify the optimal volume fraction of CNTs in the microstructure of the composites that provides the desired high thermal conductivity yet retaining the mechanical strength required for efficient function as a reactor fuel. We will systematically study the resulting microstructure (grain size, porosity, distribution of CNTs, etc.) obtained at various SPS processing conditions using optical microscopy, scanning electron microscopy (SEM), and transmission electron microscope (TEM). We will conduct indentation hardness measurements and uniaxial strength measurements as a function of volume fraction of CNTs to determine the mechanical strength and compare them to the properties of UO2. The fracture surfaces will be studied to determine the fracture characteristics that may relate to the observed cracking during service. Finally, we will perform thermal conductivity measurements on all the composites up to 1000° C. This study will relate the microstructure, mechanical properties, and thermal properties at various volume fractions of CNTs. The overall intent is to identify optimal processing conditions that will provide a well-consolidated compact with optimal microstructure and thermo-mechanical properties. The deliverables include: (1) fully characterized UO2-CNT composite with optimal CNT volume fraction and high thermal conductivity and (2) processing conditions for production of UO2-CNT composite pellets using SPS method.

  6. Intergranular fracture in UO2: derivation of traction-separation law from atomistic simulations

    SciTech Connect (OSTI)

    Yongfeng Zhang; Paul C Millett; Michael R Tonks; Xian-Ming Bai; S Bulent Biner

    2013-10-01T23:59:59.000Z

    In this study, the intergranular fracture behavior of UO2 was studied by molecular dynamics simulations using the Basak potential. In addition, the constitutive traction-separation law was derived from atomistic data using the cohesive-zone model. In the simulations a bicrystal model with the (100) symmetric tilt E5 grain boundaries was utilized. Uniaxial tension along the grain boundary normal was applied to simulate Mode-I fracture. The fracture was observed to propagate along the grain boundary by micro-pore nucleation and coalescence, giving an overall intergranular fracture behavior. Phase transformations from the Fluorite to the Rutile and Scrutinyite phases were identified at the propagating crack tips. These new phases are metastable and they transformed back to the Fluorite phase at the wake of crack tips as the local stress concentration was relieved by complete cracking. Such transient behavior observed at atomistic scale was found to substantially increase the energy release rate for fracture. Insertion of Xe gas into the initial notch showed minor effect on the overall fracture behavior.

  7. Interface control document between PUREX/UO{sub 3} Plant Transition and Solid Waste Disposal Division

    SciTech Connect (OSTI)

    Duncan, D.R.

    1994-06-30T23:59:59.000Z

    This interface control document (ICD) between PUREX/UO{sub 3} Plant Transition (PPT) and Solid Waste Disposal Division (SWD) establishes at a top level the functional responsibilities of each division where interfaces exist between the two divisions. Since the PUREX Transition and Solid Waste Disposal divisions operate autonomously, it is important that each division has a clear understanding of the other division`s expectations regarding these interfaces. This ICD primarily deals with solid wastes generated by the PPT. In addition to delineating functional responsibilities, the ICD includes a baseline description of those wastes that will require management as part of the interface between the divisions. The baseline description of wastes includes waste volumes and timing for use in planning the proper waste management capabilities: the primary purpose of this ICD is to ensure defensibility of expected waste stream volumes and Characteristics for future waste management facilities. Waste descriptions must be as complete as-possible to ensure adequate treatment, storage, and disposal capability will exist. The ICD also facilitates integration of existing or planned waste management capabilities of the PUREX. Transition and Solid Waste Disposal divisions. The ICD does not impact or affect the existing processes or procedures for shipping, packaging, or approval for shipping wastes by generators to the Solid Waste Division.

  8. Molecular dynamics simulations of intergranular fracture in UO2 with nine empirical interatomic potentials

    SciTech Connect (OSTI)

    Yongfeng Zhang; Paul C Millett; Michael R Tonks; Xian-Ming Bai; S Bulent Biner

    2014-09-01T23:59:59.000Z

    The intergranular fracture behavior of UO2 was studied using molecular dynamics simulations with a bicrystal model. The anisotropic fracture behavior due to the different grain boundary characters was investigated with the View the MathML source symmetrical tilt S5 and the View the MathML source symmetrical tilt S3 ({1 1 1} twin) grain boundaries. Nine interatomic potentials, seven rigid-ion plus two core–shell ones, were utilized to elucidate possible potential dependence. Initiating from a notch, crack propagation along grain boundaries was observed for most potentials. The S3 boundary was found to be more prone to fracture than the S5 one, indicated by a lower energy release rate associated with the former. However, some potential dependence was identified on the existence of transient plastic deformation at crack tips, and the results were discussed regarding the relevant material properties including the excess energies of metastable phases and the critical energy release rate for intergranular fracture. In general, local plasticity at crack tips was observed in fracture simulations with potentials that predict low excess energies for metastable phases and high critical energy release rates for intergranular fracture.

  9. Graphite and Beryllium Reflector Critical Assemblies of UO2 (Benchmark Experiments 2 and 3)

    SciTech Connect (OSTI)

    Margaret A. Marshall; John D. Bess

    2012-11-01T23:59:59.000Z

    INTRODUCTION A series of experiments was carried out in 1962-65 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for use in space reactor research programs. A core containing 93.2 wt% enriched UO2 fuel rods was used in these experiments. The first part of the experimental series consisted of 252 tightly-packed fuel rods (1.27-cm triangular pitch) with graphite reflectors [1], the second part used 252 graphite-reflected fuel rods organized in a 1.506-cm triangular-pitch array [2], and the final part of the experimental series consisted of 253 beryllium-reflected fuel rods in a 1.506-cm-triangular-pitch configuration and in a 7-tube-cluster configuration [3]. Fission rate distribution and cadmium ratio measurements were taken for all three parts of the experimental series. Reactivity coefficient measurements were taken for various materials placed in the beryllium reflected core. All three experiments in the series have been evaluated for inclusion in the International Reactor Physics Experiment Evaluation Project (IRPhEP) [4] and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbooks, [5]. The evaluation of the first experiment in the series was discussed at the 2011 ANS Winter meeting [6]. The evaluations of the second and third experiments are discussed below. These experiments are of interest as benchmarks because they support the validation of compact reactor designs with similar characteristics to the design parameters for a space nuclear fission surface power systems [7].

  10. WIMS/PANTHER analysis of UO{sub 2}/MOX cores using embedded super-cells

    SciTech Connect (OSTI)

    Knight, M.; Bryce, P. [EDF Energy, Barnett Way, Barnwood, Gloucester (United Kingdom); Hall, S. [Advanced Modelling and Computation Group, Imperial College, London (United Kingdom)

    2012-07-01T23:59:59.000Z

    This paper describes a method of analysing PWR UO{sub 2}MOX cores with WIMS/PANTHER. Embedded super-cells, run within the reactor code, are used to correct the standard methodology of using 2-group smeared data from single assembly lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code, or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged. The essence of the approach is that the whole core is broken down into a set of 'embedded' super-cells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly mid-lines. Each supercell is solved twice, first with a detailed multi-group pin-by-pin solution, and then with the standard single assembly approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole core calculations. The restriction that all such calculations are modelled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel pre-calculation for the entire cycle once the loading pattern has been determined, in much the same way that single assembly lattice calculations can be pre-calculated once the range of fuel types is known. Comparisons against a whole core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refuelling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multi-group diffusion solution is capable of capturing the main interface effects. This therefore defines a practical approach for achieving results close to lattice code accuracy, but broadly at the cost of a standard reactor calculation. (authors)

  11. Leaching action of EJ-13 water on unirradiated UO{sub 2} surfaces under unsaturated conditions at 90{degree}C: Interim report

    SciTech Connect (OSTI)

    Wronkiewicz, D.J.; Bates, J.K.; Gerding, T.J.; Veleckis, E.; Tani, B.S.

    1991-07-01T23:59:59.000Z

    A set of experiments, based on the application of the Unsaturated Test method to the reaction of UO{sub 2} with EJ-13 water, has been conducted over a period of 182.5 weeks. One half of the experiments have been terminated, while one half are still ongoing. Solutions that have dripped from UO{sub 2} specimens have been analyzed for all experiments, while the reacted UO{sub 2} surfaces have been examined for only the terminated experiments. A pulse of uranium release from the UO{sub 2} solid, in conjunction with the formation of dehydrated schoepite on the surface of the UO{sub 2}, was observed during the 39- to 96-week period. Thereafter, the uranium release decreased and a second set of secondary phases was observed. The latter phases incorporate cations from the EJ-13 water and include boltwoodite, uranophane, sklodowskite, compreignacite, and schoepite. The experiments are being continued to monitor for additional changes in solution composition and secondary phase formation, and have now reached the 319-week period. 9 refs., 17 figs., 25 tabs.

  12. Dissolution Behaviour of UO{sub 2} in Anoxic Conditions: Comparison of Ca-Bentonite and Boom Clay

    SciTech Connect (OSTI)

    Mennecart, Thierry; Cachoir, Christelle; Lemmens, Karel [SCK-CEN, Boeretang 200, MOL, 2400 (Belgium)

    2007-07-01T23:59:59.000Z

    In order to determine in how far the clay properties influence the dissolution of spent fuel, experiments were carried out with depleted UO{sub 2} in the presence of either compacted dry Ca-bentonite with Boom Clay groundwater (KB-BCW) or compacted dry Boom Clay with Boom Clay groundwater (BC-BCW). The leach tests were performed at 25 deg. C in anoxic atmosphere for 2 years. The U concentrations in the clay water were followed during these 2 years, and the amount of U in the clay was determined after 2 years in order to determine the UO{sub 2} dissolution rate. The uranium concentration after 0.45 {mu}m filtration was 50 times higher in the Boom Clay with Boom Clay water (2.0 x 10{sup -7} mol.L{sup -1}) than in Ca-bentonite with Boom Clay water (6.5 x 10{sup -9} mol.L{sup -1}), probably due to colloid formation in the Boom Clay system. Most released uranium was found in the clay. The fraction of uranium, dissolved from the UO{sub 2} pellet and found on the clay represents about 42 % of total uranium release in the system BC-BCW and more than 76 % in the system KB-BCW. The higher uranium retention of Boom Clay goes together with a higher dissolution rate. Global dissolution rates were estimated at about 2.0 x 10{sup -2} {mu}g.cm{sup -2}.d{sup -1} for the BCBCW system and 3.4 x 10{sup -3} {mu}g.cm{sup -2}.d{sup -1} for the KB-BCW system. This is not much lower than for similar tests with spent fuel, reported in literature. (authors)

  13. Enhanced Generic Phase-field Model of Irradiation Materials: Fission Gas Bubble Growth Kinetics in Polycrystalline UO2

    SciTech Connect (OSTI)

    Li, Yulan; Hu, Shenyang Y.; Montgomery, Robert O.; Gao, Fei; Sun, Xin

    2012-05-30T23:59:59.000Z

    Experiments show that inter-granular and intra-granular gas bubbles have different growth kinetics which results in heterogeneous gas bubble microstructures in irradiated nuclear fuels. A science-based model predicting the heterogeneous microstructure evolution kinetics is desired, which enables one to study the effect of thermodynamic and kinetic properties of the system on gas bubble microstructure evolution kinetics and morphology, improve the understanding of the formation mechanisms of heterogeneous gas bubble microstructure, and provide the microstructure to macroscale approaches to study their impact on thermo-mechanical properties such as thermo-conductivity, gas release, volume swelling, and cracking. In our previous report 'Mesoscale Benchmark Demonstration, Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing', we developed a phase-field model to simulate the intra-granular gas bubble evolution in a single crystal during post-irradiation thermal annealing. In this work, we enhanced the model by incorporating thermodynamic and kinetic properties at grain boundaries, which can be obtained from atomistic simulations, to simulate fission gas bubble growth kinetics in polycrystalline UO2 fuels. The model takes into account of gas atom and vacancy diffusion, vacancy trapping and emission at defects, gas atom absorption and resolution at gas bubbles, internal pressure in gas bubbles, elastic interaction between defects and gas bubbles, and the difference of thermodynamic and kinetic properties in matrix and grain boundaries. We applied the model to simulate gas atom segregation at grain boundaries and the effect of interfacial energy and gas mobility on gas bubble morphology and growth kinetics in a bi-crystal UO2 during post-irradiation thermal annealing. The preliminary results demonstrate that the model can produce the equilibrium thermodynamic properties and the morphology of gas bubbles at grain boundaries for given grain boundary properties. More validation of the model capability in polycrystalline is underway.

  14. Vibrational Spectroscopy of Mass-Selected [UO2(ligand)n]2+ Complexes in the Gas Phase: Comparison with Theory

    SciTech Connect (OSTI)

    Gary S. Groenewold; Anita K. Gianotto

    2006-03-01T23:59:59.000Z

    The gas-phase infrared spectra of discrete uranyl ([UO2]2+) complexes ligated with acetone and/or acetonitrile were used to evaluate systematic trends of ligation on the position of the OdUdO stretch and to enable rigorous comparison with the results of computational studies. Ionic uranyl complexes isolated in a Fourier transform ion cyclotron resonance mass spectrometer were fragmented via infrared multiphoton dissociation using a free electron laser scanned over the mid-IR wavelengths. The asymmetric OdUdO stretching frequency was measured at 1017 cm-1 for [UO2(CH3COCH3)2]2+ and was systematically red shifted to 1000 and 988 cm-1 by the addition of a third and fourth acetone ligand, respectively, which was consistent with increased donation of electron density to the uranium center in complexes with higher coordination number. The values generated computationally using LDA, B3LYP, and ZORA-PW91 were in good agreement with experimental measurements. In contrast to the uranyl frequency shifts, the carbonyl frequencies of the acetone ligands were progressively blue shifted as the number of ligands increased from two to four and approached that of free acetone. This observation was consistent with the formation of weaker noncovalent bonds between uranium and the carbonyl oxygen as the extent of ligation increases. Similar trends were observed for [UO2(CH3CN)n]2+ complexes, although the uranyl asymmetric stretching frequencies were greater than those measured for acetone complexes having equivalent coordination, which is consistent with the fact that acetonitrile is a weaker nucleophile than is acetone. This conclusion was confirmed by the uranyl stretching frequencies measured for mixed acetone/acetonitrile complexes, which showed that substitution of one acetone for one acetonitrile produced a modest red shift of 3-6 cm-1.

  15. Vibrational Spectroscopy of Mass-Selected [UO?(ligand)n]²? Complexes in the Gas Phase: Comparison with Theory

    SciTech Connect (OSTI)

    Groenewold, G. S.; Gianotto, Anita K.; Cossel, Kevin C.; Van Stipdonk, Michael J.; Moore, David T.; Polfer, Nick; Oomens, Jos; De Jong, Wibe A.; Visscher, Lucas

    2006-03-18T23:59:59.000Z

    The gas-phase infrared spectra of discrete uranyl ([UO?]²?) complexes ligated with acetone and/or acetonitrile were used to evaluate systematic trends of ligation on the position of the O=U=O stretch, and to enable rigorous comparison with the results of computational studies. Ionic uranyl complexes isolated in a Fourier transform ion cyclotron resonance mass spectrometer were fragmented via infrared multiphoton dissociation using a free electron laser scanned over the mid-IR wavelengths. The asymmetric O=U=O stretching frequency was measured at 1017 cm?¹ for [UO?(CH?COCH?)?]²? and was systematically red shifted to 1000 and 988 cm?¹ by the addition of a third and fourth acetone ligand, respectively, which was consistent with increased donation of electron density to the uranium center in complexes with higher coordination number. The values generated computationally using LDA, B3LYP, and ZORA-PW91 were in good agreement with experimental measurements. In contrast to the uranyl frequency shifts, the carbonyl frequencies of the acetone ligands were progressively blue shifted as the number of ligands increased from 2 to 4, and approached that of free acetone. This observation was consistent with the formation of weaker noncovalent bonds between uranium and the carbonyl oxygen as the extent of ligation increases. Similar trends were observed for [UO?(CH?CN)n]²? complexes, although the magnitude of the red shift in the uranyl frequency upon addition of more acetonitrile ligands was smaller than for acetone, consistent with the more modest nucleophilic nature of acetonitrile. This conclusion was confirmed by the uranyl stretching frequencies measured for mixed acetone/acetonitrile complexes, which showed that substitution of one acetone for one acetonitrile produced a modest red shift of 3 to 6 cm?¹.

  16. Evaluation of UF{sub 6}-to-UO{sub 2} conversion capability at commercial nuclear fuel fabrication facilities.

    SciTech Connect (OSTI)

    Ranek, N. L.; Monette, F. A.

    2001-06-08T23:59:59.000Z

    This report examines the capabilities of existing commercial nuclear fuel fabrication facilities to convert depleted uranium hexafluoride (UF{sub 6}) to uranium oxide (UO{sub 2}). The U.S. Department of Energy (DOE) needs this information to determine whether using such capacity to convert DOE's inventory of depleted UF{sub 6} to a more stable form is a reasonable alternative that should be considered in the site-specific environmental impact statement for construction and operation of depleted UF{sub 6} conversion facilities. Publicly available information sources were consulted to ascertain the information summarized in this report. For domestic facilities, the information summarized includes currently operating capacity to convert depleted UF{sub 6} to UO{sub 2}; transportation distances from depleted UF{sub 6} storage locations near Oak Ridge, Tennessee, Portsmouth, Ohio, and Paducah, Kentucky, to the facilities; and regulatory requirements applicable to nuclear fuel fabrication and transportation of depleted UF{sub 6}. The report concludes that the total currently operating capability of U.S. commercial nuclear fuel fabricators to convert UF{sub 6} to UO{sub 2} is approximately 5,200 metric tons of UF{sub 6} per annum (tUF{sub 6}/a). This total includes 666 tUF{sub 6}/a scheduled for shutdown by the end of 2001. However, only about 300 tUF{sub 6}/a of this capacity could be confirmed as being possibly available to DOE. The report also provides some limited descriptions of the capabilities of foreign fuel fabrication plants to convert UF{sub 6} to uranium oxide forms.

  17. Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO{sub 2{+-}x}

    SciTech Connect (OSTI)

    Deo, Chaitanya; Adnersson, Davis; Battaile, Corbett; uberuaga, Blas

    2012-10-30T23:59:59.000Z

    The team will examine how the incorporation of actinide species important for mixed oxide (MOX) and other advanced fuel designs impacts thermodynamic quantities of the host UO{sub 2} nuclear fuel and how Pu, Np, Cm and Am influence oxygen mobility. In many cases, the experimental data is either insufficient or missing. For example, in the case of pure NpO2, there is essentially no experimental data on the hyperstoichiometric form it is not even known if hyperstoichiometry NpO{sub 2{+-}x} is stable. The team will employ atomistic modeling tools to calculate these quantities

  18. Uranium vacancy mobility at the sigma 5 symmetric tilt grain boundary in UO2

    SciTech Connect (OSTI)

    Uberuaga, Blas P. [Los Alamos National Laboratory

    2012-05-02T23:59:59.000Z

    An important consequence of the fissioning process occurring during burnup is the formation of fission products. These fission products alter the thermo-mechanical properties of the fuel. They also lead to macroscopic changes in the fuel structure, including the formation of bubbles that are connected to swelling of the fuel. Subsequent release of fission gases increase the pressure in the plenum and can cause changes in the properties of the fuel pin itself. It is thus imperative to understand how fission products, and fission gases in particular, behave within the fuel in order to predict the performance of the fuel under operating conditions. Fission gas redistribution within the fuel is governed by mass transport and the presence of sinks such as impurities, dislocations, and grain boundaries. Thus, to understand how the distribution of fission gases evolves in the fuel, we must understand the underlying transport mechanisms, tied to the concentrations and mobilities of defects within the material, and how these gases interact with microstructural features that might act as sinks. Both of these issues have been addressed in previous work under NEAMS. However, once a fission product has reached a sink, such as a grain boundary, its mobility may be different there than in the grain interior and predicting how, for example, bubbles nucleate within grain boundaries necessitates an understanding of how fission gases diffuse within boundaries. That is the goal of the present work. In this report, we describe atomic level simulations of uranium vacancy diffusion in the pressence of a {Sigma}5 symmetric tilt boundary in urania (UO{sub 2}). This boundary was chosen as it is the simplest of the boundaries we considered in previous work on segregation and serves as a starting point for understanding defect mobility at boundaries. We use a combination of molecular statics calculations and kinetic Monte Carlo (kMC) to determine how the mobility of uranium vacancies is altered at this particular grain boundary. Given that the diffusion of fission gases such as Xe are tied to the mobility of uranium vacancies, these results given insight into how fission gas mobility differs at grain boundaries compared to bulk urania.

  19. Production of Depleted UO2Kernels for the Advanced Gas-Cooled Reactor Program for Use in TRISO Coating Development

    SciTech Connect (OSTI)

    Collins, J.L.

    2004-12-02T23:59:59.000Z

    The main objective of the Depleted UO{sub 2} Kernels Production Task at Oak Ridge National Laboratory (ORNL) was to conduct two small-scale production campaigns to produce 2 kg of UO{sub 2} kernels with diameters of 500 {+-} 20 {micro}m and 3.5 kg of UO{sub 2} kernels with diameters of 350 {+-} 10 {micro}m for the U.S. Department of Energy Advanced Fuel Cycle Initiative Program. The final acceptance requirements for the UO{sub 2} kernels are provided in the first section of this report. The kernels were prepared for use by the ORNL Metals and Ceramics Division in a development study to perfect the triisotropic (TRISO) coating process. It was important that the kernels be strong and near theoretical density, with excellent sphericity, minimal surface roughness, and no cracking. This report gives a detailed description of the production efforts and results as well as an in-depth description of the internal gelation process and its chemistry. It describes the laboratory-scale gel-forming apparatus, optimum broth formulation and operating conditions, preparation of the acid-deficient uranyl nitrate stock solution, the system used to provide uniform broth droplet formation and control, and the process of calcining and sintering UO{sub 3} {center_dot} 2H{sub 2}O microspheres to form dense UO{sub 2} kernels. The report also describes improvements and best past practices for uranium kernel formation via the internal gelation process, which utilizes hexamethylenetetramine and urea. Improvements were made in broth formulation and broth droplet formation and control that made it possible in many of the runs in the campaign to produce the desired 350 {+-} 10-{micro}m-diameter kernels, and to obtain very high yields.

  20. D10 experiment: coolability of UO/sub 2/ debris in sodium with downward heat removal. [LMFBR

    SciTech Connect (OSTI)

    Mitchell, G.W.; Ottinger, C.A.; Meister, H.

    1984-12-01T23:59:59.000Z

    The LMFBR Debris Coolability Program at Sandia National Laboratories investigates the coolability of particle beds which may form following a severe accident involving core disassembly in a nuclear reactor. The D series experiments utilize fission heating of fully enriched UO/sub 2/ particles submerged in sodium to realistically simulate decay heating. The D10 experiment is the first in the series to study the effects of bottom cooling of the debris that could be provided in an actual accident condition by structural materials onto which the debris might settle. Additionally, the D10 experiment was designed to achieve maximum temperatures in the debris approaching the melting point of UO/sub 2/. The experiment was successfully operated for over 50 hours and investigated downward heat removal in a packed bed at specific powers of 0.16 to 0.58 W/g. Dryout in the debris was achieved at powers from 0.42 to 0.58 W/g. Channels were induced in the bed and channeled bed dryout was achieved at powers of 1.06 to 1.77 W/g. Maximum temperatures in excess of 2500/sup 0/C were attained.

  1. Final Report: Manganese Redox Mediation of UO2 Stability and Uranium Fate in the Subsurface: Molecular and Meter Scale Dynamics

    SciTech Connect (OSTI)

    Tebo, Bradley M. [OSHU; Tebo, Bradley M.

    2014-09-02T23:59:59.000Z

    One strategy to remediate U contamination in the subsurface is the immobilization of U via injection of an electron donor, e.g., acetate, which leads to stimulation of the bioreduction of U(VI), the more mobile form of U, to U(IV), the less mobile form. This process is inevitably accompanied by the sequential reductive dissolution of Mn and Fe oxides and often continuing into sulfate-reducing conditions. When these reducing zones, which accumulate U(IV), experience oxidizing conditions, reduced Fe and Mn can be reoxidized forming Fe and Mn oxides that, along with O2, can impact the stability of U(IV). The focus of our project has been to investigate (i) the effects of Mn(II) on the dissolution of UO2 under both reducing and oxidizing conditions, (ii) the oxidative dissolution of UO2 by soluble Mn(III), (iii) the fate of U once it is oxidized by MnO2 in both laboratory and field settings, and (iv) the effects of groundwater constituents on the coupled Mn(II)/U(IV) oxidation process. Additionally, studies of the interaction of Se, found at the DOE site at Rifle, CO, and Mn cycling were initiated to understand if observed seasonal fluctuations of Se and Mn are directly linked and whether any such linkages can affect the stability of U(IV).

  2. Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation

    SciTech Connect (OSTI)

    Janne Pakrinen; Marat Khafizov; Lingfeng He; Chris Wetland; Jian Gan; Andrew T. Nelson; David H Hurley; Anter El-Azab; Todd R Allen

    2014-11-01T23:59:59.000Z

    The microstructural changes and associated effects on thermal conductivity were examined in UO2 after irradiation using 3.9 MeV He2+ ions. Lattice expansion of UO2 was observed in x-ray diffraction after ion irradiation up to 5×1016 He2+/cm2 at low-temperature (< 200 °C). Transmission electron microscopy (TEM) showed homogenous irradiation damage across an 8 µm thick plateau region, which consisted of small dislocation loops accompanied by dislocation segments. Dome-shaped blisters were observed at the peak damage region (depth around 8.5 µm) in the sample subjected to 5×1016 He2+/cm2, the highest fluence reached, while similar features were not detected at 9×1015 He2+/cm2. Laser-based thermo-reflectance measurements showed that the thermal conductivity for the irradiated layer decreased about 55 % for the high fluence sample and 35% for the low fluence sample as compared to an un-irradiated reference sample. Detailed analysis for the thermal conductivity indicated that the conductivity reduction was caused by the irradiation induced point defects.

  3. Coolability of stratified UO/sub 2/ debris in sodium with downward heat removal: The D13 experiment

    SciTech Connect (OSTI)

    Ottinger, C.A.; Mitchell, G.W.; Reed, A.W.; Meister, H.

    1987-03-01T23:59:59.000Z

    The LMFBR Debris Coolability Program at Sandia National Laboratories investigates the coolability of particle beds that may form following a severe accident involving core disassembly in a nuclear reactor. The D series experiments utilize fission heating of fully enriched UO/sub 2/ particles submerged in sodium to realistically simulate decay heating. The D13 experiment is the first in the series to study the effects of bottom cooling of stratified debris, which could be provided in an actual accident condition by structural materials onto which the debris might settle. Additionally, the D13 experiment was designed to achieve maximum temperatures in the debris approaching the melting point of UO/sub 2/. The experiment was operated for over 40 hours and investigated downward heat removal at specific powers of 0.22 to 2.58 W/g. Channeled dryout in the debris was achieved at powers from 0.94 to 2.58 W/g. Maximum temperatures approaching 2700/sup 0/C were attained. Bottom heat removal was up to 750 kW/m/sup 2/ as compared to 450 kW/m/sup 2/ in the D10 experiment.

  4. UO Department of Chemistry -Faculty Research Interests Berglund, Andy -The primary goals of the Berglund lab are to understand the molecular basis of the human disease myotonic

    E-Print Network [OSTI]

    Cina, Jeff

    measurement, and device fabrication to design, build and study new materials and structures that have applications in solar energy harvesting and electrochemical energy storage. Chartoff, Richard - The UO Polymer approach to the synthesis of extended solids that permits them to prepare families of new nanostructured

  5. Synthesis and structure of Cs[UO{sub 2}(SeO{sub 4})(OH)] . nH{sub 2}O (n = 1.5 or 1)

    SciTech Connect (OSTI)

    Serezhkina, L. B., E-mail: lserezh@ssu.samara.ru [Samara State University (Russian Federation); Peresypkina, E. V.; Virovets, A. V. [Russian Academy of Sciences, Institute of Inorganic Chemistry, Siberian Branch (Russian Federation); Pushkin, D. V.; Verevkin, A. G. [Samara State University (Russian Federation)

    2010-05-15T23:59:59.000Z

    The synthesis and single-crystal X-ray diffraction study of Cs[UO{sub 2}(SeO{sub 4})(OH)] . 1.5H{sub 2}O (I) and Cs[UO{sub 2}(SeO{sub 4})(OH)] . H{sub 2}O (II) are performed. Compound I crystallizes in the monoclinic crystal system, a = 7.2142(2) A, b = 14.4942(4) A, c = 8.9270(3) A, {beta} = 112.706(1){sup o}, space group P2{sub 1}/m, Z = 4, and R = 0.0222. Compound II is monoclinic, a = 8.4549(2) A, b = 11.5358(3) A, c = 9.5565(2) A, {beta} = 113.273(1){sup o}, space group P2{sub 1}/c, Z = 4, and R = 0.0219. The main structural units of crystals I and II are [UO{sub 2}(SeO{sub 4})(OH)]{sup -} layers which belong to the AT{sup 3}M{sup 2} crystal chemical group of uranyl complexes (A = UO{sub 2}{sup 2+}, T{sup 3} = SeO{sub 4}{sup 2-}, and M{sup 2} = OH{sup -}). In structure I, johannite-like layers are found. Structure II is a topological isomer of I. The two structures differ in the number of U(VI) atoms bound to the central atom by all bridging ligands.

  6. Possible Bose-condensated Behavior in a Quantum Phase Originating in a Collective Excitation in the Chemically and Optically Doped Mott-Hubbard System UO2+x

    SciTech Connect (OSTI)

    Conradson, Steven D.; Durakiewicz, Tomasz; Espinosa-Faller, Francisco J.; An, Yong Q.; Andersson , David; Bishop, Alan R.; Boland, Kevin S.; Bradley, Joseph A.; Byler, Darrin D.; Clark, David L.; Conradson, Dylan R.; Conradson, Leilani L.; Costello, Alison E.; Hess, Nancy J.; Lander, Gerard H.; Llobet, Anna; Martucci, Mary B.; de Leon, Jose M.; Nordlund, Dennis; Lezama-Pacheco, Juan S.; Proffen, Thomas E.; Rodriguez, George; Schwarz, Daniel E.; Seidler, Gerald T.; Taylor, Antoinette; Trugman, Stuart A.; Tyson, Trevor A.; Valdez, James A.

    2013-09-23T23:59:59.000Z

    The pinned charge defects in U4O9, and U3O7 that are the single phase fluoritestructured derivatives of UO2 have been characterized by U L3 EXAFS at 30, 100, and 200 K, xray and neutron pair distribution function analysis, O K edge XAS and non-resonant inelastic xray scattering, and Raman spectroscopy, while mobile charge defects were investigated by femtosecond time-resolved pump-probe laser spectroscopy on single crystal UO2 between 7 and 300 K. The results from all of these measurements show highly complex and anomalous behaviors, which we attribute to a charge-lattice instability in UO2 that most likely originates in the intersection of the ground U(IV) and a proximate uranyl-like excited state in a conic section, causing a breakdown of the Born-Oppenheimer approximation. Furthermore, the photoinduced quasiparticles undergo a gap-opening condensation between 50 and 60 K. Doped UO2 may therefore exhibit novel correlated electron physics that extends beyond that of the cuprate-manganite-pnictide family of compounds.

  7. Modeling the Distribution of Acidity within Nuclear Fuel (UO{sub 2}) Corrosion Product Deposits and Porous Sites

    SciTech Connect (OSTI)

    Cheong, W.J.; Keech, P.G.; Wren, J.C.; Shoesmith, D.W.; Qin, Z. [The University of Western Ontario, London, Ontario, N6A 5B7 (Canada)

    2007-07-01T23:59:59.000Z

    A model for acidity within pores within corrosion products on anodically-dissolving UO{sub 2} was developed using Comsol Multiphysics 3.2 to complement ongoing electrochemical measurements. It was determined that a depression of pH within pores can be maintained if: electrochemically measured dissolution currents used in the calculations are attenuated to reflect very localized pores; corrosion potentials exceed -250 mV (vs. SCE); and pore depths are >1 {mu}m for 300 mV or >100 {mu}m for -50 mV (vs. SCE). Mixed diffusional-chemical equilibria control is suggested through deviations in the shapes between pH-potential and pH-pore depth plots. (authors)

  8. Possible effects of UO/sub 2/ oxidation on light water reactor spent fuel performance in long-term geologic disposal

    SciTech Connect (OSTI)

    Almassy, M.Y.; Woodley, R.E.

    1982-08-01T23:59:59.000Z

    Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO/sub 2/) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO/sub 2/ oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented.

  9. Topologically identical, but geometrically isomeric layers in hydrous ?-, ?-Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})]·H{sub 2}O and anhydrous Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})

    SciTech Connect (OSTI)

    Yu, Na; Klepov, Vladislav V. [Forschungszentrum Jülich GmbH, Institute for Energy and Climate Research (IEK-6), 52428 Jülich (Germany); Villa, Eric M. [Department of Chemistry, Creighton University, 2500 California Plaza, Omaha NE 68178 (United States); Bosbach, Dirk [Forschungszentrum Jülich GmbH, Institute for Energy and Climate Research (IEK-6), 52428 Jülich (Germany); Suleimanov, Evgeny V. [Department of Chemistry, Lobachevsky State University of Nizhny Novgorod, 603950 Nizhny Novgorod (Russian Federation); Depmeier, Wulf [Institut für Geowissenschaften, Universität zu Kiel, 24118 Kiel (Germany); Albrecht-Schmitt, Thomas E., E-mail: albrecht-schmitt@chem.fsu.edu [Department of Chemistry and Biochemistry, Florida State University, 102 Varsity Way, Tallahassee, FL 32306-4390 (United States); Alekseev, Evgeny V., E-mail: e.alekseev@fz-juelich.de [Forschungszentrum Jülich GmbH, Institute for Energy and Climate Research (IEK-6), 52428 Jülich (Germany); Institut für Kristallographie, RWTH Aachen University, 52066 Aachen (Germany)

    2014-07-01T23:59:59.000Z

    The hydrothermal reaction of uranyl nitrate with rubidium nitrate and arsenic (III) oxide results in the formation of polymorphic ?- and ?-Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})]·H{sub 2}O (?-, ?-RbUAs) and the anhydrous phase Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})] (RbUAs). These phases were structurally, chemically and spectroscopically characterized. The structures of all three compounds are based upon topologically identical, but geometrically isomeric layers. The layers are linked with each other by means of the Rb cations and hydrogen bonding. Dehydration experiments demonstrate that water deintercalation from hydrous ?- and ?-RbUAs yields anhydrous RbUAs via topotactic reactions. - Graphical abstract: Three different layer geometries observed in the structures of Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})] and ?- and ?- Rb[UO{sub 2}(AsO{sub 3}OH)(AsO{sub 2}(OH){sub 2})]·H{sub 2}O. Two different coordination environments of uranium polyhedra (types I and II) are shown schematically on the top of the figure. - Highlights: • Three new uranyl arsenates were synthesized from the hydrothermal reactions. • The phases consist of the topologically identical but geometrically different layers. • Topotactic transitions were observed in the processes of mono-hyrates dehydration.

  10. {gamma}-Radiolysis of NaCl Brine in the Presence of UO{sub 2}(s): Effects of Hydrogen and Bromide

    SciTech Connect (OSTI)

    Metz, Volker; Bohnert, Elke; Kelm, Manfred; Schild, Dieter; Kienzler, Bernhard [Institute for Radioactive Waste Disposal (FZK-INE), Forschungszentrum Karlsruhe / Research Center Karlsruhe, Helmholtz-Platz, Eggenstein-Leopoldshafen, D-76344 (Germany); Reinhardt, Juergen; Buchmeiser, Michael R. [Leibniz-Institut fuer Oberflaechenmodifizierung, IOM, Permoserstr. 15, Leipzig, D-04318 (Germany)

    2007-07-01T23:59:59.000Z

    A concentrated NaCl solution was {gamma}-irradiated in autoclaves under a pressure of 25 MPa. A set of experiments were conducted in 6 mol (kg H{sub 2}O){sup -1} NaCl solution in the presence of UO{sub 2}(s) pellets; in a second set of experiments, {gamma}-radiolysis of the NaCl brine was studied without UO{sub 2}(s). Hydrogen, oxygen and chlorate were formed as long-lived radiolysis products. Due to the high external pressure, all radiolysis products remained dissolved. H{sub 2} and O{sub 2} reached steady state concentrations in the range of 5.10{sup -3} to 6.10{sup -2} mol (kg H{sub 2}O){sup -1} corresponding to a partial gas pressure of {approx}2 to {approx}20 MPa. Radiolytic formation of hydrogen and oxygen increased with the concentration of bromide added to solution. Both, in the presence of bromide, resulting in a relatively high radiolytic yield, and in the absence of bromide surfaces of the UO{sub 2}(s) samples were oxidized, and concentration of dissolved uranium reached the solubility limit of the schoepite / NaUO{sub 2}O(OH)(cr) transition. At the end of the experiments, the pellets were covered by a surface layer of a secondary solid phase having a composition close to Na{sub 2}U{sub 2}O{sub 7}. The experimental results demonstrate that bromide counteracts an H{sub 2} inhibition effect on radiolysis gas production, even at a concentration ratio of [H{sub 2}] / [Br{sup -}] > 100. The present observations are related to the competitive reactions of OH radicals with H{sub 2}, Br{sup -} and Cl{sup -}. A similar competition of hydrogen and bromide, controlling the yield of {gamma}-radiolysis products, is expected for solutions of lower Cl{sup -} concentration. (authors)

  11. Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2 +/- x: Implications for nuclear fuel performance modeling

    SciTech Connect (OSTI)

    Giovanni Pastore; Michael R. Tonks; Derek R. Gaston; Richard L. Williamson; David Andrs; Richard Martineau

    2014-03-01T23:59:59.000Z

    Based on density functional theory (DFT) and empirical potential calculations, the diffusivity of fission gas atoms (Xe) in UO2 nuclear fuel has been calculated for a range of non-stoichiometry (i.e. UO2x), under both out-of-pile (no irradiation) and in-pile (irradiation) conditions. This was achieved by first deriving expressions for the activation energy that account for the type of trap site that the fission gas atoms occupy, which includes the corresponding type of mobile cluster, the charge state of these defects and the chemistry acting as boundary condition. In the next step DFT calculations were used to estimate migration barriers and internal energy contributions to the thermodynamic properties and calculations based on empirical potentials were used to estimate defect formation and migration entropies (i.e. pre-exponentials). The diffusivities calculated for out-of-pile conditions as function of the UO2x nonstoichiometrywere used to validate the accuracy of the diffusion models and the DFT calculations against available experimental data. The Xe diffusivity is predicted to depend strongly on the UO2x non-stoichiometry due to a combination of changes in the preferred Xe trap site and in the concentration of uranium vacancies enabling Xe diffusion, which is consistent with experiments. After establishing the validity of the modeling approach, it was used for studying Xe diffusion under in-pile conditions, for which experimental data is very scarce. The radiation-enhanced Xe diffusivity is compared to existing empirical models. Finally, the predicted fission gas diffusion rates were implemented in the BISON fuel performance code and fission gas release from a Risø fuel rod irradiation experiment was simulated. 2014 Elsevier B.V. All rights

  12. Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-MOX, R2-UO2 and MORGANE/R configurations.

    SciTech Connect (OSTI)

    Zhong, Z.; Klann, R. T.; Nuclear Engineering Division

    2007-08-03T23:59:59.000Z

    An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R2-UO2 and MORGANE/R core configuration were completed. The calculation model was generated using the lattice physics code DRAGON. In addition, an initial comparison of calculated values to experimental measurements was performed based on preliminary results for the R1-MOX configuration.

  13. Oxidative corrosion of spent UO{sub 2} fuel in vapor and dripping groundwater at 90{degree}C.

    SciTech Connect (OSTI)

    Finch, R. J.

    1999-04-29T23:59:59.000Z

    Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Oxidative dissolution in vapor and dripping groundwater at 90 C occurs via general corrosion at fuel-fragment surfaces. Dissolution along fuel-grain boundaries is also evident in samples contacted by the largest volumes of groundwater, and corroded grain boundaries extend at least 20 or 30 grains deep (> 200 {micro}m), possibly throughout millimeter-sized fragments. Apparent dissolution of fuel along defects that intersect grain boundaries has created dissolution pits that are 50 to 200 nm in diameter. Dissolution pits penetrate 1-2 {micro}m into each grain, producing a ''worm-like'' texture along fuel-grain-boundaries. Sub-micrometer-sized fuel shards are common between fuel grains and may contribute to the reactive surface area of fuel exposed to groundwater. Outer surfaces of reacted fuel fragments develop a fine-grained layer of corrosion products adjacent to the fuel (5-15 {micro}m thick). A more coarsely crystalline layer of corrosion products commonly covers the fine-grained layer, the thickness of which varies considerably among samples (from less than 5 {micro}m to greater than 40 {micro}m). The thickest and most porous corrosion layers develop on fuel fragments exposed to the largest volumes of groundwater. Corrosion-layer compositions depend strongly on water flux, with uranyl oxy-hydroxides predominating in vapor experiments, and alkali and alkaline earth uranyl silicates predominating in high drip-rate experiments. Low drip-rate experiments exhibit a complex assemblage of corrosion products, including phases identified in vapor and high drip-rate experiments.

  14. Dispersion of UO{sub 2}F{sub 2} aerosol and HF vapor in the operating floor during winter ventilation at the Paducah Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    Kim, S.H.; Chen, N.C.J.; Taleyarkhan, R.P.; Keith, K.D.; Schmidt, R.W. [Oak Ridge National Lab., TN (United States); Carter, J.C. [J.C. Carter Associates, Inc., Knoxville, TN (United States)

    1996-12-30T23:59:59.000Z

    The gaseous diffusion process is currently employed at two plants in the US: the Paducah Gaseous Diffusion Plant and the Portsmouth Gaseous Diffusion Plant. As part of a facility-wide safety evaluation, a postulated design basis accident involving large line-rupture induced releases of uranium hexafluoride (UF{sub 6}) into the process building of a gaseous diffusion plant (GDP) is evaluated. When UF{sub 6} is released into the atmosphere, it undergoes an exothermic chemical reaction with moisture (H{sub 2}O) in the air to form vaporized hydrogen fluoride (HF) and aerosolized uranyl fluoride (UO{sub 2}F{sub 2}). These reactants disperse in the process building and transport through the building ventilation system. The ventilation system draws outside air into the process building, distributes it evenly throughout the building, and discharges it to the atmosphere at an elevated temperature. Since air is recirculated from the cell floor area to the operating floor, issues concerning in-building worker safety and evacuation need to be addressed. Therefore, the objective of this study is to evaluate the transport of HF vapor and UO{sub 2}F{sub 2} aerosols throughout the operating floor area following B-line break accident in the cell floor area.

  15. Criticality Safety Study of UF6and UO2F2in 8-in. Inner Diameter Piping

    SciTech Connect (OSTI)

    Elam, K.R.

    2003-10-07T23:59:59.000Z

    The purpose of this report is to provide an evaluation of the criticality safety aspects of using up to 8-in.-inner-diameter (ID) piping as part of a system to monitor the {sup 235}U enrichment in uranium hexafluoride (UF{sub 6}) gas both before and after an enrichment down-blending operation. The evaluated operation does not include the blending stage but includes only the monitors and the piping directly associated with the monitors, which are in a separate room from the blending operation. There are active controls in place to limit the enrichment of the blended UF{sub 6} to a maximum of 5 weight percent (wt%) {sup 235}U. Under normal operating conditions of temperature and pressure, the UF{sub 6} will stay in the gas phase and criticality will not be credible. The two accidents of concern are solidification of the UF{sub 6} along with some hydrofluoric acid (HF) and water or moisture ingress, which would cause the UF{sub 6} gas to react and form a hydrated uranyl fluoride (UO{sub 2}F{sub 2}) solid or solution. Of these two types of accidents, the addition of water and formation of UO{sub 2}F{sub 2} is the most reactive scenario and thus limits related to UO{sub 2}F{sub 2} will bound the limits related to UF{sub 6}. Two types of systems are included in the monitoring process. The first measures the enrichment of the approximately 90 wt% enriched UF{sub 6} before it is blended. This system uses a maximum 4-in.-(10.16-cm-) ID pipe, which is smaller than the 13.7-cm-cylinder-diameter subcritical limit for UO{sub 2}F{sub 2} solution of any enrichment as given in Table 1 of American National Standard ANSI/ANS-8.1.1 Therefore, this system poses no criticality concerns for either accident scenario. The second type of system includes two enrichment monitors for lower-enriched UF{sub 6}. One monitors the approximately 1.5 wt% enriched UF{sub 6} entering the blending process, and the second monitors the approximately 5 wt% enriched UF{sub 6} coming out of the blending process. Both use a maximum 8-in.-(20.32-cm-) ID piping, where the length of the larger ID piping is approximately 9.5 m. This diameter of piping is below the 26.6-cm-cylinder-diameter subcritical limit for 5 wt% enriched UO{sub 2}F{sub 2} solutions as given in Table 6 of ANSI/ANS-8.1. Therefore, for up to 5 wt% enriched UF{sub 6}, this piping does not present a criticality concern for either accident scenario. Calculations were performed to determine the enrichment level at which criticality could become a concern in these 8-in.-ID piping sections. Both unreflected and fully water-reflected conditions were considered.

  16. 2. HIGH-LOv~ JUNCTION FORY_,\\'UO AN EXPERIMENTAL STUDY OF AL-ALLOYED:'p+ JUNCT;[ONS FOR SSF SOLAR CELT.S As temperature rises en..!."

    E-Print Network [OSTI]

    del Alamo, Jesús A.

    . Luque formed. The deposited Al diss Instituto de Energia Solar {E.T,S,I.T,} phase composition given2. HIGH-LOv~ JUNCTION FORY_,\\'UO AN EXPERIMENTAL STUDY OF AL-ALLOYED:§'p+ JUNCT;[ONS FOR SSF SOLAR+pp+ bifacial SSF solar cells are used to experimentally analyse the interphase in a similar way a 5i layer

  17. High temperature redox reactions with uranium: Synthesis and characterization of Cs(UO{sub 2})Cl(SeO{sub 3}), Rb{sub 2}(UO{sub 2}){sub 3}O{sub 2}(SeO{sub 3}){sub 2}, and RbNa{sub 5}U{sub 2}(SO{sub 4}){sub 7}

    SciTech Connect (OSTI)

    Babo, Jean-Marie [Department of Chemistry and Biochemistry, Florida State University, 95 Chieftan Way, Tallahassee, FL 32306-4390 (United States); Department of Civil and Environmental Engineering and Earth Sciences and Department of Chemistry and Biochemistry, University of Notre Dame, Notre Dame, IN 46556 (United States); Albrecht-Schmitt, Thomas E., E-mail: talbrechtschmitt@gmail.com [Department of Chemistry and Biochemistry, Florida State University, 95 Chieftan Way, Tallahassee, FL 32306-4390 (United States)

    2013-10-15T23:59:59.000Z

    Cs(UO{sub 2})Cl(SeO{sub 3}) (1), Rb{sub 2}(UO{sub 2}){sub 3}O{sub 2}(SeO{sub 3}){sub 3} (2), and RbNa{sub 5}U{sub 2}(SO{sub 4}){sub 7} (3) single crystals were synthesized using CsCl, RbCl, and a CuCl/NaCl eutectic mixture as fluxes, respectively. Their lattice parameters and space groups are as follows: P2{sub 1}/n (a=6.548(1) Å, b=11.052(2) Å, c=10.666(2) Å and ?=93.897(3)°), P1{sup ¯} (a=7.051(2) Å, b=7.198(2) Å, c=8.314(2) Å, ?=107.897(3)°, ?=102.687(3)° and ?=100.564(3)°) and C2/c (a=17.862(4) Å, b=6.931(1) Å, c=20.133(4) Å and ?=109.737(6)°. The small anionic building units found in these compounds are SeO{sub 3}{sup 2?} and SO{sub 4}{sup 2?} tetrahedra, oxide, and chloride. The crystal structure of the first compound is composed of [(UO{sub 2}){sub 2}Cl{sub 2}(SeO{sub 3}){sub 2}]{sup 2?} chains separated by Cs{sup +} cations. The structure of (2) is constructed from [(UO{sub 2}){sub 3}O{sub 11}]{sup 16?} chains further connected through selenite units into layers stacked perpendicularly to the [0 1 0] direction, with Rb{sup +} cations intercalating between them. The structure of compound (3) is made of uranyl sulfate layers formed by edge and vertex connections between dimeric [U{sub 2}O{sub 16}] and [SO{sub 4}] polyhedra. These layers contain unusual sulfate–metal connectivity as well as large voids. - Graphical abstract: A new family of uranyl selenites and sulfates has been prepared by high-temperature redox reactions. This compounds display new bonding motifs. Display Omitted - Highlights: • Low-dimensional Uranyl Oxoanion compounds. • Conversion of U(IV) to U(VI) at high temperatures. • Dimensional reduction by both halides and stereochemically active lone-pairs.

  18. LWR fuel assembly designs for the transmutation of LWR Spent Fuel TRU with FCM and UO{sub 2}-ThO{sub 2} Fuels

    SciTech Connect (OSTI)

    Bae, G.; Hong, S. G. [Department of Nuclear Engineering, KyungHee University, 1732 Deokyoungdaero, Giheung-gu, Yongin, Gyeonggi-do, 446-701 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    In this paper, transmutation of transuranic (TRU) nuclides from LWR spent fuels is studied by using LWR fuel assemblies which consist of UO{sub 2}-ThO{sub 2} fuel pins and FCM (Fully Ceramic Microencapsulated) fuel pins. TRU from LWR spent fuel is loaded in the kernels of the TRISO particle fuels of FCM fuel pins. In the FCM fuel pins, the TRISO particle fuels are distributed in SiC matrix having high thermal conductivity. The loading patterns of fuel pins and the fuel compositions are searched to have high transmutation rate and feasible neutronic parameters including pin power peaking, temperature reactivity coefficients, and cycle length. All studies are done only in fuel assembly calculation level. The results show that our fuel assembly designs have good transmutation performances without multi-recycling and without degradation of the safety-related neutronic parameters. (authors)

  19. Comet whole-core solution to a stylized 3-dimensional pressurized water reactor benchmark problem with UO{sub 2}and MOX fuel

    SciTech Connect (OSTI)

    Zhang, D.; Rahnema, F. [Georgia Inst. of Technology, 770 State Street, Atlanta, GA 30332-0745 (United States)

    2012-07-01T23:59:59.000Z

    A stylized pressurized water reactor (PWR) benchmark problem with UO{sub 2} and MOX fuel was used to test the accuracy and efficiency of the coarse mesh radiation transport (COMET) code. The benchmark problem contains 125 fuel assemblies and 44,000 fuel pins. The COMET code was used to compute the core eigenvalue and assembly and pin power distributions for three core configurations. In these calculations, a set of tensor products of orthogonal polynomials were used to expand the neutron angular phase space distribution on the interfaces between coarse meshes. The COMET calculations were compared with the Monte Carlo code MCNP reference solutions using a recently published an 8-group material cross section library. The comparison showed both the core eigenvalues and assembly and pin power distributions predicated by COMET agree very well with the MCNP reference solution if the orders of the angular flux expansion in the two spatial variables and the polar and azimuth angles on the mesh boundaries are 4, 4, 2 and 2. The mean and maximum differences in the pin fission density distribution ranged from 0.28%-0.44% and 3.0%-5.5%, all within 3-sigma uncertainty of the MCNP solution. These comparisons indicate that COMET can achieve accuracy comparable to Monte Carlo. It was also found that COMET's computational speed is 450 times faster than MCNP. (authors)

  20. Mesoscale Benchmark Demonstration Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing

    SciTech Connect (OSTI)

    Li, Yulan; Hu, Shenyang Y.; Montgomery, Robert; Gao, Fei; Sun, Xin; Tonks, Michael; Biner, Bullent; Millet, Paul; Tikare, Veena; Radhakrishnan, Balasubramaniam; Andersson , David

    2012-04-11T23:59:59.000Z

    A study was conducted to evaluate the capabilities of different numerical methods used to represent microstructure behavior at the mesoscale for irradiated material using an idealized benchmark problem. The purpose of the mesoscale benchmark problem was to provide a common basis to assess several mesoscale methods with the objective of identifying the strengths and areas of improvement in the predictive modeling of microstructure evolution. In this work, mesoscale models (phase-field, Potts, and kinetic Monte Carlo) developed by PNNL, INL, SNL, and ORNL were used to calculate the evolution kinetics of intra-granular fission gas bubbles in UO2 fuel under post-irradiation thermal annealing conditions. The benchmark problem was constructed to include important microstructural evolution mechanisms on the kinetics of intra-granular fission gas bubble behavior such as the atomic diffusion of Xe atoms, U vacancies, and O vacancies, the effect of vacancy capture and emission from defects, and the elastic interaction of non-equilibrium gas bubbles. An idealized set of assumptions was imposed on the benchmark problem to simplify the mechanisms considered. The capability and numerical efficiency of different models are compared against selected experimental and simulation results. These comparisons find that the phase-field methods, by the nature of the free energy formulation, are able to represent a larger subset of the mechanisms influencing the intra-granular bubble growth and coarsening mechanisms in the idealized benchmark problem as compared to the Potts and kinetic Monte Carlo methods. It is recognized that the mesoscale benchmark problem as formulated does not specifically highlight the strengths of the discrete particle modeling used in the Potts and kinetic Monte Carlo methods. Future efforts are recommended to construct increasingly more complex mesoscale benchmark problems to further verify and validate the predictive capabilities of the mesoscale modeling methods used in this study.

  1. Synthesis and X-ray structural investigation of K{sub 8}[(UO{sub 2}){sub 2}(C{sub 2}O{sub 4}){sub 2}(SeO{sub 4}){sub 4}] . 2H{sub 2}O

    SciTech Connect (OSTI)

    Serezhkina, L. B., E-mail: lserezh@ssu.samara.ru [Samara State University (Russian Federation); Peresypkina, E. V.; Virovets, A. V. [Russian Academy of Sciences, Nikolaev Institute of Inorganic Chemistry, Siberian Branch (Russian Federation); Verevkin, A. G.; Pushkin, D. V. [Samara State University (Russian Federation)

    2009-01-15T23:59:59.000Z

    Single crystals of the compound K{sub 8}[(UO{sub 2}){sub 2}(C{sub 2}O{sub 4}){sub 2}(SeO{sub 4})4] . 2H{sub 2}O (I) are synthesized, and their structure is investigated using X-ray diffraction. Compound I crystallizes in the monoclinic system with the unit cell parameters a = 14.9290(4) A, b = 7.2800(2) A, c = 15.3165(4) A, {beta} = 109.188(1){sup o}, V = 1572.17(7) A{sup 3}, space group P2{sub 1}/n, Z = 2, and R = 0.0297. The uranium-containing structural units of crystals I are dimers of the composition [(UO {sub 2}){sub 2}(C{sub 2}O{sub 4}){sub 2}(SeO{sub 4}){sub 4}]{sup 8-}, which belong to the crystal-chemical group AB{sup 01}B{sup 2}M{sup 1} (A = UO{sub 2}{sup 2+}, B{sup 01} = C{sub 2}O{sub 4}{sup 2-}, B{sup 2} = SeO{sub 4}{sup 2-}, M{sup 1} = SeO{sub 4}{sup 2-}) of the uranyl complexes. The [(UO{sub 2}){sub 2}(C{sub 2}O{sub 4}){sub 2}(SeO{sub 4}){sub 4}]{sup 8-} dimers are joined into a three-dimensional framework through electrostatic interactions with the outer-sphere potassium cations.

  2. ladedqsleasatl uo!lelSluam!radx3

    E-Print Network [OSTI]

    Standiford, Richard B.

    , timber management regime Estimates of timber net value change due to wildfire are sensitive: at the time oflhis study were with the Station's unit studying fire management planning and economics, Riverside.She has been with the Station since 1976. DARlA A. CAIN, research forester, earned a bachelor

  3. Pipe diffusion at dislocations in UO2

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for RenewableSpeedingBiomassPPPOPetroleum ReservesThrust AreasDepartment ofFUEL.P8.01

  4. PUREX/UO{sub 3} facilities deactivation lessons learned: History

    SciTech Connect (OSTI)

    Gerber, M.S.

    1997-11-25T23:59:59.000Z

    In May 1997, a historic deactivation project at the PUREX (Plutonium URanium EXtraction) facility at the Hanford Site in south-central Washington State concluded its activities (Figure ES-1). The project work was finished at $78 million under its original budget of $222.5 million, and 16 months ahead of schedule. Closely watched throughout the US Department of Energy (DOE) complex and by the US Department of Defense for the value of its lessons learned, the PUREX Deactivation Project has become the national model for the safe transition of contaminated facilities to shut down status.

  5. Oxidative Dissolution of UO2 in a Simulated Groundwater Containing...

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

    under oxic conditions. Field and laboratory studies have implicated iron sulfide minerals as redox buffers or oxidant scavengers that may slow oxidation of reduced U(VI) solid...

  6. UO Annual Report 2011 Page 1 2011 Annual Report

    E-Print Network [OSTI]

    . CONDITIONS NOT MET Student Performance Criteria SPC 9: Non-Western Traditions progress to ensure that we are meeting 2009 SPC A. 9. Historical Traditions and Global Culture. SPC 13: Human Diversity The visiting team report states

  7. UoS PhD Studentship! A University of Sheffield PhD studentship within the framework of Project

    E-Print Network [OSTI]

    Dixon, Peter

    Sunshine is available, held jointly at the Solar Physics and Space Plasma Research Centre (SP2 RC), School

  8. , 227 240 . Half-life Radioactive decay Reaction with 2200 m/s neutrons

    E-Print Network [OSTI]

    Hong, Deog Ki

    . 700-800 U2N3 UN2 . 1.2.5. 1.5 . , . UF4 UF6 UO2 HF . UO3 + 4HF Boils at 1 atm UF6 Black ~1427 8.95 UF4 Green 1036 1457 6.70 U4F17 Black 430 Disp. 6.94 U2F9 390 Disp. 7.06 UF5 White 348 Disp. 6.45 UF6 Colorless 64.05 56.54 5.06 UCl3 Olive green 837 1657 5.51 UCl4 Dark

  9. Lattice anisotropy, electronic and chemical structures of uranyl carbonate, UO2CO3, from

    E-Print Network [OSTI]

    Boyer, Edmond

    localization function mapping, oxygen atoms are found to preferentially bind with uranium for one sublattice Binary and ternary uranium natural and synthetic compounds are known and characterized (mainly X the electron band structure, the equation of state (EOS) as well as the properties of chemi- cal bonding

  10. A brief history of the PUREX and UO{sub 3} facilities

    SciTech Connect (OSTI)

    Gerber, M.S.

    1993-11-01T23:59:59.000Z

    The Plutonium-Uranium Extraction (PUREX) Plant, conceived during the early Cold War years, was a vehicle to increase significantly US nuclear weapons production capacity. The original PUREX Plant was a concrete rectangle 1,005 feet long and 61.5 feet wide. The shielding capacity of the concrete was designed so that personnel in non-regulated service areas would not receive radiation in excess of 0.1 millirem per hour. This report discusses the design of the PUREX Plant, the production chronology, projects and equipment changes, equipment decontamination and reuse, waste management, and contamination events that have occurred during the operation of the plant. Additionally, the development and history of the Uranium Trioxide Plant are also covered.

  11. Lattice thermal conductivity of UO{sub 2} using ab-initio and classical molecular dynamics

    SciTech Connect (OSTI)

    Kim, Hyoungchul [Department of Mechanical Engineering, University of Michigan, Ann Arbor, Michigan 48109 (United States); High-Temperature Energy Materials Research Center, Korea Institute of Science and Technology, Seoul 136–791 (Korea, Republic of); Kim, Moo Hwan [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Pohang 790-784 (Korea, Republic of); Kaviany, Massoud, E-mail: kaviany@umich.edu [Department of Mechanical Engineering, University of Michigan, Ann Arbor, Michigan 48109 (United States); Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Pohang 790-784 (Korea, Republic of)

    2014-03-28T23:59:59.000Z

    We applied the non-equilibrium ab-initio molecular dynamics and predict the lattice thermal conductivity of the pristine uranium dioxide for up to 2000?K. We also use the equilibrium classical molecular dynamics and heat-current autocorrelation decay theory to decompose the lattice thermal conductivity into acoustic and optical components. The predicted optical phonon transport is temperature independent and small, while the acoustic component follows the Slack relation and is in good agreement with the limited single-crystal experimental results. Considering the phonon grain-boundary and pore scatterings, the effective lattice thermal conductivity is reduced, and we show it is in general agreement with the sintered-powder experimental results. The charge and photon thermal conductivities are also addressed, and we find small roles for electron, surface polaron, and photon in the defect-free structures and for temperatures below 1500?K.

  12. Recovery of UO{sub 2}/PuO{sub 2} in IFR electrorefining process

    DOE Patents [OSTI]

    Tomczuk, Z.; Miller, W.E.

    1992-01-01T23:59:59.000Z

    This invention is comprised of a process for converting PuO{sub 2} and U0{sub 2} present in an electrorefiner to the chlorides, by contacting the PuO{sub 2} and U0{sub 2} with Li metal in the presence of an alkali metal chloride salt substantially free of rare earth and actinide chlorides for a time and at a temperature sufficient to convert the U0{sub 2} and PuO{sub 2} to metals while converting Li metal to Li{sub 2}O. Li{sub 2}O is removed either by reducing with rare earth metals or by providing an oxygen electrode for transporting 0{sub 2} out of the electrorefiner and a cathode, and thereafter applying an emf to the electrorefiner electrodes sufficient to cause the Li{sub 2}O to disassociate to 0{sub 2} and Li metal but insufficient to decompose the alkali metal chloride salt. The U and Pu and excess lithium are then converted to chlorides by reaction with CdCl{sub 2}.

  13. A DualDisk File System: ext4 Mihai Budiu

    E-Print Network [OSTI]

    Budiu, Mihai

    uranium oxide, UO2 [8,4] and hexavalent uranium based fluorides, UF6 [5], oxides, CaUO4 [9] and CdUO4 [10

  14. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel 

    E-Print Network [OSTI]

    Fu, Chun

    2000-01-01T23:59:59.000Z

    A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck prepared by the Kurchatov Institute of Moscow. The RELAP5 model includes both the primary...

  15. E&nr Ph. S. W.. Wahhgt~n. D.C. 200242174, TIkpbnc (202) 48a60uo

    Office of Legacy Management (LM)

    Institute Rockefeller Institute'for Medical Research University of Rochester Case School of Applied Science, Ohio State University University of Cincinnati University of...

  16. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel

    E-Print Network [OSTI]

    Fu, Chun

    2000-01-01T23:59:59.000Z

    Secondary System Parameters and Calculated Values. . 38 Vl The Sequence of Events during LBLOCA. 46 VII Experimental Design and Calculated Temperatures. . . 57 NOMENCLATURE ATWS BOL CR DBA ECCS FLC HA HP HPIS IAEA I&C Anticipated Transient... postulated accidents such as loss of coolant accident (LOCA) and operational transients such as anticipated transients without scram (ATWS), loss of off-site power, loss of feedwater, loss of flow, and turbine trip. RELAP5 is a one-dimensional code which...

  17. A Study of UO2 Grain Boundary Structure and Thermal Resistance Change under Irradiation using Molecular Dynamics Simulations

    E-Print Network [OSTI]

    Chen, Tianyi

    2013-08-02T23:59:59.000Z

    Our study is focused on the behavior of grain boundaries in uranium dioxide system under irradiation conditions. The research can be seen as two parts: the study of interaction of the grain boundary and the damage cascade, and the calculation...

  18. Fully-coupled engineering and mesoscale simulations of thermal conductivity in UO2 fuel using an implicit multiscale approach

    SciTech Connect (OSTI)

    Michael Tonks; Derek Gaston; Cody Permann; Paul Millett; Glen Hansen; Chris Newman

    2009-08-01T23:59:59.000Z

    Reactor fuel performance is sensitive to microstructure changes during irradiation (such as fission gas and pore formation). This study proposes an approach to capture microstructural changes in the fuel by a two-way coupling of a mesoscale phase field irradiation model to an engineering scale, finite element calculation. This work solves the multiphysics equation system at the engineering-scale in a parallel, fully-coupled, fully-implicit manner using a preconditioned Jacobian-free Newton Krylov method (JFNK). A sampling of the temperature at the Gauss points of the coarse scale is passed to a parallel sequence of mesoscale calculations within the JFNK function evaluation phase of the calculation. The mesoscale thermal conductivity is calculated in parallel, and the result is passed back to the engineering-scale calculation. As this algorithm is fully contained within the JFNK function evaluation, the mesoscale calculation is nonlinearly consistent with the engineering-scale calculation. Further, the action of the Jacobian is also consistent, so the composite algorithm provides the strong nonlinear convergence properties of Newton's method. The coupled model using INL's \\bison\\ code demonstrates quadratic nonlinear convergence and good parallel scalability. Initial results predict the formation of large pores in the hotter center of the pellet, but few pores on the outer circumference. Thus, the thermal conductivity is is reduced in the center of the pellet, leading to a higher internal temperature than that in an unirradiated pellet.

  19. Y H-S I-H HATIOHAL LEAth~~Y~~OF' OtUO ' Industrial Hygiene No.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7 AugustAFRICAN3uj:'I,\ W C 5% "y$ -- :I_.

  20. E&nr Ph. S. W.. Wahhgt~n. D.C. 200242174, TIkpbnc (202) 48a60uo

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling CorpNew 1325.8.Enaineer District andP.Dr.Wm.*

  1. MS Detectors

    SciTech Connect (OSTI)

    Koppenaal, David W.; Barinaga, Charles J.; Denton, M Bonner B.; Sperline, Roger P.; Hieftje, Gary M.; Schilling, G. D.; Andrade, Francisco J.; Barnes IV., James H.

    2005-11-01T23:59:59.000Z

    Good eyesight is often taken for granted, a situation that everyone appreciates once vision begins to fade with age. New eyeglasses or contact lenses are traditional ways to improve vision, but recent new technology, i.e. LASIK laser eye surgery, provides a new and exciting means for marked vision restoration and improvement. In mass spectrometry, detectors are the 'eyes' of the MS instrument. These 'eyes' have also been taken for granted. New detectors and new technologies are likewise needed to correct, improve, and extend ion detection and hence, our 'chemical vision'. The purpose of this report is to review and assess current MS detector technology and to provide a glimpse towards future detector technologies. It is hoped that the report will also serve to motivate interest, prompt ideas, and inspire new visions for ion detection research.

  2. UO Department of Chemistry & Biochemistry -Faculty Research Interests Berglund, Andy -The primary goals of the Berglund lab are to understand the molecular basis of the human disease myotonic

    E-Print Network [OSTI]

    Cina, Jeff

    , physical measurement, and device fabrication to design, build and study new materials and structures that have applications in solar energy harvesting and electrochemical energy storage Cina, Jeffrey A solids that permits them to prepare families of new nanostructured and kinetically stable compounds

  3. Biosciences Undergraduate Research at Nottingham School of Biosciences, UoN, 2009. 1 Assessing the link between forest composition and soil nutrient

    E-Print Network [OSTI]

    Nottingham, University of

    threat of global climate change, concern is growing about the consequence of large scale biodiversity exudates or changes in growth, increasing litter input or nutrient uptake. Nutrient cycling and the plant and therefore more efficient nutrient cycling. The Kamchatka peninsula in Far East Russia makes up the northern

  4. Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels

    SciTech Connect (OSTI)

    Carbajo, J.J.

    2005-05-27T23:59:59.000Z

    The purpose of this report is to quantify the differences between mixed oxide (MOX) and low-enriched uranium (LEU) fuels and to assess in reasonable detail the potential impacts of MOX fuel use in VVER-1000 nuclear power plants in Russia. This report is a generic tool to assist in the identification of plant modifications that may be required to accommodate receiving, storing, handling, irradiating, and disposing of MOX fuel in VVER-1000 reactors. The report is based on information from work performed by Russian and U.S. institutions. The report quantifies each issue, and the differences between LEU and MOX fuels are described as accurately as possible, given the current sources of data.

  5. Hello "Rhythms and Rhymes" FIG student! My name is Brandon Parry and I will be your FIG Assistant this fall at the UO. When fall

    E-Print Network [OSTI]

    Oregon, University of

    , riding my bike and hanging out with my friends. Naturally, being the FA for "Rhythms and Rhymes", I have, and created, in order for people to assert their individual and group identities. The words we use

  6. (front end fuel cycle) 2.1 (CANDU

    E-Print Network [OSTI]

    Hong, Deog Ki

    , , Phosphorus . 2.2. (U3O8) . U235 . UO2 ( ) UF6 ( ) . 2235 U235 UF6 . 2.2.2. UF6 UO2 UF6 UO2 UF4 UF4 UF6 . (1) : (4) : UF4 UF6 . UF4 1600 500 . UF4 UF4 UO2 . UF6 , , 150

  7. ICP-MS Workshop

    SciTech Connect (OSTI)

    Carman, April J.; Eiden, Gregory C.

    2014-11-01T23:59:59.000Z

    This is a short document that explains the materials that will be transmitted to LLNL and DNN HQ regarding the ICP-MS Workshop held at PNNL June 17-19th. The goal of the information is to pass on to LLNL information regarding the planning and preparations for the Workshop at PNNL in preparation of the SIMS workshop at LLNL.

  8. Prof Dr Mr Mrs Ms Prof Dr Mr Mrs Ms

    E-Print Network [OSTI]

    Xu, Jianliang

    Prof Dr Mr Mrs Ms Prof Dr Mr Mrs Ms Standard Room Request Payment Card No Expiry Date Contact or a 1-night applicable room charge will be levied as cancellation charge. * Daily rate will be subject

  9. M.S. Physics Program M.S. in Physics

    E-Print Network [OSTI]

    Hemmers, Oliver

    M.S. Physics Program M.S. in Physics Department(s) Physics and Astronomy College Sciences 1 for later reference. 1. understanding of a variety of fields of physics at the graduate level 2. performance of a physics research project suitable for a masters thesis 3. ability to communicate scientific research

  10. METLIN: MS/MS metabolite data from the MAGGIE Project

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    METLIN is a metabolite database for metabolomics containing over 50,000 structures, it also represents a data management system designed to assist in a broad array of metabolite research and metabolite identification by providing public access to its repository of current and comprehensive MS/MS metabolite data. An annotated list of known metabolites and their mass, chemical formula, and structure are available on the METLIN website. Each metabolite is conveniently linked to outside resources such as the the Kyoto Encyclopedia of Genes and Genomes (KEGG) for further reference and inquiry. MS/MS data is also available on many of the metabolites. The list is expanding continuously as more metabolite information is being deposited and discovered. [from http://metlin.scripps.edu/] Metlin is a component of the MAGGIE Project. MAGGIE is funded by the DOE Genomics: GTL and is an acronym for "Molecular Assemblies, Genes, and Genomics Integrated Efficiently."

  11. Ms. Maria Galanti Site Coordinator

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

    Office 2195 Front Street Logan, Ohio 43138 Dear Ms. Galanti: TRANSMITTAL OF Dl CONSTRUCTION COMPLETION REPORT FOR PHASES I AND II OF THE REMOVAL OF THE X-760 CHEMICAL...

  12. PROCEEDINGS OF WORKSHOP ON THERMOMECHANICAL-HYDROCHEMICAL MODELING FOR A HARDROCK WASTE REPOSITORY. JULY 29-31, 1980. MARRIOTT INN, BERKELEY, CA

    E-Print Network [OSTI]

    Authors, Various

    2010-01-01T23:59:59.000Z

    Experi ments by the BGR in the Asse II", Proc. UoS. /FRG Bi"pp,-- Rothfuchs, T. (1979): "Asse II In-Situ Brine Migrationin the late 1960's in the Asse Salt Mine in the Federal

  13. The Influence of the Linker Geometry in Bis(3-hydroxy-N-methyl-pyridin-2-one) Ligands on Solution-Phase Uranyl Affinity

    E-Print Network [OSTI]

    Szigethy, Géza

    2011-01-01T23:59:59.000Z

    M. S. Murali, K. L. Nash, Solv. Extr. Ion Exch. 2001, 19,dimers of the form [UO 2 L 2 (solv. )] 2 as opposed to thesterically-induced [UO 2 (L)(solv. )] 2 dimer formation, [

  14. Ligand field effects on the multiplet structure of the U4f XPS...

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

    Ligand field effects on the multiplet structure of the U4f XPS of UO2. Ligand field effects on the multiplet structure of the U4f XPS of UO2. Abstract: Ab initio, fully...

  15. Uranyl Sequestration: Synthesis and Structural Characterization of Uranyl Complexes with a Tetradentate Methylterephthalamide Ligand

    E-Print Network [OSTI]

    Ni, Chengbao

    2012-01-01T23:59:59.000Z

    Me 4 N] 8 [L(UO 2 )] 4 tetramer, formed via coordination ofAddition of KOH to the tetramer gave the corresponding2- forms an unexpected tetramer [L(UO 2 )] 48- , in which

  16. Winter 2012 Prof. Carol Silverman Office: 321 Condon Off. hrs. M 4-5, W 12-1:00 PM

    E-Print Network [OSTI]

    in the UO Bookstore are: Sacco, Joe. Safe Area Gorazde: The War in Eastern Bosnia 1992-95. Fantagraphics

  17. Clustering of protein families into functional subtypes using Relative Complexity Measure with reduced

    E-Print Network [OSTI]

    Yanikoglu, Berrin

    @su.sabanciuniv.edu HHO: hotu@bidmc.harvard.edu UOS: ugur@sabanciuniv.edu #12;- 2 - Abstract Background Phylogenetic

  18. MODELING THE PERFORMANCE OF HIGH BURNUP THORIA AND URANIA PWR FUEL

    E-Print Network [OSTI]

    Long, Y.

    Fuel performance models have been developed to assess the performance of ThO[subscript 2]-UO[subscript 2]

  19. Ms. Nancy Slach Department of

    E-Print Network [OSTI]

    /Certificate, Orthodon- tics, 1948 UI Alumni Service Award Ms. Penni Ryan Alumni Relations and Con- tinuing Dental Education 2009 Regents Staff Excellence Award; President designate of the Association of Continuing Dental Education (2013). Dr. Jeffrey Murray Colleges of Medicine and Dentistry Research grant total: $1

  20. The Influence of Linker Geometry on Uranyl Complexation by Rigidly-Linked Bis(3-hydroxy-N-methyl-pyridin-2-one)

    E-Print Network [OSTI]

    Szigethy, Geza

    2011-01-01T23:59:59.000Z

    to the formation of UO 2 L(solv. ) complexes (where L is theUO 2 (bis-Me-3,2-HOPO)(solv. ) (right), tabulated in Tablethe uranyl cation. The U–O solv distances also show little

  1. Page 1 of 2 Risk Management March 2012 Risk Management

    E-Print Network [OSTI]

    Page 1 of 2 Risk Management March 2012 Risk Management Supervisor's Vehicle Incident Report-Employee Volunteer Drivers License No. State of Issue UO Certification Date UO Driver Training Date Vehicle Information: License No. Make Model Year UO Vehicle # Motorpool Outside Rental Personal Vehicle Incident

  2. Forest fires, explosions, and random trees Edward Crane

    E-Print Network [OSTI]

    Wirosoetisno, Djoko

    Forest fires, explosions, and random trees Edward Crane HIMR, UoB 13th January 2014 #12 and James Martin at the University of Oxford. Edward Crane (HIMR, UoB) Forest fires, explosions, and random process and the Brownian CRT. Edward Crane (HIMR, UoB) Forest fires, explosions, and random trees 13th

  3. ARM - Instrument - ptr-ms

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006Datastreamstwrcam40mgovInstrumentsmwr3c Documentation MWR3CgovInstrumentspgsgovInstrumentsptr-ms

  4. LA-5097-MS INFORMAL REPORT

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling CorpNewCF INDUSTRIES,L? .-I I2 m.m 2L5097-MS

  5. 2d-LC-MS/MS Method-ORNL Developed for Bacteriophage

    E-Print Network [OSTI]

    Sullivan, Matthew B.

    mass spectrometry (2d-LC-MS/MS) method was optimized for bacteriophage by Kristen Corrier undergraduate should be. 4. The mass spectrometer is run in data dependent mode, specific settings should be optimized

  6. JOURNALDEPHYSIQUEIV ColloqueC7,supplkmentauJournaldePhysique111,Volume3,novembre1993

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ) connected to an image analyzer system, made of a host computer (SUN 3.140) and an Imaging Technology image~alaas'slreqapalou-rod.paquasa~daqITrMs~oqroede3pa-ralurs aqqpuesuTr.Juaa.xBaqq'lap~odayqoqpaqqals7Tnsa-r~e3~801oqd~ourauosA~uo E'C -saps)sq~edpaJaTUrspaqsr~od30saseurr~3suo~'~3a~aK~epuo3as #12;Granulometric and granulomorphic distributions on projected

  7. Analysis of Thiodiglycol: Validation of Semi-Volatile Analysis by HPLC-MS/MS by EPA Method MS777

    SciTech Connect (OSTI)

    Owens, J; Koester, C

    2008-07-24T23:59:59.000Z

    The Environmental Protection Agency's (EPA) Region 5 Chicago Regional Laboratory (CRL) developed a method for the analysis of thiodiglycol, the breakdown product of the sulfur mustard HD, in water by high performance liquid chromatography tandem mass spectrometry (HPLC-MS/MS), titled Method EPA MS777 (hereafter referred to as EPA CRL SOP MS777). This draft standard operating procedure (SOP) was distributed to multiple EPA laboratories and to Lawrence Livermore National Laboratory, which was tasked to serve as a reference laboratory for EPA's Environmental Reference Laboratory Network (ERLN) and to develop and validate analytical procedures. The primary objective of this study was to verify the analytical procedures described in MS777 for analysis of thiodiglycol in aqueous samples. The gathered data from this study will be used to: (1) demonstrate analytical method performance; (2) generate quality control acceptance criteria; and (3) revise the SOP to provide a validated method that would be available for use during a homeland security event. The data contained in this report will be compiled, by EPA CRL, with data generated by other EPA Regional laboratories so that performance metrics of Method EPA MS777 can be determined.

  8. Investigation of Uranium Polymorphs

    SciTech Connect (OSTI)

    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

    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.

  9. MS.BIOLOGY.THESIS ACADEMIC LEARNING PLAN

    E-Print Network [OSTI]

    O'Laughlin, Jay

    effectively to constructive feedback. Job Prospects for Biology Graduates MS in Biology Bioremediation Biotechnology Medical Research Industry Government Education Microbiology Health Professions Research Health Food Production Pollution Control Environmental Diagnostics Forestry Agriculture #12;APPENDIX B

  10. Energy Management Standards (EnMS)

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

    Management Standards (EnMS) Paul Scheihing U.S. DOE January, 2009 2 Why an Energy Management Standard? Most energy efficiency in industry is achieved through changes in how energy...

  11. Laser Ablation-ICP-MS Analysis of Dissected Tissue: A

    E-Print Network [OSTI]

    Hopkins, William A.

    Laser Ablation-ICP-MS Analysis of Dissected Tissue: A Conservation-Minded Approach to Assessing the animal. In this paper, we report on the application of laser ablation-ICP-MS (LA- ICP-MS) for sampling

  12. Sources of Technical Variability in Quantitative LC-MS Proteomics...

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

    Sources of Technical Variability in Quantitative LC-MS Proteomics: Human Brain Tissue Sample Analysis. Sources of Technical Variability in Quantitative LC-MS Proteomics: Human...

  13. Electrospray Ionization Tandem Mass Spectrometry (ESI-MS/MS)-Based Shotgun Lipidomics

    SciTech Connect (OSTI)

    Mezengie, Giorgis I.

    2011-01-11T23:59:59.000Z

    In the past decade, many new strategies for mass spectrometry (MS)-based analyses of lipids have been developed. Lipidomics is one of the most promising research fields to emerge as a result of these advances in MS. Currently, mass spectrometric analysis of lipids involves two complementary approaches: direct infusion (shotgun lipidomics) and liquid chromatography coupled to MS. In this chapter, I will demonstrate the approach of shotgun lipidomics using electrospray ionization tandem MS for the analysis of lipid molecular species directly from crude biological extracts of tissue or fluids.

  14. Analysis of Ethanolamines: Validation of Semi-Volatile Analysis by HPLC-MS/MS by EPA Method MS888

    SciTech Connect (OSTI)

    Owens, J; Vu, A; Koester, C

    2008-10-08T23:59:59.000Z

    The Environmental Protection Agency's (EPA) Region 5 Chicago Regional Laboratory (CRL) developed a method titled 'Analysis of Diethanolamine, Triethanolamine, n-Methyldiethanolamine, and n-Ethyldiethanolamine in Water by Single Reaction Monitoring Liquid Chromatography/Tandem Mass Spectrometry (LC/MS/MS): EPA Method MS888'. This draft standard operating procedure (SOP) was distributed to multiple EPA laboratories and to Lawrence Livermore National Laboratory, which was tasked to serve as a reference laboratory for EPA's Environmental Reference Laboratory Network (ERLN) and to develop and validate analytical procedures. The primary objective of this study was to validate and verify the analytical procedures described in 'EPA Method MS888' for analysis of the listed ethanolamines in aqueous samples. The gathered data from this validation study will be used to: (1) demonstrate analytical method performance; (2) generate quality control acceptance criteria; and (3) revise the SOP to provide a validated method that would be available for use during a homeland security event. The data contained in this report will be compiled, by EPA CRL, with data generated by other EPA Regional laboratories so that performance metrics of 'EPA Method MS888' can be determined.

  15. Analysis of Carbamate Pesticides: Validation of Semi-Volatile Analysis by HPLC-MS/MS by EPA Method MS666

    SciTech Connect (OSTI)

    Owens, J; Koester, C

    2008-05-14T23:59:59.000Z

    The Environmental Protection Agency's (EPA) Region 5 Chicago Regional Laboratory (CRL) developed a method for analysis of aldicarb, bromadiolone, carbofuran, oxamyl, and methomyl in water by high performance liquid chromatography tandem mass spectrometry (HPLC-MS/MS), titled Method EPA MS666. This draft standard operating procedure (SOP) was distributed to multiple EPA laboratories and to Lawrence Livermore National Laboratory, which was tasked to serve as a reference laboratory for EPA's Environmental Reference Laboratory Network (ERLN) and to develop and validate analytical procedures. The primary objective of this study was to validate and verify the analytical procedures described in MS666 for analysis of carbamate pesticides in aqueous samples. The gathered data from this validation study will be used to: (1) demonstrate analytical method performance; (2) generate quality control acceptance criteria; and (3) revise the SOP to provide a validated method that would be available for use during a homeland security event. The data contained in this report will be compiled, by EPA CRL, with data generated by other EPA Regional laboratories so that performance metrics of Method EPA MS666 can be determined.

  16. Molten uranium dioxide structure and dynamics

    SciTech Connect (OSTI)

    Skinner, L. B. [Argonne National Laboratory (ANL), Argonne, IL (United States); Stony Brook Univ., Stony Brook, NY (United States); Materials Development Inc., Arlington Heights, IL (United States); Parise, J. B. [Stony Brook Univ., Stony Brook, NY (United States); Benmore, C. J. [Argonne National Laboratory (ANL), Argonne, IL (United States); Weber, J. K.R. [Materials Development Inc., Arlington Heights, IL (United States); Williamson, M. A. [Argonne National Laboratory (ANL), Argonne, IL (United States); Tamalonis, A. [Materials Development Inc., Arlington Heights, IL (United States); Hebden, A. [Argonne National Laboratory (ANL), Argonne, IL (United States); Wiencek, T. [Argonne National Laboratory (ANL), Argonne, IL (United States); Alderman, O. L.G. [Materials Development Inc., Arlington Heights, IL (United States); Guthrie, M. [Carnegie Inst., Washington, DC (United States); Leibowitz, L. [Argonne National Laboratory (ANL), Argonne, IL (United States)

    2014-11-20T23:59:59.000Z

    Uranium dioxide (UO2) is the major nuclear fuel component of fission power reactors. A key concern during severe accidents is the melting and leakage of radioactive UO2 as it corrodes through its zirconium cladding and steel containment. Yet, the very high temperatures (>3140 kelvin) and chemical reactivity of molten UO2 have prevented structural studies. In this work, we combine laser heating, sample levitation, and synchrotron x-rays to obtain pair distribution function measurements of hot solid and molten UO2. The hot solid shows a substantial increase in oxygen disorder around the lambda transition (2670 K) but negligible U-O coordination change. On melting, the average U-O coordination drops from 8 to 6.7 ± 0.5. Molecular dynamics models refined to this structure predict higher U-U mobility than 8-coordinated melts.

  17. Molten uranium dioxide structure and dynamics

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

    Skinner, L. B. [Argonne National Laboratory (ANL), Argonne, IL (United States); Stony Brook Univ., Stony Brook, NY (United States); Materials Development Inc., Arlington Heights, IL (United States); Parise, J. B. [Stony Brook Univ., Stony Brook, NY (United States); Benmore, C. J. [Argonne National Laboratory (ANL), Argonne, IL (United States); Weber, J. K.R. [Materials Development Inc., Arlington Heights, IL (United States); Williamson, M. A. [Argonne National Laboratory (ANL), Argonne, IL (United States); Tamalonis, A. [Materials Development Inc., Arlington Heights, IL (United States); Hebden, A. [Argonne National Laboratory (ANL), Argonne, IL (United States); Wiencek, T. [Argonne National Laboratory (ANL), Argonne, IL (United States); Alderman, O. L.G. [Materials Development Inc., Arlington Heights, IL (United States); Guthrie, M. [Carnegie Inst., Washington, DC (United States); Leibowitz, L. [Argonne National Laboratory (ANL), Argonne, IL (United States)

    2014-11-20T23:59:59.000Z

    Uranium dioxide (UO2) is the major nuclear fuel component of fission power reactors. A key concern during severe accidents is the melting and leakage of radioactive UO2 as it corrodes through its zirconium cladding and steel containment. Yet, the very high temperatures (>3140 kelvin) and chemical reactivity of molten UO2 have prevented structural studies. In this work, we combine laser heating, sample levitation, and synchrotron x-rays to obtain pair distribution function measurements of hot solid and molten UO2. The hot solid shows a substantial increase in oxygen disorder around the lambda transition (2670 K) but negligible U-O coordination change. On melting, the average U-O coordination drops from 8 to 6.7 ± 0.5. Molecular dynamics models refined to this structure predict higher U-U mobility than 8-coordinated melts.

  18. Molten uranium dioxide structure and dynamics

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

    Skinner, L. B.; Parise, J. B.; Benmore, C. J.; Weber, J. K.R.; Williamson, M. A.; Tamalonis, A.; Hebden, A.; Wiencek, T.; Alderman, O. L.G.; Guthrie, M.; et al

    2014-11-20T23:59:59.000Z

    Uranium dioxide (UO2) is the major nuclear fuel component of fission power reactors. A key concern during severe accidents is the melting and leakage of radioactive UO2 as it corrodes through its zirconium cladding and steel containment. Yet, the very high temperatures (>3140 kelvin) and chemical reactivity of molten UO2 have prevented structural studies. In this work, we combine laser heating, sample levitation, and synchrotron x-rays to obtain pair distribution function measurements of hot solid and molten UO2. The hot solid shows a substantial increase in oxygen disorder around the lambda transition (2670 K) but negligible U-O coordination change. Onmore »melting, the average U-O coordination drops from 8 to 6.7 ± 0.5. Molecular dynamics models refined to this structure predict higher U-U mobility than 8-coordinated melts.« less

  19. LA-12968-MS The Unsaturated Hydraulic

    E-Print Network [OSTI]

    LA-12968-MS The Unsaturated Hydraulic Characteristics of the BandelierTuff LosN A T I O N A L L A B technical correctness. #12;The Unsaturated Hydraulic Characteristics of the Bandelier Tuff David B. Rogers........................................................................................................4 Hydraulic Data Presentation

  20. High Field Magnetization measurements of uranium dioxide single crystals (P08358- E003-PF)

    SciTech Connect (OSTI)

    K. Gofryk; N. Harrison; M. Jaime

    2014-12-01T23:59:59.000Z

    Conclusions: Our preliminary high field magnetic measurements of UO2 are consistent with a complex nature of the magnetic ordering in this material, compatible with the previously proposed non-collinear 3-k magnetic structure. Further extensive magnetic studies on well-oriented (<100 > and <111>) UO2 crystals are planned to address the puzzling behavior of UO2 in both antiferromagnetic and paramagnetic states at high fields.

  1. Atomistic Simulations of Uranium Incorporation into Iron (Hydr...

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

    characterize the coordination environments of U incorporated in three Fe-(hydr)oxide minerals: goethite, magnetite, and hematite. The simulations provided information on U-O and...

  2. Crystallographic controls on uranyl binding at the quartz/water...

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

    controls on uranyl binding at the quartzwater interface. Abstract: Molecular dynamics methods were used to simulate UO2(OH)20 binding to pairs of oxo sites on three...

  3. A Coordinate Gradient Descent Method for Linearly Constrained ...

    E-Print Network [OSTI]

    2 (1992),X#" -5s . 29%$ ? uo, Z .-Q. and Tseng, P., Error bounds and convergence analysis of feasible descent methods: a general approach, Ann. Oper. Res.

  4. anhydrous li uranyl: Topics by E-print Network

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

    crystal structure and thermal behavior are reported herein. Experimental Synthesis Uranyl nitrate (UO2(NO31 Hydrothermal synthesis, structure and thermal stability of...

  5. Transition projects FY 1995 multi-year program plan/fiscal year work plan WBS 1.3.1. and 7.1

    SciTech Connect (OSTI)

    Cartmell, D.B.

    1994-09-01T23:59:59.000Z

    This document presents a complete listing and time line of transitional projects associated with the Purex/UO3 deactivation project at the Hanford reservation.

  6. 4th Annual DOE-ERSP PI Meeting: Abstracts

    E-Print Network [OSTI]

    Hazen, Terry C.

    2009-01-01T23:59:59.000Z

    to adhere to hematite and goethite. Two adhesion-deficientUO 2 by ferrihydrite, goethite, and hematite-coated quartzof batch experiments with goethite as the electron acceptor,

  7. RADIOACTIVE ELEMENT REMOVAL FROM WATER USING GRAPHENE OXIDE (GO) 

    E-Print Network [OSTI]

    Concklin, Joshua Paul

    2013-12-19T23:59:59.000Z

    the UO2 and create a water soluble salt of uranyl nitrate (UO2?(NO3)2). This salt will then be dissolved in deionized water to produce a 1ppm solution of uranium. Once the sample solution has been produced, it should be stored in a glass container....84E+04 counts per second ? Total activity expected from sample = 9.57E+04 counts per second A solution containing uranium was created by treating depleted reactor fuel (UO2) with Nitric Acid (HNO3) to create uranyl nitrate (UO2·(NO3)2) which...

  8. MS 211 -CALCULO NUMERICO -1o http://www.ime.unicamp.br/ ms211/

    E-Print Network [OSTI]

    Sussner, Peter

    MS 211 - C´ALCULO NUM´ERICO - 1o SEM/2010 http://www.ime.unicamp.br/ ms211/ Turma Per Ruggiero e V´era Lucia da Rocha Lopes, C´alculo Num´erico - Aspectos Te´oricos e Computacionais, Pearson´etodos Num´ericos para as Engenharias e Ci^encias Aplicadas, Edi- tora da Unicamp, Campinas, segunda edi

  9. Simultaneous MS-IR Studies of Surface Formate Reactivity Under...

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

    MS-IR Studies of Surface Formate Reactivity Under Methanol Synthesis Conditions on CuSiO2. Simultaneous MS-IR Studies of Surface Formate Reactivity Under Methanol Synthesis...

  10. Ms. Judy Clayton, Chair Paducah Citizens Advisory Board EHI Consultant...

    Office of Environmental Management (EM)

    0 Ms. Judy Clayton, Chair Paducah Citizens Advisory Board EHI Consultants, Inc. 1 1 1 Memorial Drive Paducah, Kentucky 4200 1 Dear Ms. Clayton: Thank you for your recent letter...

  11. MS.BIOLOGY.NON-THESIS ACADEMIC LEARNING PLAN

    E-Print Network [OSTI]

    O'Laughlin, Jay

    to constructive feedback Job Prospects for Biology Graduates MS/non-thesis in Biology Bioremediation Biotechnology Medical Research Industry Government Education Microbiology Health Professions Research Laboratories Find Food Production Pollution Control Environmental Diagnostics Forestry Agriculture #12;MS

  12. DEBRA ANNE ROACH, M.S. Assistant Dean

    E-Print Network [OSTI]

    Navara, Kristen

    #12;DEBRA ANNE ROACH, M.S. Assistant Dean Director Graduate Enrollment SEAN-MICHAEL GREEN, J.D., LL & Adult Enrollment 845-575-3512 sean-michael.green@marist.edu DEBRA ANNE ROACH, M.S. Assistant Dean

  13. Designing a Digital Version of British Library, Harley MS 4431 

    E-Print Network [OSTI]

    Laidlaw, James; Mansfield, Charlie

    2005-05-12T23:59:59.000Z

    Discusses design for the electronic transcription of MS BL Harley 4431 aims first of all to create a diplomatic corpus made up of the thirty works which Christine de Pizan included in the Queen’s MS. The generally accepted ...

  14. Genizah MS T-S AS 154.342

    E-Print Network [OSTI]

    Unknown

    2011-02-24T23:59:59.000Z

    Possibly payment order or accounting, mentioning M?s? (?), Egypt and 'only three', with Persian-Arabic numerals....

  15. 607 MS Major Code Major College Bachelor's Master's Doctor's

    E-Print Network [OSTI]

    Bolding, M. Chad

    Engineering CAFLS BS MS PhD 824 Biotechnology CAFLS MS 500 Business & Behavioral Science Entomology CAFLS MS PhD #12;402 General CES non 129 Environmental and Natural Res (Natural Resources CAFLS BS 126 Environmental and Natural Resources CAFLS nondegree 127 Environmental

  16. Master of Science (MS), Major: Chemical Engineering Apply Now

    E-Print Network [OSTI]

    Shihadeh, Alan

    Master of Science (MS), Major: Chemical Engineering Apply Now The Chemical Engineering Program to the following degrees: Master of Science, major Chemical Engineering The MS program will be open to students with a Bachelor of Science (BS) in Chemical Engineering, or other related disciplines. The MS program will also

  17. Source term evaluation for UF{sub 6} release event in feed facility at gaseous diffusion plants

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.

    1997-01-30T23:59:59.000Z

    An assessment of UF{sub 6} release accidents was conducted for the feed facility of a gaseous diffusion plant (GDP). Release rates from pig-tail connections were estimated from CYLIND code predictions, whereas, MELCOR was utilized for simulating reactions of UF{sub 6} with moisture and consequent transport of UO{sub 2}F{sub 2} aerosols and HF vapor through the building and to the environment. Two wind speeds were utilized. At the high end (Case 1) a wind speed of {approximately} 1 m/s (200 fpm) was assumed to flow parallel to the building length. At the low end (Case 2) to represent stagnant conditions a corresponding wind speed of 1 cm/s (2 fpm) was utilized. A further conservative assumption was made to specify no closure of crane and train doors at either end of the building. Relaxation of this assumption should provide for additional margins. Results indicated that, for the high (200 fpm) wind speed, close to 66% of the UO{sub 2}F{sub 2} aerosols and 100% of the HF gas get released to the environment over a 10-minute period. However, for the low (2 fpm) wind speed, negligible amount ({approximately} 1% UO{sub 2}F{sub 2}) of aerosols get released even over a 2 hour period.

  18. ARM - Campaign Instrument - ptr-ms

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492air Comments? We would love to hear from you!jpl Comments?govInstrumentsprecipisogovInstrumentsptr-ms

  19. To: Ms. Dorothy Riehle, FOIA Officer,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin Transition in2, 2003 (NextTime-ResolvedTo: Ms. Dorothy Riehle, FOIA

  20. LA-8318-MS Informal Report I

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem Not Found Item Not Found TheHot electron dynamics in grapheneInverter8318-MS

  1. Alignment of LC-MS Data Using Peptide Features

    E-Print Network [OSTI]

    Tang, Xincheng

    2012-02-14T23:59:59.000Z

    Spectrometry MALDI Matrix Assisted Laser Desorption Ionization MS Mass Spectrometry MS/MS Tandem Mass Spectrometry M/Z Mass-To-Charge Ratio PNNL Paci c Northwest National Laboratory RT Retention Time SELDI Surface Enhanced Laser Desorption Ionization... alignment. In this paper, two Shewanella datasets are obtained from Paci c Northwest Na- tional Laboratory (PNNL) and they were analyzed by SEQUEST on di erent days. SEQUEST correlates uninterpreted tandem mass spectra of peptides with amino acid...

  2. Short Curriculum Vitae of Kyriacos Petratos

    E-Print Network [OSTI]

    Petratos, Kyriacos

    of Crete (UoC). The set-up comprises an X-ray rotating anode generator (RU-3HR, Rigaku), a crystal cryo-cooling system (X-stream, Rigaku) and a system of `imaging-plate' photon detector (Mar300, Mar Department, UoC. Participation in committees for the supervision of graduate students' progress

  3. SUSS-EX CLUB STEERING GROUP The 21st meeting will be held at 17.00 on Friday 11th November 2011

    E-Print Network [OSTI]

    Sussex, University of

    /6/11) [b] UoS 50th birthday (10/9/11) `Sussex through the ages' ~Bob Benewick, Jennifer Platt & David Smith (late summer & December /January) ~ Jennifer Platt [e] Christmas Party (December) ~ Sue Bullock [g 2010 Jennifer Platt July 2010 Ken Wheeler September 2010 David Smith November 2010 Charles Goldie

  4. On the possibility of using uranium-beryllium oxide fuel in a VVER reactor

    SciTech Connect (OSTI)

    Kovalishin, A. A.; Prosyolkov, V. N.; Sidorenko, V. D. [National Research Center Kurchatov Institute (Russian Federation); Stogov, Yu. V., E-mail: YVStogov@mephi.ru [National Research Nuclear University MEPhI (Russian Federation)

    2014-12-15T23:59:59.000Z

    The possibility of using UO{sub 2}-BeO fuel in a VVER reactor is considered with allowance for the thermophysical properties of this fuel. Neutron characteristics of VVER fuel assemblies with UO{sub 2}-BeO fuel pellets are estimated.

  5. s.haszeldine@ed.ac.uk Scottish Centre for Carbon Storage, Petrobras 2008 1 University of Edinburgh (est 1583)

    E-Print Network [OSTI]

    Haszeldine, Stuart

    , and HWU Chem Eng Legislation and regulation UoE Europa Institute, Dundee CEPMLP Energy systems & Social, environmental impacts (HWU, BGS UoE) Licensing and regulation Enhanced hydrocarbon recovery (HWU #12;s for Carbon Storage, Petrobras 2008 9 Sci-tech. background Geoscience, Power plant Capture, Pipeline Legal

  6. Magnetization measurements of uranium dioxide single crystals (P08358-E002-PF)

    SciTech Connect (OSTI)

    K. Gofryk; V. Zapf; M. Jaime

    2014-12-01T23:59:59.000Z

    Conclusions Our preliminary magnetic susceptibility measurements of UO2 point to complex nature of the magnetic ordering in this material, consistent with the proposed non-collinear 3-k magnetic structure. Further extensive magnetic studies are planned to address the puzzling behavior of UO2 in both antiferromagnetic and paramagnetic states.

  7. JOURNAL OF GEOPHYSICAL RESEARCH, VOL. 97, NO. A9, PAGES 13,911-13,914, SEPTEMBER 1, 1992 Comment on "Dayside Pickup Oxygen Ion Precipitation at Venus and Mars'

    E-Print Network [OSTI]

    Johnson, Robert E.

    on "Dayside Pickup Oxygen Ion Precipitation at Venus and Mars' Spatial Distributions, Energy Deposition; McGrath and Johnson, 1987]and by locally generated"pickup ions" [e.g., Kozyra et al., 1982; Ishimoto a hemisphericallyaveragedyield for ejection of oxygen atoms (O) from an oxygen exosphere, Y0= [rr(T> Uo)+ (6/·2)(otSn)/Uo]/o'd (1

  8. MS. CHERYL ZAHNISER (Chair) 5915 Beach Drive SW

    E-Print Network [OSTI]

    .com MRS. GAIL HAYES DAVIS MS `74 ArtEd; BS `69 ArtEd Executive Director (retired) Young Audiences.stangelandlandscape.com MR. DOUG STREETER Arch `80 Design Principal Perkins + Will 1221 Second Avenue, Ste. 200 Seattle, WA 98101 206.381.6007 doug.streeter@perkinswill.com www.perkinswill.com MS. JULIE STOTT B-IArch `77

  9. GRADUATE STUDENT HANDBOOK Vol. I. Master Programs (MS and ME)

    E-Print Network [OSTI]

    .2 Degree Requirements 3.2.1 MS and ME Degree Requirements in Civil Engineering and Environmental.1 Welcome Welcome to the graduate program of the Department of Civil and Environmental Engineering and Environmental Engineering: Master of Engineering (M.E.) in Civil Engineering Master of Science (M.S.) in Civil

  10. Ms. Maushumi, Head Mistress Babul Sarkar, Vice President

    E-Print Network [OSTI]

    Nahar, Sultana Nurun

    Ms. Maushumi, Head Mistress Babul Sarkar, Vice President Char Domdoama Primary School Vill: Char Razzaq-Shamsun Best Teacher Award and Abdul Awal Sarkar Best Student Awards in Char Domdoma Primary School Dear Ms. Maushumi and Mr. Sarkar, My proposal for the introduction of one teaching and three

  11. Investigation of the metabolism of Substance-P at the blood-brain barrier using LC-MS/MS

    E-Print Network [OSTI]

    Chappa, Arvind K.; Cooper, Joshua D.; Audus, Kenneth L.; Lunte, Susan M.

    2007-01-01T23:59:59.000Z

    , the metabolism of SP was investigated using an in vitro model of the BBB and LC-MS/MS. Substance P metabolism was found to be non-saturable in the concentration range of 100 nM to 10 ?M, with approximately 70% of the peptide remaining intact after 5 hrs...

  12. Some effects of data base variations on numerical simulations of uranium migration

    SciTech Connect (OSTI)

    Carnahan, C.L.

    1987-12-01T23:59:59.000Z

    Numerical simulations of migration of chemicals in the geosphere depend on knowledge of identities of chemical species and on values of chemical equilibrium constants supplied to the simulators. In this work, some effects of variability in assumed speciation and in equilibrium constants were examined, using migration of uranium as an example. Various simulations were done of uranium migration in systems with varying oxidation potential, pH, and mator component content. A simulation including formation of aqueous species UO/sub 2//sup 2 +/, UO/sub 2/CO/sub 3//sup 0/, UO/sub 2/(CO/sub 3/)/sub 2//sup 2 -/, UO/sub 2/(CO/sub 3/)/sub 3//sup 4 -/, (UO/sub 2/)/sub 2/CO/sub 3/(OH)/sub 3//sup -/, UO/sub 2//sup +/, U(OH)/sub 4//sup 0/, and U(OH)/sub 5//sup -/ is compared to simulation excluding formation of UO/sub 2//sup +/ and U(OH)/sub 5//sup -/. These simulations relied on older data bases, and they are compared to a further simulation using recently published data on formation of U(OH)/sub 4//sup 0/, (UO/sub 2/)/sub 2/CO/sub 3/(OH)/sub 3//sup -/, UO/sub 2/(CO/sub 3/)/sub 5//sup 5 -/, and U(CO/sub 3/)/sub 5//sup 6 -/. Significant differences in dissolved uranium concentrations are noted among the simulations. Differences are noted also in precipitation of two solids, USiO/sub 4/(c) (coffinite) and CaUO/sub 4/(c) (calcium uranate), although the solubility products of the solids were not varied in the simulations. 18 refs., 9 figs., 2 tabs.

  13. Characterization of the Human Pancreatic Islet Proteome by Two-Dimensional LC/MS/MS

    SciTech Connect (OSTI)

    Metz, Thomas O.; Jacobs, Jon M.; Gritsenko, Marina A.; Fontes, Ghislaine; Qian, Weijun; Camp, David G.; Poitout, Vincent J.; Smith, Richard D.

    2006-12-01T23:59:59.000Z

    Research to elucidate the pathogenesis of type 1 diabetes mellitus has traditionally focused on the genetic and immunological factors associated with the disease, and, until recently, has not considered the target cell. While there have been reports detailing proteomic analyses of established islet cell lines or isolated rodent islets, the information gained is not always easily extrapolated to humans. Therefore, extensive characterization of the human islet proteome could result in better understanding of islet biology and lead to more effective treatment strategies. We have applied a two-dimensional LC-MS/MS-based analysis to the characterization of the human islet proteome, resulting in the detection of 29,021 unique peptides corresponding to 4,925 proteins. As expected, major islet hormones (insulin, glucagon, somatostatin), beta-cell enriched secretory products (IAPP), ion channels (K-ATP channel), and transcription factors (PDX-1, Nkx 6.1, HNF-1 beta) were detected. In addition, significant proteome coverage of metabolic enzymes and cellular pathways was obtained, including the insulin signaling cascade and the MAP kinase, NF-??, and JAK/STAT pathways. This work represents the most extensive characterization of the human islet proteome to date and provides a peptide reference library that may be utilized in future studies of islet biology and type 1 diabetes.

  14. MS211 -CALCULO NUMERICO -1o semestre de 2008

    E-Print Network [OSTI]

    Gomes Ruggiero, Márcia A.

    MS211 - C´ALCULO NUM´ERICO - 1o semestre de 2008 (http://www.ime.unicamp.br/ms211) turma professor¸c~ao: o suporte computacional b´asico da disciplina ser´a o MatLab. BIBLIOGRAFIA · "C´alculo Num´erico¸c~ao, Editora Pearson, 1997. · "M´etodos Num´ericos", Maria Cristina Cunha, 2a edi¸c~ao, Editora da Unicamp

  15. MS211 -CALCULO NUMERICO -2o semestre de 2007

    E-Print Network [OSTI]

    Sussner, Peter

    MS211 - C´ALCULO NUM´ERICO - 2o semestre de 2007 (http://www.ime.unicamp.br/ms211) Turma Professor suporte computacional da disciplina ser´a o MatLab. BIBLIOGRAFIA · "C´alculo Num´erico - Aspectos Te Pearson, 1997. · "M´etodos Num´ericos", Maria Cristina Cunha, 2a edi¸c~ao, Editora da Unicamp, 2000

  16. An LC-IMS-MS Platform Providing Increased Dynamic Range for High...

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

    a tryptic digest of mouse blood plasma and analyzed with both a LC-Linear Ion Trap Fourier Transform (FT) MS and LC-IMS-TOF MS. The LC-FT MS detected thirteen out of the twenty...

  17. MS17AM LEAK CHECKER The MS17AM is a manual valve version of the MS17AB. Since it is a manual unit, some care must be

    E-Print Network [OSTI]

    Massey, Thomas N.

    MS17AM LEAK CHECKER The MS17AM is a manual valve version of the MS17AB. Since it is a manual unit, some care must be exercised in the sequencing of the valves. The most important things to remember are that during normal leak testing: 1. The THROTTLE VALVE is NEVER opened unless the ROUGH VALVE has been

  18. Fast and accurate database searches with MS-GF+Percolator

    SciTech Connect (OSTI)

    Granholm, Viktor; Kim, Sangtae; Navarro, Jose' C.; Sjolund, Erik; Smith, Richard D.; Kall, Lukas

    2014-02-28T23:59:59.000Z

    To identify peptides and proteins from the large number of fragmentation spectra in mass spectrometrybased proteomics, researches commonly employ so called database search engines. Additionally, postprocessors like Percolator have been used on the results from such search engines, to assess confidence, infer peptides and generally increase the number of identifications. A recent search engine, MS-GF+, has previously been showed to out-perform these classical search engines in terms of the number of identified spectra. However, MS-GF+ generates only limited statistical estimates of the results, hence hampering the biological interpretation. Here, we enabled Percolator-processing for MS-GF+ output, and observed an increased number of identified peptides for a wide variety of datasets. In addition, Percolator directly reports false discovery rate estimates, such as q values and posterior error probabilities, as well as p values, for peptide-spectrum matches, peptides and proteins, functions useful for the whole proteomics community.

  19. This form is for use by MS students applying for a 2nd MS, Engineer or PhD degrees or for Engineer

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    This form is for use by MS students applying for a 2nd MS, Engineer or PhD degrees or for Engineer degree students applying for PhD. The form should be completed and returned to the CEE department office degree goal: ( ) 2nd MS ( ) Engineer ( ) PhD Field of study

  20. (WPI-iCeMS) Pure Nano Drugs*

    E-Print Network [OSTI]

    Takada, Shoji

    (WPI-iCeMS) SN-38 50 nm * Pure Nano Drugs* SN-38 10 HepG2* JST (-STEP Permeation and Retention (EPR)* EPR 20100 nm SN-38 SN-38 * SN-38 * SN-38 20 SN-38 Pure Nano Drugs

  1. SPE-163690-MS Synthetic, Geomechanical Logs for Marcellus Shale

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    SPE-163690-MS Synthetic, Geomechanical Logs for Marcellus Shale M. O. Eshkalak, SPE, S. D of production from shale gas reservoirs. In this study, synthetic geomechanical logs (Including following-driven models are developed that are capable of generating synthetic geomechanical logs from conventional logs

  2. Deborah K. Smith Department of Geology and Geophysics, MS 22

    E-Print Network [OSTI]

    Smith, Deborah K.

    Deborah K. Smith Department of Geology and Geophysics, MS 22 Woods Hole Oceanographic Institution: Jordan, T. H., H. W. Menard, and D.K. Smith, Density and size distribution of seamounts in the eastern. Smith, H. W. Menard, J. A. Orcutt and T. H. Jordan, Seismic reflection site survey: correlation

  3. PhD Chemical Engineering MS Chemical Engineering

    E-Print Network [OSTI]

    Collins, Gary S.

    phenomena in nature and technology. The chemical engineer leverages knowledge of molecular processes across1 PhD Chemical Engineering MS Chemical Engineering Bylaws Gene and Linda Voiland School of Chemical Engineering and Bioengineering College of Engineering and Architecture Approved by Voiland School faculty

  4. The Next Generation Isotope Ratio MS DELTA V Advantage

    E-Print Network [OSTI]

    Lachniet, Matthew S.

    on front panel - All pumps inside - Low noise design #12;T The Next Generation Isotope Ratio MS More than with intrinsic alignment of all ion optical components - Integrated signal amplifiers and digitizers - All ion - Comprehensive set of automated diagnostics · Compact and user-friendly design - Small footprint - Space for on

  5. MS in Water, Society, and Policy University of Arizona

    E-Print Network [OSTI]

    Fay, Noah

    MS in Water, Society, and Policy University of Arizona Biological Sciences East, Room 325 Phone of scholarship. The Water, Society and Policy Program draws on the expertise of scientists, social scientists and the Environment School of Geography and Development Water Resources Research Center Institute

  6. Ms. Vicki Cowart Secretary of the Board of Trustees

    E-Print Network [OSTI]

    Executive Officer of Planned Parenthood of the Rocky Mountains. Previously she served for ten years as the State Geologist and Director of the State of Colorado Geological Survey. Early in her career she worked as a geophysicist for several oil and gas companies and was a District Manager for Schlumberger Well Services. Ms

  7. GRADUATE HANDBOOK M.S. and PhD Programs

    E-Print Network [OSTI]

    GRADUATE HANDBOOK M.S. and PhD Programs in Mechanical Engineering and Engineering Mechanics another MSU program 8 2.3 Admission Requirements: Ph.D. Programs.................................................. 9 2.3.1 Regular Status. 9 2.3.2 Accelerated Ph.D. Program Entry 9 2.3.3 Provisional Status. 10 2

  8. Electrolytic process for preparing uranium metal

    DOE Patents [OSTI]

    Haas, Paul A. (Knoxville, TN)

    1990-01-01T23:59:59.000Z

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

  9. Extreme Performance Scalable Operating Systems Final Progress Report (July 1, 2008 ���¢�������� October 31, 2011)

    SciTech Connect (OSTI)

    Allen D. Malony; Sameer Shende

    2011-10-31T23:59:59.000Z

    This is the final progress report for the FastOS (Phase 2) (FastOS-2) project with Argonne National Laboratory and the University of Oregon (UO). The project started at UO on July 1, 2008 and ran until April 30, 2010, at which time a six-month no-cost extension began. The FastOS-2 work at UO delivered excellent results in all research work areas: * scalable parallel monitoring * kernel-level performance measurement * parallel I/0 system measurement * large-scale and hybrid application performance measurement * onlne scalable performance data reduction and analysis * binary instrumentation

  10. Complexation of Gluconate with Uranium(VI) in Acidic Solutions: Thermodynamic Study with Structural Analysis

    SciTech Connect (OSTI)

    Zhang, Zhicheng; Helms, G.; Clark, S. B.; Tian, Guoxin; Zanonato, PierLuigi; Rao, Linfeng

    2009-01-05T23:59:59.000Z

    Within the pC{sub H} range of 2.5 to 4.2, gluconate forms three uranyl complexes UO{sub 2}(GH{sub 4}){sup +}, UO{sub 2}(GH{sub 3})(aq), and UO{sub 2}(GH{sub 3})(GH{sub 4}){sup -}, through the following reactions: (1) UO{sub 2}{sup 2+} + GH{sub 4}{sup -} = UO{sub 2}(GH{sub 4}){sup +}, (2) UO{sub 2}{sup 2+} + GH{sub 4}{sup -} = UO{sub 2}(GH{sub 3})(aq) + H{sup +}, and (3) UO{sub 2}{sup 2+} + 2GH{sub 4}{sup -} = UO{sub 2}(GH{sub 3})(GH{sub 4}){sup -} + H{sup +}. Complexes were inferred from potentiometric, calorimetric, NMR, and EXAFS studies. Correspondingly, the stability constants and enthalpies were determined to be log {Beta}{sub 1} = 2.2 {+-} 0.3 and {Delta}H{sub 1} = 7.5 {+-} 1.3 kJ mol{sup -1} for reaction (1), log {Beta}{sub 2} = -(0.38 {+-} 0.05) and {Delta}H{sub 2} = 15.4 {+-} 0.3 kJ mol{sup -1} for reaction (2), and log {Beta}{sub 3} = 1.3 {+-} 0.2 and {Delta}H{sub 3} = 14.6 {+-} 0.3 kJ mol{sup -1} for reaction (3), at I = 1.0 M NaClO{sub 4} and t = 25 C. The UO{sub 2}(GH{sub 4}){sup +} complex forms through the bidentate carboxylate binding to U(VI). In the UO{sub 2}(GH{sub 3})(aq) complex, hydroxyl-deprotonated gluconate (GH{sub 3}{sup 2-}) coordinates to U(VI) through the five-membered ring chelation. For the UO{sub 2}(GH{sub 3})(GH{sub 4}){sup -} complex, multiple coordination modes are suggested. These results are discussed in the context of trivalent and pentavalent actinide complexation by gluconate.

  11. MS211 -CALCULO NUMERICO -2o semestre de 2011

    E-Print Network [OSTI]

    Sussner, Peter

    MS211 - C´ALCULO NUM´ERICO - 2o semestre de 2011 turma professor sala e-mail A ´Alvaro R. De Pierro. An´alise Num´erica. Pioneira Thompson Learning, 2003. 2. M.C.Cunha. M´etodos Num´ericos. 2a edi¸c~ao, Editora da Unicamp, 2000. 3. M.A.Gomes Ruggiero, V. L. da Rocha Lopes. C´alculo Num´erico - Aspectos Te

  12. MS211 -CALCULO NUMERICO -2o semestre de 2014

    E-Print Network [OSTI]

    Sussner, Peter

    MS211 - C´ALCULO NUM´ERICO - 2o semestre de 2014 Turma Professor Sala­IMECC e-mail A M. Aparecida. Darezzo. C´alculo Num´erico - Aprendizagem com Apoio de Software. Thompson Learning, 2008. 2. R.L.Burden, J.D. Faires. An´alise Num´erica. Pioneira Thompson Learning, 2003. 3. M.C.Cunha. M´etodos Num´ericos

  13. Method for factor analysis of GC/MS data

    DOE Patents [OSTI]

    Van Benthem, Mark H; Kotula, Paul G; Keenan, Michael R

    2012-09-11T23:59:59.000Z

    The method of the present invention provides a fast, robust, and automated multivariate statistical analysis of gas chromatography/mass spectroscopy (GC/MS) data sets. The method can involve systematic elimination of undesired, saturated peak masses to yield data that follow a linear, additive model. The cleaned data can then be subjected to a combination of PCA and orthogonal factor rotation followed by refinement with MCR-ALS to yield highly interpretable results.

  14. Two-locus linkage analysis in multiple sclerosis (MS)

    SciTech Connect (OSTI)

    Tienari, P.J. (National Public Health Institute, Helsinki (Finland) Univ. of Helsinki (Finland)); Terwilliger, J.D.; Ott, J. (Columbia Univ., New York (United States)); Palo, J. (Univ. of Helsinki (Finland)); Peltonen, L. (National Public Health Institute, Helsinki (Finland))

    1994-01-15T23:59:59.000Z

    One of the major challenges in genetic linkage analyses is the study of complex diseases. The authors demonstrate here the use of two-locus linkage analysis in multiple sclerosis (MS), a multifactorial disease with a complex mode of inheritance. In a set of Finnish multiplex families, they have previously found evidence for linkage between MS susceptibility and two independent loci, the myelin basic protein gene (MBP) on chromosome 18 and the HLA complex on chromosome 6. This set of families provides a unique opportunity to perform linkage analysis conditional on two loci contributing to the disease. In the two-trait-locus/two-marker-locus analysis, the presence of another disease locus is parametrized and the analysis more appropriately treats information from the unaffected family member than single-disease-locus analysis. As exemplified here in MS, the two-locus analysis can be a powerful method for investigating susceptibility loci in complex traits, best suited for analysis of specific candidate genes, or for situations in which preliminary evidence for linkage already exists or is suggested. 41 refs., 6 tabs.

  15. Improved Quality Control Processing of Peptide-centric LC-MS...

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

    Quality Control Processing of Peptide-centric LC-MS Proteomics Data. Improved Quality Control Processing of Peptide-centric LC-MS Proteomics Data. Abstract: In the analysis of...

  16. A Top-Down LC-FTICR MS-Based Strategy for Characterizing Oxidized...

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

    Top-Down LC-FTICR MS-Based Strategy for Characterizing Oxidized Calmodulin in Activated Macrophages . A Top-Down LC-FTICR MS-Based Strategy for Characterizing Oxidized Calmodulin...

  17. FT-ICR MS optimization for the analysis of intact proteins. ...

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

    FT-ICR MS optimization for the analysis of intact proteins. FT-ICR MS optimization for the analysis of intact proteins. Abstract: Fourier-transform ion cyclotron resonance (FT-ICR)...

  18. Effects of the anesthesia agents benozocaine and tricaine methanesulfonate (MS-222) on

    E-Print Network [OSTI]

    Kane, Andrew S.

    1 Effects of the anesthesia agents benozocaine and tricaine methanesulfonate (MS-222) on immune anesthesia ­ 10 min MS-222 ­ 14 min benzocaine #12;3 Materials and Methods Control Rinse MS-222 Benzocaine Control Anesthesia Recovery ASW ASW Aquaria 7 days Materials and Methods: Experiment 1 · Blood collection

  19. Aerospace Engineering Aircraft and Spacecraft Design BS, MS Space Transportation and Exploration

    E-Print Network [OSTI]

    Su, Xiao

    Engineering BS, MS Chemical Engineering Biotechnology BS, MS Environmental Health and Safety Semiconductors and Polymers Processing Civil Engineering Construction BS, MS Environmental Geotechnical Structural and Environmental Engineering 408-924-3900 www.cee.sjsu.edu Computer Engineering 408-924-4150 www

  20. Mini-Project Assignment: MS2a Bioinformatics and Computational Biology

    E-Print Network [OSTI]

    Goldschmidt, Christina

    1 Mini-Project Assignment: MS2a Bioinformatics and Computational Biology Deadline TWO COPIES of your completed mini-project for MS2a Bioinformatics and Computational Biology should be handed-project assignment are on pages 2-4 below. #12;2 Mini-Project Assignment: MS2a Bioinformatics and Computational

  1. Physical Separation and Multiphase

    E-Print Network [OSTI]

    Sóbester, András

    - research into CVD and HVOF coatings for subsea choke valve applications. s US Navy - understanding the processes of charge generation in gear contacts as a predictive maintenance tool. s DRA/UoS - corrosion

  2. workshop.report.indd

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

    3( 66*:4-01,(56(-&-(6&1+-?-'+:()1::'+)03( Figure 7. (Left) Phase fi eld calculation using empirical free energy model (after SY Hu et al) & (Right) Irradiated UO2...

  3. Evaluation of alternative fuel cycle strategies for nuclear power generation in the 21st century

    E-Print Network [OSTI]

    Boscher, Thomas

    2005-01-01T23:59:59.000Z

    The deployment of fuel recycling through either CONFU (COmbined Non-Fertile and UO2 fuel) thermal watercooled reactors (LWRs) or fast ABR (Actinide Burner Reactor) reactors is compared to the Once-Through LWR reactor system ...

  4. Influence of Temperature on the Corrosion of Uranium Dioxide Nuclear Fuel

    SciTech Connect (OSTI)

    Broczkowski, Michael E.; Noel, Jamie J.; Shoesmith, David W. [Chemistry, The University of Western Ontario, 1151 Richmond St., London, N6A 5B7 (Canada)

    2007-07-01T23:59:59.000Z

    The anodic dissolution of UO{sub 2} has been studied at 60 deg. C and the results compared to previous observations at 22 deg. C. The rate of oxidation / dissolution was determined electrochemically at constant potentials in the range -500 mV to 500 mV (vs. SCE). The composition of the electrochemically oxidized surface was determined by X-Ray Photoelectron Spectroscopy (XPS). The onset of oxidation (UO{sub 2} {yields} UO{sub 2+x}) occurred at approximately the same potential (-400 mV) at both temperatures. However, the conversion of U{sub V} to U{sub VI}, and hence to soluble UO{sub 2}{sup 2+}, was accelerated by temperature. This acceleration of dissolution caused the development of acidity at localized sites on the fuel surface at lower (less oxidizing) potentials ({>=} 100 mV) at 60 deg. C than at 22 deg. C ({>=} 350 mV)

  5. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques NGSI Research Overview and Update on NDA Techniques

    E-Print Network [OSTI]

    A., V. Mozin, S.J. Tobin, L.W. Cambell, J.R. Cheatham, C.R. Freeman, C.J. Gesh,

    2012-01-01T23:59:59.000Z

    considered one of the 17x17 PWR assemblies from the NGSIplutonium signal because in a PWR spent fuel its content isspectra for a single PWR fuel pin with fresh and spent UO 2

  6. On the Disposition of Graphite Containing TRISO Particles and the Aqueous Transport of Radionuclides via Heterogeneous Geological Formations

    E-Print Network [OSTI]

    van den Akker, Bret Patrick

    2012-01-01T23:59:59.000Z

    element) 0.225 (compact only) 5.144 Graphite CSNF 21-PWR12-PWR 44-BWR 24-BWR UO2 21 PWR fuel assemblies 12 PWR fuel assemblies, 44

  7. Microsoft PowerPoint - MOX Adventure_Reactor Subcommittee_Tamara...

    National Nuclear Security Administration (NNSA)

    MOX Fuel at Duke Energy MOX Fuel and NMMSS Page 3 MOX Fuel - General MOX fuel pellets from former weapons plutonium Blend of 5% PuO 2 with 95% depleted UO 2 Like...

  8. CX-012689: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Experimental Validation of UO2 Microstructural Evolution for NEAMS tool MARMOT – University of Florida CX(s) Applied: B3.6Date: 41869 Location(s): FloridaOffices(s): Nuclear Energy

  9. Subsurface Uranium Fate and Transport: Integrated Experiments and Modeling of Coupled Biogeochemical Mechanisms of Nanocrystalline Uraninite Oxidation by Fe(III)-(hydr)oxides - Project Final Report

    SciTech Connect (OSTI)

    Peyton, Brent M. [Montana State University; Timothy, Ginn R. [University of California Davis; Sani, Rajesh K. [South Dakota School of Mines and Technology

    2013-08-14T23:59:59.000Z

    Subsurface bacteria including sulfate reducing bacteria (SRB) reduce soluble U(VI) to insoluble U(IV) with subsequent precipitation of UO2. We have shown that SRB reduce U(VI) to nanometer-sized UO2 particles (1-5 nm) which are both intra- and extracellular, with UO2 inside the cell likely physically shielded from subsequent oxidation processes. We evaluated the UO2 nanoparticles produced by Desulfovibrio desulfuricans G20 under growth and non-growth conditions in the presence of lactate or pyruvate and sulfate, thiosulfate, or fumarate, using ultrafiltration and HR-TEM. Results showed that a significant mass fraction of bioreduced U (35-60%) existed as a mobile phase when the initial concentration of U(VI) was 160 µM. Further experiments with different initial U(VI) concentrations (25 - 900 ?M) in MTM with PIPES or bicarbonate buffers indicated that aggregation of uraninite depended on the initial concentrations of U(VI) and type of buffer. It is known that under some conditions SRB-mediated UO2 nanocrystals can be reoxidized (and thus remobilized) by Fe(III)-(hydr)oxides, common constituents of soils and sediments. To elucidate the mechanism of UO2 reoxidation by Fe(III) (hydr)oxides, we studied the impact of Fe and U chelating compounds (citrate, NTA, and EDTA) on reoxidation rates. Experiments were conducted in anaerobic batch systems in PIPES buffer. Results showed EDTA significantly accelerated UO2 reoxidation with an initial rate of 9.5?M day-1 for ferrihydrite. In all cases, bicarbonate increased the rate and extent of UO2 reoxidation with ferrihydrite. The highest rate of UO2 reoxidation occurred when the chelator promoted UO2 and Fe(III) (hydr)oxide dissolution as demonstrated with EDTA. When UO2 dissolution did not occur, UO2 reoxidation likely proceeded through an aqueous Fe(III) intermediate as observed for both NTA and citrate. To complement to these laboratory studies, we collected U-bearing samples from a surface seep at the Rifle field site and have measured elevated U concentrations in oxic iron-rich sediments. To translate experimental results into numerical analysis of U fate and transport, a reaction network was developed based on Sani et al. (2004) to simulate U(VI) bioreduction with concomitant UO2 reoxidation in the presence of hematite or ferrihydrite. The reduction phase considers SRB reduction (using lactate) with the reductive dissolution of Fe(III) solids, which is set to be microbially mediated as well as abiotically driven by sulfide. Model results show the oxidation of HS– by Fe(III) directly competes with UO2 reoxidation as Fe(III) oxidizes HS– preferentially over UO2. The majority of Fe reduction is predicted to be abiotic, with ferrihydrite becoming fully consumed by reaction with sulfide. Predicted total dissolved carbonate concentrations from the degradation of lactate are elevated (log(pCO2) ~ –1) and, in the hematite system, yield close to two orders-of-magnitude higher U(VI) concentrations than under initial carbonate concentrations of 3 mM. Modeling of U(VI) bioreduction with concomitant reoxidation of UO2 in the presence of ferrihydrite was also extended to a two-dimensional field-scale groundwater flow and biogeochemically reactive transport model for the South Oyster site in eastern Virginia. This model was developed to simulate the field-scale immobilization and subsequent reoxidation of U by a biologically mediated reaction network.

  10. anti-ganglioside gd2 antibodies: Topics by E-print Network

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

    Dillon; Barry; M. Gray 3 Determination of Gd concentration profile in UO2-Gd2O3 fuel pellets CERN Preprints Summary: A transversal mapping of the Gd concentration was measured in...

  11. Pacific Northwest Solar Radiation Data

    E-Print Network [OSTI]

    Oregon, University of

    Pacific Northwest Solar Radiation Data UO SOLAR MONITORING LAB Physics Department -- Solar Energy Center 1274 University of Oregon Eugene, Oregon 97403-1274 April 1, 1999 #12;Hourly solar radiation data

  12. Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR

    E-Print Network [OSTI]

    Mertens, Paul Gustaaf

    1971-01-01T23:59:59.000Z

    An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and ...

  13. Changes in U(VI) speciation upon sorption onto montmorillonite from aqueous and organic solutions

    SciTech Connect (OSTI)

    Chisholm-Brause, C.; Morris, D.E.; Eller, P.G.; Buscher, T.; Conradson, S.D.

    1991-01-01T23:59:59.000Z

    The speciation of UO{sub 2}{sup 2+} and UO{sub 2}{sup 2+} Tributylphosphate (TBP) mixtures has been investigated in solution and intercalated with the reference smectite clay SAz-1 using x-ray absorption, Raman, and luminescence spectroscopies. Neither aquated UO{sub 2}{sup 2+} nor its TBP complex undergoes any detectable changes in uranium oxidation state on intercalation. Further, at the pH values employed in this work, there is no evidence for hydrolysis of the uranium species to generate dimeric or higher order uranium oligomers. However, we do find indications that the structures of the solution complexes are altered on intercalation, particularly for the UO{sub 2}{sup 2+}/TBP system. In addition, several lines of evidence suggest that, at the loading levels used in this study, the uranyl species may be interacting with two or more spectroscopically distinguishable sites on SAz-1. 29 refs., 3 figs., 2 tabs.

  14. Proton Radiography at Los Alamos National Laboratory (pRad)

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

    pRad User Program pRad-uo@lanl.gov P-25 Subatomic Physics P-Division LANSCE pRad logo Los Alamos National Laboratory has used high energy protons as a probe in flash...

  15. Laboratory Experiments and their Applicability 

    E-Print Network [OSTI]

    Steinhaus, Thomas; Jahn, Wolfram

    2007-11-14T23:59:59.000Z

    In conjunction with the Dalmarnock Fire Tests a series of laboratory tests have been conducted at the BRE Centre for Fire Safety Engineering at the University of Edinburgh (UoE) in support of the large scale tests. These ...

  16. MFR PAPER 1031 Traw ls and traps capture

    E-Print Network [OSTI]

    a carapace II idlh of 7 inches and a \\\\eighl of more than 2.5 pounds (WillieI'. 1966), A cammer· ci al prl,\\uo, of ,\\ ,hart ,upph prl)UULCr "I red .:rab

  17. Annual Report 2008 -- Office of the Chief Financial Officer (OCFO)

    E-Print Network [OSTI]

    Fernandez, Jeffrey

    2009-01-01T23:59:59.000Z

    C R A D A - Small Business CRADA • Othei Total CooperativeInformation ($K) uo.ooo DOEM&O CRADA WFO Program (WN| BT FY2006 FY2007 T DOEM&O CRADA WFO Program (WN| Universities

  18. Department of architecturein portlanD

    E-Print Network [OSTI]

    recognized for educating architects who understand and practice sustainable design. The UO architecture program is rated in the top three for sustainable design education based on surveys of U.S. architectural . . . . . . . . . . . . . 24 For further information . . . . . . . . 26 Arch architecture

  19. MARMOT Enhanced

    Broader source: Energy.gov [DOE]

    To develop mechanistic models for fuel thermal conductivity, the Fuel team used supercells up to 55 nm long to determine the thermal conductivity of UO2 with Xe incorporated.

  20. DOE - Office of Legacy Management -- University of California...

    Office of Legacy Management (LM)

    Subject: List of California Sites; May 17, 1989 CA.05-3 - AEC Memorandum; Ball to Smith; Subject: 500 Pounds UO3 - SR-1952; July 10, 1951 CA.05-4 - AEC Memorandum; Blatzs to...

  1. Identification and Characterization of UndA-HRCR-6, an Outer...

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

    MR-1 mutant’s ability to reduce solid phase ferrihydrite at 40% of that for MR-1 wild type, (ii) increased extracellular formation of UO2 associated with the outer membrane...

  2. c-Type Cytochrome-Dependent Formation of U(IV) Nanoparticles...

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

    of mtrC andor omcA significantly affected the in vivo U(VI) reduction rate relative to wild type MR-1. Similar to the wild type, the mutants accumulated UO2 nanoparticles...

  3. Contact Detection and Constraints Enforcement for the Simulation of Pellet/Clad Thermo-Mechanical Contact in Nuclear Fuel Rods

    E-Print Network [OSTI]

    Lebrun-Grandié, Damien Thomas

    2014-03-05T23:59:59.000Z

    As fission process heats up the fuel rods, UO2 pellets stacked on top of each other swell both radially and axially, while the surrounding Zircaloy cladding creeps down, so that the pellets eventually come into contact with the clad...

  4. Electronic structure and ionicity of actinide oxides from first principles L. Petit,1,2,* A. Svane,1 Z. Szotek,2 W. M. Temmerman,2 and G. M. Stocks3

    E-Print Network [OSTI]

    Svane, Axel Torstein

    . A mixture of UO2 and PuO2, where Pu is blended with either natural or depleted uranium, constitutes. INTRODUCTION Actinide oxides play a dominant role in the nuclear fuel cycle.1 For many years, uranium dioxide

  5. Energistyrelsen 9. juni 2008 Centre for Energy, Environment and Health (CEEH)

    E-Print Network [OSTI]

    data for new technologies (Fuel cells, Electrolysis, Wind turbines ..) Present power system optimization Climate change Met. modelling DMI/NERI/UoC Risø Resulting damages and costs on regional and local

  6. Subsurface Biogeochemical Research (SBR) Contractor-Grantee Workshop--Abstracts

    E-Print Network [OSTI]

    Hazen, Terry C.

    2010-01-01T23:59:59.000Z

    UO 2 by ferrihydrite, goethite, and hematite-coated quartzFe(III) oxides (primarily goethite) were present at the timeFe(III), ferrihydrite, goethite, and hematite. Unraveling

  7. ARM - Campaign Instrument - pyran-eko-ms-801

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492air Comments? We would love to hear from you!jplcarter-scott Comments? We would love to heareko-ms-801

  8. Pole- versus MS-mass definitions in the electroweak theory

    E-Print Network [OSTI]

    M. Faisst; J. H. Kuhn; O. Veretin

    2004-03-16T23:59:59.000Z

    Two different two-loop relations between the pole- and the MS-mass of the top quark have been derived in the literature which were based on different treatments of the tadpole diagrams. In addition, the limit M_W^2/m_t^2 \\to 0 was employed in one of the calculations. It is shown that, after appropriate transformations, the results of the two calculations are in perfect agreement. Furthermore we demonstrate that the inclusion of the non-vanishing mass of the W-boson leads to small modifications only.

  9. Bioenergia Brasil S A MS | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof EnergyInnovation in Carbonof AlternativeBioenergia Brasil S A MS Jump to:

  10. Thermodynamics of Uranyl Minerals: Enthalpies of Formation of Uranyl Oxide Hydrates

    SciTech Connect (OSTI)

    K. Kubatko; K. Helean; A. Navrotsky; P.C. Burns

    2005-05-11T23:59:59.000Z

    The enthalpies of formation of seven uranyl oxide hydrate phases and one uranate have been determined using high-temperature oxide melt solution calorimetry: [(UO{sub 2}){sub 4}O(OH){sub 6}](H{sub 2}O){sub 5}, metaschoepite; {beta}-UO{sub 2}(OH){sub 2}; CaUO{sub 4}; Ca(UO{sub 2}){sub 6}O{sub 4}(OH){sub 6}(H{sub 2}O){sub 8}, becquerelite; Ca(UO{sub 2}){sub 4}O{sub 3}(OH){sub 4}(H{sub 2}O){sub 2}; Na(UO{sub 2})O(OH), clarkeite; Na{sub 2}(UO{sub 2}){sub 6}O{sub 4}(OH){sub 6}(H{sub 2}O){sub 7}, the sodium analogue of compreignacite and Pb{sub 3}(UO{sub 2}){sub 8}O{sub 8}(OH){sub 6}(H{sub 2}O){sub 2}, curite. The enthalpy of formation from the binary oxides, {Delta}H{sub f-ox}, at 298 K was calculated for each compound from the respective drop solution enthalpy, {Delta}H{sub ds}. The standard enthalpies of formation from the elements, {Delta}H{sub f}{sup o}, at 298 K are -1791.0 {+-} 3.2, -1536.2 {+-} 2.8, -2002.0 {+-} 3.2, -11389.2 {+-} 13.5, -6653.1 {+-} 13.8, -1724.7 {+-} 5.1, -10936.4 {+-} 14.5 and -13163.2 {+-} 34.4 kJ mol{sup -1}, respectively. These values are useful in exploring the stability of uranyl oxide hydrates in auxiliary chemical systems, such as those expected in U-contaminated environments.

  11. Ab Initio Molecular Dynamics Study of the Reaction between Th+ Jia Zhou and H. Bernhard Schlegel*

    E-Print Network [OSTI]

    Schlegel, H. Bernhard

    explored by Jackson et al.15-17 in a study of the reactivity of Th+ , U+ , ThO+ , UO+ , and UO2 in providing additional information. Uranium is one of the most well-studied actinides, and in particular) to examine O-H and N-O bond activation by uranium ions.18-20 In addition to uranium and its oxides, thorium

  12. Production of cerium oxide microsheres by an internal gelation sol-gel process

    E-Print Network [OSTI]

    Wegener, Jeffrey J.

    2010-01-14T23:59:59.000Z

    Initiative DSC Differential Scanning Calorimetry DOE Department of Energy HMTA Hexamethylenetetramine MOX Mixed Oxide NERI Nuclear Energy Research Initiative ORNL Oak Ridge National Laboratory PUREX Plutonium and Uranium Extraction RTV Room... Page Figure 1 Dried UO2 spheres (~1000 ?m diameter, left) and sintered UO2 spheres (500 to 532 ?m diameter, right) ........................................... 11 Figure 2 Diagram of Oak Ridge internal gelation sol-gel system...

  13. Fundamental study on recovery uranium oxide from HEPA filters

    SciTech Connect (OSTI)

    Izumida, T. [Hitachi Ltd., Ibaraki (Japan). Hitachi Works; Matsumoto, H.; Tsuchiya, H.; Iba, H. [Hitachi Nuclear Engineering Co., Ltd., Ibaraki (Japan); Noguchi, Y. [Radioactive Waste Management Center, Tokyo (Japan)

    1993-12-31T23:59:59.000Z

    Large numbers of spent HEPA filters are produced at uranium fuel fabrication facilities. Uranium oxide particles have been collected on these filters. Then, a spent HEPA filter treatment system was developed from the viewpoint of recovering the UO{sub 2} and minimizing the volume. The system consists of a mechanical separation process and a chemical dissolution process. This paper describes the results of fundamental experiments on recovering UO{sub 2} from HEPA filters.

  14. Production of cerium oxide microsheres by an internal gelation sol-gel process 

    E-Print Network [OSTI]

    Wegener, Jeffrey J.

    2010-01-14T23:59:59.000Z

    Initiative DSC Differential Scanning Calorimetry DOE Department of Energy HMTA Hexamethylenetetramine MOX Mixed Oxide NERI Nuclear Energy Research Initiative ORNL Oak Ridge National Laboratory PUREX Plutonium and Uranium Extraction RTV Room... Page Figure 1 Dried UO2 spheres (~1000 ?m diameter, left) and sintered UO2 spheres (500 to 532 ?m diameter, right) ........................................... 11 Figure 2 Diagram of Oak Ridge internal gelation sol-gel system...

  15. Infrared Spectroscopy of Discrete Uranyl Anion Complexes

    SciTech Connect (OSTI)

    Gary S. Groenewold; Anita K. Gianotto; Michael E. McIlwain; Michael J. Van Stipdonk; Michael Kullman; Travis J. Cooper; David T. Moore; Nick Polfer; Jos Oomens; Ivan Infante; Lucas Visscher; Bertrand Siboulet; Wibe A. de Jong

    2007-12-01T23:59:59.000Z

    The Free-Electron Laser for Infrared Experiments, FELIX, was used to study the wavelength-resolved multiphoton dissociation of discrete, gas phase uranyl (UO22+) complexes containing a single anionic ligand (A), with or without ligated solvent molecules (S). The apparent uranyl antisymmetric and symmetric stretching frequencies were measured for complexes with general formula [UO2A(S)n]+, where A was either hydroxide, methoxide or acetate, S was water, ammonia, acetone or acetonitrile, and n = 0-2. The values for the antisymmetric stretching frequency for uranyl ligated with only an anion ([UO2A]+) were as low or lower than measurements for [UO2]2+ ligated with as many as five strong neutral donor ligands, and are comparable to solution phase values. This result was surprising because initial DFT calculations using B3LYP predicted values that were 30 – 40 cm-1 higher, consistent with intuition but not with the data. Modification of the basis set and use of alternative functionals improved computational accuracy for the methoxide and acetate complexes, but calculated values for the hydroxide were greater than the measurement regardless of the computational method used. Attachment of a neutral donor ligand S to [UO2A]+ produced [UO2AS]+, which resulted only very modest changes to the uranyl frequency, and did not universally shift values lower. DFT calculations for [UO2AS]+ were in accord with trends in the data, and showed that attachment of the solvent was accommodated by weakening of the U-anion bond as well as the uranyl. When uranyl frequencies were compared for [UO2AS]+ species having different solvent neutrals, values decreased with increasing neutral nucleophilicity.

  16. Infared Spectroscopy of Discrete Uranyl Anion Complexes

    SciTech Connect (OSTI)

    Groenewold, G. S.; Gianotto, Anita K.; McIIwain, Michael E.; Van Stipdonk, Michael J.; Kullman, Michael; Moore, David T.; Polfer, Nick; Oomens, Jos; Infante, Ivan A.; Visscher, Lucas; Siboulet, Bertrand; De Jong, Wibe A.

    2008-01-24T23:59:59.000Z

    The Free-Electron Laser for Infrared Experiments (FELIX) w 1 as used to study the wavelength-resolved multiple photon photodissociation of discrete, gas phase uranyl (UO2 2 2+) complexes containing a single anionic ligand (A), with or without ligated solvent molecules (S). The uranyl antisymmetric and symmetric stretching frequencies were measured for complexes with general formula [UO2A(S)n]+, where A was either hydroxide, methoxide, or acetate; S was water, ammonia, acetone, or acetonitrile; and n = 0-3. The values for the antisymmetric stretching frequency for uranyl ligated with only an anion ([UO2A]+) were as low or lower than measurements for [UO2]2+ ligated with as many as five strong neutral donor ligands, and are comparable to solution phase values. This result was surprising because initial DFT calculations predicted values that were 30–40 cm-1 higher, consistent with intuition but not with the data. Modification of the basis sets and use of alternative functionals improved computational accuracy for the methoxide and acetate complexes, but calculated values for the hydroxide were greater than the measurement regardless of the computational method used. Attachment of a neutral donor ligand S to [UO2A]+ produced [UO2AS]+, which produced only very modest changes to the uranyl antisymmetric stretch frequency, and did not universally shift the frequency to lower values. DFT calculations for [UO2AS]+ were in accord with trends in the data, and showed that attachment of the solvent was accommodated by weakening of the U-anion bond as well as the uranyl. When uranyl frequencies were compared for [UO2AS]+ species having different solvent neutrals, values decreased with increasing neutral nucleophilicity.

  17. Catalysts for the hydrolysis of thiophosphate triesters 

    E-Print Network [OSTI]

    Picot, Alexandre

    2005-02-17T23:59:59.000Z

    ............................................................ Coordination reaction of 66 with uranyl nitrate...................................... NMR spectra of 66 in the presence of increasing amount of UO 2 2+ ....... Coordination chemistry of UO 2 (II... decontaminants during and after World War II. However, the active chlorines would rapidly decompose upon storage and large excesses of bleach were needed for the oxidation of the agents. As these solutions were also corrosive to most surfaces and ineffective...

  18. Free energies and mechanisms of water exchange around Uranyl from first principles molecular dynamics

    SciTech Connect (OSTI)

    Atta-Fynn, Raymond; Bylaska, Eric J.; De Jong, Wibe A.

    2012-02-01T23:59:59.000Z

    From density functional theory (DFT) based ab initio (Car-Parrinello) metadynamics, we compute the activation energies and mechanisms of water exchange between the first and second hydration shells of aqueous Uranyl (UO{sub 2}{sup 2+}) using the primary hydration number of U as the reaction coordinate. The free energy and activation barrier of the water dissociation reaction [UO{sub 2}(OH{sub 2}){sub 5}]{sup 2+}(aq) {yields} [UO{sub 2}(OH{sub 2})4]{sup 2+}(aq) + H{sub 2}O are 0.7 kcal and 4.7 kcal/mol respectively. The free energy is in good agreement with previous theoretical (-2.7 to +1.2 kcal/mol) and experimental (0.5 to 2.2 kcal/mol) data. The associative reaction [UO{sub 2}(OH{sub 2}){sub 5}]{sup 2+}(aq) + H{sub 2}O {yields} [UO{sub 2}(OH{sub 2})6]{sup 2+}(aq) is short-lived with a free energy and activation barrier of +7.9 kcal/mol and +8.9 kca/mol respectively; it is therefore classified as associative-interchange. On the basis of the free energy differences and activation barriers, we predict that the dominant exchange mechanism between [UO{sub 2}(OH{sub 2}){sub 5}]{sup 2+}(aq) and bulk water is dissociative.

  19. Advanced Proliferation Resistant, Lower Cost, Uranium-Thorium Dioxide Fuels for Light Water Reactors (Progress report for work through June 2002, 12th quarterly report)

    SciTech Connect (OSTI)

    Mac Donald, Philip Elsworth

    2002-09-01T23:59:59.000Z

    The overall objective of this NERI project is to evaluate the potential advantages and disadvantages of an optimized thorium-uranium dioxide (ThO2/UO2) fuel design for light water reactors (LWRs). The project is led by the Idaho National Engineering and Environmental Laboratory (INEEL), with the collaboration of three universities, the University of Florida, Massachusetts Institute of Technology (MIT), and Purdue University; Argonne National Laboratory; and all of the Pressurized Water Reactor (PWR) fuel vendors in the United States (Framatome, Siemens, and Westinghouse). In addition, a number of researchers at the Korean Atomic Energy Research Institute and Professor Kwangheon Park at Kyunghee University are active collaborators with Korean Ministry of Science and Technology funding. The project has been organized into five tasks: · Task 1 consists of fuel cycle neutronics and economics analysis to determine the economic viability of various ThO2/UO2 fuel designs in PWRs, · Task 2 will determine whether or not ThO2/UO2 fuel can be manufactured economically, · Task 3 will evaluate the behavior of ThO2/UO2 fuel during normal, off-normal, and accident conditions and compare the results with the results of previous UO2 fuel evaluations and U.S. Nuclear Regulatory Commission (NRC) licensing standards, · Task 4 will determine the long-term stability of ThO2/UO2 high-level waste, and · Task 5 consists of the Korean work on core design, fuel performance analysis, and xenon diffusivity measurements.

  20. Variables and units in Ocean 420 u zonal velocity (east-west) m/s

    E-Print Network [OSTI]

    Thompson, LuAnne

    speed m/s Cg group velocity m/s k wave number 1/m frequency 1/s wavelength m T period s kinematic mixed-layer and water below C E Energy density in surface gravity wave J/m 2 #12;Some constants k Von surface height m g gravitational constant m/s 2 a amplitude of wave in sea surface height m f Coriolis

  1. STEPS: A Grid Search Methodology for Optimized Peptide Identification Filtering of MS/MS Database Search Results

    SciTech Connect (OSTI)

    Piehowski, Paul D.; Petyuk, Vladislav A.; Sandoval, John D.; Burnum, Kristin E.; Kiebel, Gary R.; Monroe, Matthew E.; Anderson, Gordon A.; Camp, David G.; Smith, Richard D.

    2013-03-01T23:59:59.000Z

    For bottom-up proteomics there are a wide variety of database searching algorithms in use for matching peptide sequences to tandem MS spectra. Likewise, there are numerous strategies being employed to produce a confident list of peptide identifications from the different search algorithm outputs. Here we introduce a grid search approach for determining optimal database filtering criteria in shotgun proteomics data analyses that is easily adaptable to any search. Systematic Trial and Error Parameter Selection - referred to as STEPS - utilizes user-defined parameter ranges to test a wide array of parameter combinations to arrive at an optimal "parameter set" for data filtering, thus maximizing confident identifications. The benefits of this approach in terms of numbers of true positive identifications are demonstrated using datasets derived from immunoaffinity-depleted blood serum and a bacterial cell lysate, two common proteomics sample types.

  2. Discovery of novel glucose-regulated proteins in isolated human pancreatic islets using LC-MS/MS-based proteomics

    SciTech Connect (OSTI)

    Rutledge, Alexandra C.; Fontes, Ghislaine; Gritsenko, Marina A.; Norbeck, Angela D.; Anderson, David J.; Waters, Katrina M.; Adkins, Joshua N.; Smith, Richard D.; Poitout, Vincent; Metz, Thomas O.

    2012-07-06T23:59:59.000Z

    The prevalence of diabetes mellitus is increasing dramatically throughout the world, and the disease has become a major public health issue. The most common form of the disease, type 2 diabetes, is due in part to insufficient insulin production from the pancreatic beta-cell. Since glucose is the most potent and physiologically important regulators of beta-cell function under physiological conditions, understanding the insulin secretory defect underlying type 2 diabetes requires a better understanding of glucose regulation of beta-cell function. To this aim, a bottom-up LC-MS/MS-based proteomics approach was used to profile pooled islets from multiple donors under basal (5 mM) or high (15 mM) glucose conditions. Our analysis discovered 256 differentially abundant proteins ({approx}p < 0.05) after 24 h of high glucose exposure from more than 4500 identified in total. Several novel glucose-regulated proteins were elevated under high glucose conditions, including regulators of mRNA splicing (Pleiotropic regulator 1), processing (Retinoblastoma binding protein 6), and function (Nuclear RNA export factor 1), in addition to Neuron navigator 1 and Plasminogen activator inhibitor 1. Proteins whose abundances markedly decreased during incubation at 15 mM glucose included Bax inhibitor 1 and Synaptotagmin-17. Many proteins found to be differentially abundant after high glucose stimulation were uncharacterized or hypothetical. These findings expand our knowledge of glucose regulation of the human islet proteome and suggest many hitherto unknown responses to glucose that require additional studies to explore novel functional roles.

  3. Application of Printed Circuit Board Technology to FT-ICR MS...

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

    Technology to FT-ICR MS Analyzer Cell Construction and Prototyping. Abstract: Although Fourier transform ion cyclotron resonance mass spectrometry (FT-ICRMS) remains themass...

  4. Apply for the OIA Undergraduate Scholarship 1. Your name Mr. Miss, Ms., Mrs.

    E-Print Network [OSTI]

    Rock, Chris

    Apply for the OIA Undergraduate Scholarship 1. Your name Mr. Miss, Ms., Mrs. Family Name (as of birth (country): ____________________________________________ Page 1 of 3 You are eligible

  5. 1 AVS 2001 National Symposium, MS-TuA9 Research supported by

    E-Print Network [OSTI]

    Rubloff, Gary W.

    1 AVS 2001 National Symposium, MS-TuA9 Research supported by In-Situ FTIR Spectroscopy of Maryland, College Park, MD C.A. Gogol, J.F. Kushneir Inficon, Inc. East Syracuse, NY #12;2 AVS 2001 Spectroscopy Acoustic Sensing Ultra-Violet Spectroscopy #12;3 AVS 2001 National Symposium, MS-TuA9 Non

  6. REVISED 01/6/10 -MS SSRL/LCLS User Account Form

    E-Print Network [OSTI]

    Wechsler, Risa H.

    REVISED 01/6/10 - MS SSRL/LCLS User Account Form To open or renew an account, complete and submit Park, CA 94025 FAX: 650-926-8665 TEL: 650-926-3011 SSRL/LCLS SPOKESPERSON): __________________________ _________________________ __________________________ _________________________ __________________________ _________________________ __________________________ _________________________ __________________________ _________________________ SSRL/LCLS USER ACCOUNT INFORMATION #12;REVISED 01/6/10 - MS Why Have a User Account? Each user group

  7. Parallel Processing of Large Datasets from NanoLC-FTICR-MS Measurements

    E-Print Network [OSTI]

    van Nieuwpoort, Rob V.

    for these biomarkers Fourier transform ion cyclotron resonance mass spectrometry (FTICR-MS) is a powerful tool becauseParallel Processing of Large Datasets from NanoLC-FTICR-MS Measurements Y. E. M. van der Burgt, I parallel processing of large mass spectral datasets in a distributed computing environment is demonstrated

  8. Boston University User Fee Structure for ICP-ES, ICP-MS and Laser Labs

    E-Print Network [OSTI]

    Hutyra, Lucy R.

    Cost per sample by laser ablation includes three spots on a sample plus an additional three spotsBoston University User Fee Structure for ICP-ES, ICP-MS and Laser Labs The Department of Earth come to BU and digest their samples in our labs with sufficient training. Laser-ICP-MS cost per sample

  9. Stanford MBA/MS Electrical Engineering Joint Degree Program Page 1 of 20 August 18, 2014

    E-Print Network [OSTI]

    Kay, Mark A.

    Stanford MBA/MS Electrical Engineering Joint Degree Program Page 1 of 20 August 18, 2014 Becky at the end of this transcript. Stanford MBA/MS Electrical Engineering Joint Degree Webinar August 18, 2014 on the Masters in Electrical Engineering and MBA Joint Degree Program. We are going to be together here for 45

  10. ENG BE/ME/MS 504: Polymers and Soft Materials GRS PY 744: Polymer Physics.

    E-Print Network [OSTI]

    Vajda, Sandor

    ENG BE/ME/MS 504: Polymers and Soft Materials GRS PY 744: Polymer Physics. Prof. Rama Bansil Class: Blackboard.bu.edu ME/MS/BE 504 PY 744 A1 POLYMERS AND SOFT MATERIALS (FALL 2012) (12FALLENGME504_A1) E with thermodynamics and statistical mechanics will be assumed. Practical applications of polymers will be discussed

  11. Name Degree Year Notes Thesis title Berg, Ronald J. MS. Zoology 1969

    E-Print Network [OSTI]

    Sheridan, Jennifer

    thermoregulation of fishes in relation to heated effluent from a steam-electric power plant (Lake Monona & 1975 MS.Distribution of fishes near Point Beach Power Plant, Lake Michigan; Ph.D. Habitat selection bluegill and three other panfish in Lake Wingra. Brauer, Garrett MS Zoology 1972 The effect of a power

  12. Gas chromatograph-mass spectrometer (GC/MS) system for quantitative analysis of reactive chemical compounds

    DOE Patents [OSTI]

    Grindstaff, Quirinus G. (Oak Ridge, TN)

    1992-01-01T23:59:59.000Z

    Described is a new gas chromatograph-mass spectrometer (GC/MS) system and method for quantitative analysis of reactive chemical compounds. All components of such a GC/MS system external to the oven of the gas chromatograph are programmably temperature controlled to operate at a volatilization temperature specific to the compound(s) sought to be separated and measured.

  13. Energy Frontier Research Center Center for Materials Science of Nuclear Fuels

    SciTech Connect (OSTI)

    Todd Allen

    2014-04-01T23:59:59.000Z

    Scientific Successes • The first phonon density of states (PDOS) measurements for UO2 to include anharmonicity were obtained using time-of-flight inelastic neutron scattering at the Spallation Neutron Source (SNS), and an innovative, experimental-based anharmonic smoothing technique has enabled quantitative benchmarking of ab initio PDOS simulations. • Direct comparison between anharmonicity-smoothed ab initio PDOS simulations for UO2 and experimental measurements has demonstrated the need for improved understanding of UO2 at the level of phonon dispersion, and, further, that advanced lattice dynamics simulations including finite temperatures approaches will be required for handling this strongly correlated nuclear fuel. • PDOS measurements performed on polycrystalline samples have identified the phonon branches and energy ranges most highly impacted by fission-product and hyper-stoichiometry lattice defects in UO2. These measurements have revealed the broad-spectrum impact of oxygen hyper-stoichiometry on thermal transport. The reduction in thermal conductivity caused by hyper-stoichiometry is many times stronger than that caused by substitutional fission-product impurities. • Laser-based thermo-reflectance measurements on UO2 samples irradiated with light (i.e. He) ions to introduce point defects have been coupled with MD simulations and lattice parameter measurements to determine the role of uranium and oxygen point defects in reducing thermal conductivity. • A rigorous perturbation theory treatment of phonon lifetimes in UO2 based on a 3D discretization of the Brillouin zone coupled with experimentally measured phonon dispersion has been implemented that produces improved predictions of the temperature dependent thermal conductivity. • Atom probe investigations of the influence of grain boundary structure on the segregation behavior of Kr in UO2 have shown that smaller amounts of Kr are present at low angle grain boundaries than at large angle grain boundaries due to the more dense dislocation arrays associated with large angle boundaries; this observation has potentially important ramifications for thermal transport in the high burn-up rim region of light water reactor fuel. • A variable charge interatomic potential has been developed that not only provides an accurate representation of the fluorite UO2 phase, it is further capable of describing continuous stoichiometry changes from UO2 to hyper-stoichiometric UO2+x, to U4O9 and U3O7, and possibly to orthorhombic U3O8. This is the first potential that features many-body effects in all possible interactions (U-U, U-O and O-O) combined with the variable charge. • A theoretical proof has been formulated showing that it is necessary to use the so-called model C phase field approach, consisting of Cahn-Hilliard and Allen-Cahn equations, to describe void evolution in irradiated materials. This work resolved a longstanding literature controversy regarding how to model voids at the mesoscale. • A novel cluster dynamics model has been developed for the nucleation of voids and loops in UO2 under irradiation. This model is important in understanding the defect state of UO2 after irradiation and, more importantly, reveals off-stoichiometric states of irradiated UO2 that are critical for understanding the impact of irradiation on thermal transport. Personnel Successes

  14. Potential incorporation of transuranics into uranium phases

    SciTech Connect (OSTI)

    Kim, C. W.; Wronkiewicz, D. J.; Buck, E. C.

    1999-12-07T23:59:59.000Z

    The UO{sub 2} in spent nuclear fuel is unstable under moist oxidizing conditions and will be altered to uranyl oxide hydrate phases. The transuranics released during the corrosion of spent fuel may also be incorporated into the structures of secondary U{sup 6+} phases. The incorporation of radionuclides into alteration products will affect their mobility. A series of precipitation tests were conducted at either 150 or 90 C for seven days to determine the potential incorporation of Ce{sup 4+} and Nd{sup 3+} (surrogates for Pu{sup 4+} and Am{sup 3+}, respectively) into uranium phases. Ianthinite ([U{sub 2}{sup 4+}(UO{sub 2}){sub 4}O{sub 6}(OH){sub 4}(H{sub 2}O){sub 4}](H{sub 2}O){sub 5}) was produced by dissolving uranium oxyacetate in a solution containing copper acetate monohydrate as a reductant. The leachant used in these tests were doped with either 2.1 ppm cerium or 399 ppm neodymium. Inductively coupled plasma-mass spectrometer (ICP-MS) analysis of the solid phase reaction products which were dissolved in a HNO{sub 3} solution indicates that about 306 ppm Ce (K{sub d} = 146) was incorporated into ianthinite, while neodymium contents were much higher, being approximately 24,800 ppm (K{sub d} = 62). Solid phase examinations using an analytical transmission electron microscope/electron energy-loss spectrometer (AEM/EELS) indicate a uniform distribution of Nd, while Ce contents were below detection. Becquerelite (Ca[(UO{sub 2}){sub 6}O{sub 4}(OH){sub 6}]{center_dot}8H{sub 2}O) was produced by dissolving uranium oxyacetate in a solution containing calcium acetate. The leachant in these tests was doped with either 2.1 ppm cerium or 277 ppm neodymium. ICP-MS results indicate that about 33 ppm Ce (K{sub d}=16) was incorporated into becquerelite, while neodymium contents were higher, being approximately 1,300 ppm (K{sub d}=5). Homogeneous distribution of Nd in the solid phase was noted during AEM/EELS examination, and Ce contents were also below detection.

  15. Updated 7-12 Ms. Markowich is currently the Director of the Battlespace Simulation Department (AIR-5.4) at

    E-Print Network [OSTI]

    and complete adequate testing to demonstrate suitable and effective operations in the joint battlespace. Ms and simulation in a Battlespace environment. Ms. Markowich is the Department of Navy Modeling and Simulation and unmanned partnerships across the Navy and Joint Services. Ms. Markowich previously served as the Deputy

  16. Glass particles produced by laser ablation for ICP-MS measurements

    E-Print Network [OSTI]

    Gonzalez, J.; Liu, C.; Wen, S.; Mao, X.; Russo, R.E.

    2008-01-01T23:59:59.000Z

    Glass particles produced by laser ablation for ICP-MS266nm) was used to generate glass particles from two sets ofWhen the current data on glass were compared with the metal

  17. Training is sponsoring two MS PowerPoint Courses. The course...

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

    Training is sponsoring two MS PowerPoint Courses. The course options feature level 1 and level 2. This email is to gauge interest. The associated cost per class is 200.00. If...

  18. Daniel A. Goldstein 501 Campbell Hall #3411 1 Cyclotron Road MS 50B-4206

    E-Print Network [OSTI]

    Backer, Don

    Daniel A. Goldstein 501 Campbell Hall #3411 1 Cyclotron Road MS 50B-4206 Department of Astronomy., Brown, P.J., Finley, D. A., Fischer, J., Goldstein, D., et al. DES13S2cmm: The First Superluminous

  19. THE NOTRE DAME INDUCTIVELY COUPLED PLASMA -MASS SPECTROMETRY (ICP-MS)

    E-Print Network [OSTI]

    the PQII STE ICP-MS, Electrothermal Vaporization, and Laser Ablation units The report supercedes STE, LaserProbe (tuned to 266 nm, but with 532 nm and 1046 nm capabilities), CETAC Ultrasonic

  20. Engineering (MS, PhD) www.grad.clemson.edu/brochure/IndustEng

    E-Print Network [OSTI]

    Duchowski, Andrew T.

    maintenance. · The Advanced Quality Engineering Laboratory focuses on research to discover scientific design, reliability engineering, tolerance design, human-machine collaborative design optimizationIndustrial Engineering (MS, PhD) www.grad.clemson.edu/brochure/IndustEng #12;Introduction

  1. SOLID STATE ELECTRONICS ECE 103 M.S. COMPREHENSIVE EXAM SPRING 2013

    E-Print Network [OSTI]

    Wang, Deli

    SOLID STATE ELECTRONICS ­ ECE 103 M.S. COMPREHENSIVE EXAM SPRING 2013 1. Semiconductor fundamentals-type Si sample with one end heavily doped so that the carrier concentration is 10 times greater than

  2. TEXTS OF EMPOWERMENT: A FUNCTIONAL RHETORICAL ANALYSIS OF MS. MAGAZINE IN THE FIRST FIVE YEARS

    E-Print Network [OSTI]

    Partlow Lefevre, Sarah Taylor

    2009-07-21T23:59:59.000Z

    Ms. was the first mass mediated feminist magazine in the United States and has often been identified as an icon of the feminist movement. This study examines three rhetorical sites in the magazine during the first five ...

  3. Repres rapides pour dbuter avec MsOffice 2007 Le logo identificateur de

    E-Print Network [OSTI]

    Skorobogatiy, Maksim

    Repères rapides pour débuter avec MsOffice 2007 Le logo identificateur de l'application cache des menus... Il faut cliquer sur le logo pour avoir accès aux icônes ouvrir, enregistrer, etc. #12;Les

  4. REACTIVITY INITIATED ACCIDENT TEST SERIES TEST RIA 1-4 EXPERIMENT PREDICTIONS

    SciTech Connect (OSTI)

    Fukuda, S. K.; Martinson, Z. R.

    1980-02-01T23:59:59.000Z

    The results of the pretest analyses for Test RIA 1-4 are presented. Test RIA 1-4 consists of a 3x3 array of previously irradiated MAP! fuel rods. The rods have 5.7% enriched UO{sub 2} fuel in zircaloy-4 cladding with an average burnup of 5300 MWd/t. The objective for Test RIA 1-4 is to provide information regarding loss-of-coolable fuel rod geometry following RIA event for a radial-average peak fuel enthalpy equivalent to the present licensing criteria of 1172 J/g (280 cal/g UO{sub 2}). Radial averaged peak fuel enthalpies of 1172 J/g (280 cal/g) 1077 J/g {257 cal/g), and 978 J/g (234 cal/g) for the corner, side, and center fuel rods, respectively, are planned to be achieved during a 2.7 ms reactor period power burst. The results of the FRAP-T5 analyses indicate that all nine rods will fail within 26 ms from the start of the power burst due to pellet-cladding mechanical interaction. All of the rods will undergo partial fuel melting. All rods will operate under extended film boiling (>30 sec) conditions and about 70% of the cladding length is expected to be molten. Approximately 15% of the cladding thickness will be oxided. Fuel swelling due to fission gas release and melting combined with fuel and cladding fragmentation, will probably produce a complete coolant flow blockage within the flow shroud.

  5. Materials Science and Engineering BS/MS Program The Department of Materials Science and Engineering offers a combined BS/MS degree

    E-Print Network [OSTI]

    Tipple, Brett

    Materials Science and Engineering BS/MS Program The Department of Materials Science and Engineering currently enrolled in Major Status in the Materials Science and Engineering program can be admitted of Materials Science and Engineering at the University of Utah. A minimum 3.5 GPA is required for admission

  6. SNRE MS and MLA Career Information From 2008-2009 the School of Natural Resources and Environment graduated 84 MS and MLA students.

    E-Print Network [OSTI]

    Edwards, Paul N.

    Corps (Protected Areas Management Advisor) USDA Forest Service Sierra National Forest (Natural Resource (Research Assistant) Matthaei Botanical Gardens and Nichols Arboretum (Natural Areas Manager) Michigan StateSNRE MS and MLA Career Information From 2008-2009 the School of Natural Resources and Environment

  7. Automated Liquid Microjunction Surface Sampling-HPLC-MS/MS Analysis of Drugs and Metabolites in Whole-Body Thin Tissue Sections

    SciTech Connect (OSTI)

    Kertesz, Vilmos [ORNL; Van Berkel, Gary J [ORNL

    2013-01-01T23:59:59.000Z

    A fully automated liquid extraction-based surface sampling system utilizing a commercially available autosampler coupled to high performance liquid chromatography-tandem mass spectrometry (HPLC-MS/MS) detection is reported. Discrete spots selected for droplet-based sampling and automated sample queue generation for both the autosampler and MS were enabled by using in-house developed software. In addition, co-registration of spatially resolved sampling position and HPLC-MS information to generate heatmaps of compounds monitored for subsequent data analysis was also available in the software. The system was evaluated with whole-body thin tissue sections from propranolol dosed rat. The hands-free operation of the system was demonstrated by creating heatmaps of the parent drug and its hydroxypropranolol glucuronide metabolites with 1 mm resolution in the areas of interest. The sample throughput was approximately 5 min/sample defined by the time needed for chromatographic separation. The spatial distributions of both the drug and its metabolites were consistent with previous studies employing other liquid extraction-based surface sampling methodologies.

  8. Surface Decontamination of System Components in Uranium Conversion Plant at KAERI

    SciTech Connect (OSTI)

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

    2003-02-25T23:59:59.000Z

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

  9. EFRC CMSNF Major Accomplishments

    SciTech Connect (OSTI)

    D. Hurley; Todd R. Allen

    2014-09-01T23:59:59.000Z

    The mission of the Center for Material Science of Nuclear Fuels (CMSNF) has been to develop a first-principles-based understanding of thermal transport in the most widely used nuclear fuel, UO2, in the presence of defect microstructure associated with radiation environments. The overarching goal within this mission was to develop an experimentally validated multiscale modeling capability directed toward a predictive understanding of the impact of radiation and fission-product induced defects and microstructure on thermal transport in nuclear fuel. Implementation of the mission was accomplished by integrating the physics of thermal transport in crystalline solids with microstructure science under irradiation through multi institutional experimental and computational materials theory teams from Idaho National Laboratory, Oak Ridge National Laboratory, Purdue University, the University of Florida, the University of Wisconsin, and the Colorado School of Mines. The Center’s research focused on five major areas: (i) The fundamental aspects of anharmonicity in UO2 crystals and its impact on thermal transport; (ii) The effects of radiation microstructure on thermal transport in UO2; (iii) The mechanisms of defect clustering in UO2 under irradiation; (iv) The effect of temperature and oxygen environment on the stoichiometry of UO2; and (v) The mechanisms of growth of dislocation loops and voids under irradiation. The Center has made important progress in each of these areas, as summarized below.

  10. Standard test method for determination of impurities in plutonium: acid dissolution, ion exchange matrix separation, and inductively coupled plasma-atomic emission spectroscopic (ICP/AES) analysis

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2003-01-01T23:59:59.000Z

    1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C 753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %. 1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction to UO2 powder. This specification is applicable to uranium oxide powders for such use from any source. 1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of th...

  11. {sup 99}Tc bioassay by inductively coupled plasma mass spectrometry (ICP-MS)

    SciTech Connect (OSTI)

    Lewis, L.A.

    1998-05-01T23:59:59.000Z

    A means of analyzing {sup 99}Tc in urine by inductively coupled plasma mass spectrometry (ICP-MS) has been developed. Historically, {sup 99}Tc analysis was based on the radiometric detection of the 293 keV E{sub Max} beta decay product by liquid scintillation or gas flow proportional counting. In a urine matrix, the analysis of{sup 99}Tc is plagued with many difficulties using conventional radiometric methods. Difficulties originate during chemical separation due to the volatile nature of Tc{sub 2}O{sub 7} or during radiation detection due to color or chemical quenching. A separation scheme for {sup 99}Tc detection by ICP-MS is given and is proven to be a sensitive and robust analytical alternative. A comparison of methods using radiometric and mass quantitation of {sup 99}Tc has been conducted in water, artificial urine, and real urine matrices at activity levels between 700 and 2,200 dpm/L. Liquid scintillation results based on an external standard quench correction and a quench curve correction method are compared to results obtained by ICP-MS. Each method produced accurate results, however the precision of the ICP-MS results is superior to that of liquid scintillation results. Limits of detection (LOD) for ICP-MS and liquid scintillation detection are 14.67 and 203.4 dpm/L, respectively, in a real urine matrix. In order to determine the basis for the increased precision of the ICP-MS results, the detection sensitivity for each method is derived and measured. The detection sensitivity for the {sup 99}Tc isotope by ICP-MS is 2.175 x 10{sup {minus}7} {+-} 8.990 x 10{sup {minus}9} and by liquid scintillation is 7.434 x 10{sup {minus}14} {+-} 7.461 x 10{sup {minus}15}. A difference by seven orders of magnitude between the two detection systems allows ICP-MS samples to be analyzed for a period of 15 s compared to 3,600 s by liquid scintillation counting with a lower LOD.

  12. Ms Robin Felder | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurTheBrookhaven National LaboratoryJeffreyMs. Linda Cerrone Scientific UserMs.

  13. Ms Rocio Meneses | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurTheBrookhaven National LaboratoryJeffreyMs. Linda Cerrone Scientific UserMs.Rocio

  14. Physiological Stress Responses to Prolonged Exposure to MS-222 and Surgical Implantation in Juvenile Chinook Salmon

    SciTech Connect (OSTI)

    Wagner, Katie A.; Woodley, Christa M.; Seaburg, Adam; Skalski, John R.; Eppard, Matthew B.

    2014-08-07T23:59:59.000Z

    While many studies have investigated the effects of transmitters on fish condition, behavior, and survival, to our knowledge, no studies have taken into account anesthetic exposure time in addition to tag and surgery effects. We investigated stress responses to prolonged MS-222 exposure after stage 4 induction in surgically implanted juvenile Chinook salmon (Oncorhynchus tshawytscha). Survival, tag loss, plasma cortisol concentration, and blood [Na+], [K+], [Ca2+], and pH were measured immediately following anesthetic exposure and surgical implantation and 1, 7, and 14 days post-treatment. Despite the prolonged anesthetic exposure, 3-15 minutes post Stage 4 induction, there were no mortalities or tag loss in any treatment. MS-222 was effective at delaying immediate cortisol release during surgical implantation; however, osmotic disturbances resulted, which were more pronounced in longer anesthetic time exposures. From day 1 to day 14, [Na+], [Ca2+], and pH significantly decreased, while cortisol significantly increased. The cortisol increase was exacerbated by surgical implantation. There was a significant interaction between MS-222 time exposure and observation day for [Na+], [Ca2+], [K+], and pH; variations were seen in the longer time exposures, although not consistently. In conclusion, stress response patterns suggest stress associated with surgical implantation is amplified with increased exposure to MS-222.

  15. Roger E Husser, Jr., M.S., P.E. Planning, Design & Construction

    E-Print Network [OSTI]

    Harms, Kyle E.

    Roger E Husser, Jr., M.S., P.E. Director Planning, Design & Construction Herschel Hoffpauir Associate Director Campus Design & Construction Cliff Gillio Manager Mechanical Engineering Neal Pendleton Project Manager Architect Danielle Welborn Civil Engineer Planning, Design & Construction 1/13/2014 Hari

  16. M.S. Physics and Astronomy, University of Pittsburgh, 2005 Submitted to the Graduate Faculty of

    E-Print Network [OSTI]

    Minnesota, University of

    M.S. Physics and Astronomy, University of Pittsburgh, 2005 Submitted to the Graduate Faculty of the Department of Physics and Astronomy in partial fulfillment of the requirements for the degree of Doctor of Philosophy University of Pittsburgh 2009 Andrew J. Mason B.S. Physics, State University of New York

  17. 182 28th ANNUAL eMS Sorption and Desorption of Quaternary Amine Cations on Clays

    E-Print Network [OSTI]

    Sparks, Donald L.

    182 28th ANNUAL eMS Sorption and Desorption of Quaternary Amine Cations on Clays Z. Z. Zhang and D of organic cations on clays was first studied by Hendricks1. It has been shown that organic cations to measure the cation exchange capacity of the clay2 as well as to determine the specific surface area3

  18. advanced gc-ms technology: Topics by E-print Network

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

    gc-ms technology First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Kasvinsuojeluaineiden jmien...

  19. Microsymposium 34, MS047, 2001 SOME PROBLEMS OF THE EVOLUTION OF ASTEROIDS RUBBLE PILE. G. A

    E-Print Network [OSTI]

    Microsymposium 34, MS047, 2001 SOME PROBLEMS OF THE EVOLUTION OF ASTEROIDS ­ RUBBLE PILE. G the evolution of an asteroid ­ rubble pile ­ as an isolated object. Evidently, we can distinguish two processes the pile of individ- ual fragments with maximum energy and an- gular momentum, the distribution of which

  20. COAL RESOURCES OF THE HANNA AND CARBON By M.S. Ellis,1

    E-Print Network [OSTI]

    Chapter HN COAL RESOURCES OF THE HANNA AND CARBON BASINS By M.S. Ellis,1 G.L. Gunther,2 A.M. Ochs,2, Delaware 1999 Resource assessment of selected Tertiary coal beds and zones in the Northern Rocky in the toolbar to return. 1999 Resource assessment of selected Tertiary coal beds and zones in the Northern Rocky

  1. COAL RESOURCES, POWDER RIVER BASIN By M.S. Ellis,1

    E-Print Network [OSTI]

    Chapter PN COAL RESOURCES, POWDER RIVER BASIN By M.S. Ellis,1 G.L. Gunther,2 A.M. Ochs,2 S, Delaware 1999 Resource assessment of selected Tertiary coal beds and zones in the Northern Rocky in the toolbar to return. 1999 Resource assessment of selected Tertiary coal beds and zones in the Northern Rocky

  2. Computer Engineering Integrated BS/MS Handbook Dated: February 06, 2014

    E-Print Network [OSTI]

    de Lijser, Peter

    Computer Engineering Integrated BS/MS Handbook Dated: February 06, 2014 INTEGRATED BACHELOR AND MASTER OF SCIENCE IN COMPUTER ENGINEERING Computer Engineering Program College of Engineering & Computer@fullerton.edu Telephone: 657-278-5987 Fax: 657-278-5804 http://www.fullerton.edu/ecs/cpe #12;Computer Engineering

  3. 5 year BS/MS Accelerated Physics Program Requirements and other important information.

    E-Print Network [OSTI]

    Crawford, T. Daniel

    5 year BS/MS Accelerated Physics Program Requirements and other important information. Overall GPA 3.300 or better You must maintain a Physics GPA 3.500 or better in core physics classes Must apply the Graduate School accelerated program application online application and include Statement of purpose Two

  4. MS Degree Program in Computer Engineering College of Engineering and Computer Science

    E-Print Network [OSTI]

    de Lijser, Peter

    of computer-based systems, along with an in-depth knowledge in engineering analysis, design, implementationMS Degree Program in Computer Engineering College of Engineering and Computer Science California State University, Fullerton The Computer Engineering Program in the College of Engineering and Computer

  5. Christine L. Harvey, M.S. Page 1 CHRISTINE L. HARVEY

    E-Print Network [OSTI]

    Miami, University of

    ) Department of Advanced Geospatial Modeling and Simulation: · Perform geospatial engineering supporting the Phantom Works CEMSA project (Complex Events Modeling Simulation and Analysis) · Developed prototype P components · Voting member of the OGC (Open Geospatial Consortium) #12;Christine L. Harvey, M.S. Page 2

  6. Sediment profiles of less commonly determined elements measured by Laser Ablation ICP-MS

    E-Print Network [OSTI]

    Mcdonough, William F.

    Sediment profiles of less commonly determined elements measured by Laser Ablation ICP on a short list of high-abundance trace elements. Laser Ablation-Inductively Coupled Plasma-Mass Spectrometry of this investigation is to harness the analytical power of Laser Ablation ICP-MS to explore the behavior of a large

  7. MICROANALYSIS OF SIDEROPHILE ELEMENTS IN FREMDLINGE USING LASER ABLATION ICP-MS. A. J. Campbell

    E-Print Network [OSTI]

    Grossman, Lawrence

    MICROANALYSIS OF SIDEROPHILE ELEMENTS IN FREMDLINGE USING LASER ABLATION ICP-MS. A. J. Campbell 1@midway.uchicago.edu). Introduction: Laser ablation ICP mass spectrome- try has been used to measure distributions of the highly vein in Allende (CV3-oxidized). Experimental: The laser ablation system utilized a CETAC LSX-200 laser

  8. Lee, C-T A Laser Ablation Data Reduction 2006 LASER ABLATION ICP-MS: DATA

    E-Print Network [OSTI]

    Lee, Cin-Ty Aeolus

    Lee, C-T A Laser Ablation Data Reduction 2006 1 LASER ABLATION ICP-MS: DATA REDUCTION Cin-Ty A. Lee 24 September 2006 Analysis and calculation of concentrations Laser ablation analyses are done in time by turning on the laser and ablating the sample, generating a time-dependent signal (Fig. 1). Measurements

  9. Environmental Hydrology and Hydraulic Engineering Degree Requirements for 1year MS

    E-Print Network [OSTI]

    Minsker, Barbara S.

    Environmental Hydrology and Hydraulic Engineering Degree Requirements for 1year MS To obtain (choose 4 hours) Core Courses [Requireda ] CEE 450: Surface Hydrology CEE 451: Env. Fluid Mech. CEE 457: Groundwater Hydrology CEE 434: Environmental Systems I CEE 595W: Seminar CEE 595W: Seminar Choose at least

  10. M.S. in Library and Information Science (M.S.(LIS)) 1. Scope and Objectives

    E-Print Network [OSTI]

    Bandyopadhyay, Antar

    M.S. in Library and Information Science (M.S.(LIS)) 1. Scope and Objectives This is an advanced programme in Library and Information Science with special emphasis on applications of Information technology of information systems. Contributing to the discipline of Library and Information science in terms of research

  11. Degrees Offered: MS Rice University introduced the professional master's degree in environmental

    E-Print Network [OSTI]

    Richards-Kortum, Rebecca

    in the Environment(F) CEVE536Environmental Biotechnology and Bioremediation(S) CEVE 550 Environmental Organic1 Degrees Offered: MS Rice University introduced the professional master's degree in environmental.Asaninterdisciplinaryprogram, it aims to give students the ability to predict environmental problems, not just solve them. It emphasizes

  12. COMPDYN 2011 -May 2011 Corfu Greece MS -Fuzzy methods in computational dynamics

    E-Print Network [OSTI]

    Kreinovich, Vladik

    COMPDYN 2011 - May 2011 Corfu Greece MS - Fuzzy methods in computational dynamics G. C. Marano, M), imprecise simulation methods and tools, subjectivity and heuristic assessments of the engineer, etc-symposium aims to present the latest advances on the application of fuzzy methods in computational mechanics

  13. Childhood Obesity and Insulin-Resistant Cynthia S. Yensel, MS, RN, CPNP

    E-Print Network [OSTI]

    Kihara, Daisuke

    Childhood Obesity and Insulin-Resistant Syndrome Cynthia S. Yensel, MS, RN, CPNP Daniel Preud'Homme, MD, CNS Donna Miles Curry, PhD, RN Childhood obesity has become a national concern, health threat, and is increasing at an alarming rate. Obesity is associated with many comorbidities that last into adulthood

  14. MS ID: JLR/2013/039446 Obesity alters the gustatory perception of lipids in the mouse

    E-Print Network [OSTI]

    Boyer, Edmond

    1 MS ID: JLR/2013/039446 Obesity alters the gustatory perception of lipids in the mouse: plausible INSERM/Université de Bourgogne/AgroSup Dijon, F-21000 Dijon, France. Short title: Obesity decreases-induced obesity; GLP-1, glucagon-like peptide-1; HF, high fat diet; HFHS, high fat/high sucrose diet; LA, linoleic

  15. EB2012-MS-43 ADVANCES IN THE MODELLING OF CARBON/CARBON

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    , the Carbon-Carbon composites (C/C) are materials frequently used in industrial applications such as planeEB2012-MS-43 ADVANCES IN THE MODELLING OF CARBON/CARBON COMPOSITE UNDER TRIBOLOGICAL CONSTRAINTS 1, homogenization, carbon ABSTRACT Thermo mechanical properties of Carbon-Carbon composite (C/C) allow them

  16. CALIBRATING MS-SSIM FOR COMPRESSION DISTORTIONS USING MLDS C. Charrier1

    E-Print Network [OSTI]

    Maloney, Laurence T.

    its performance. Index Terms-- Difference scaling, Genetic algorithm, MS-SSIM. 1. INTRODUCTION Lossy image compression techniques such as JPEG2000 al- low high compression rates, but only at the cost as the compression rate is increased to optimize the construction of psychovisual scale. Such a scale will serve

  17. Improving Alpha Spectrometry Energy Resolution by Ion Implantation with ICP-MS

    SciTech Connect (OSTI)

    Dion, Michael P.; Liezers, Martin; Farmer, Orville T.; Miller, Brian W.; Morley, Shannon M.; Barinaga, Charles J.; Eiden, Gregory C.

    2015-01-01T23:59:59.000Z

    We report results of a novel technique using an Inductively Coupled Plasma Mass Spectrometer (ICP-MS) as a method of source preparation for alpha spectrometry. This method produced thin, contaminant free 241Am samples which yielded extraordinary energy resolution which appear to be at the lower limit of the detection technology used in this research.

  18. ECE 230A/B AP/EDM (Grad) MS Comprehensive Exam FA10

    E-Print Network [OSTI]

    Wang, Deli

    ECE 230A/B ­ AP/EDM (Grad) MS Comprehensive Exam FA10 Problem 1 For the 1-D Ga (everything else unchanged). (d) Replace the Si base with a uniform SiGe base of bandgap 0.1 eV smaller than that of Si (everything else unchanged). #12;

  19. Parentage: MS702-80 x NY88 Developers: Michigan State University and

    E-Print Network [OSTI]

    Douches, David S.

    Boulder (MSF373-8) Parentage: MS702-80 x NY88 Developers: Michigan State University Douches at Michigan State University (517-355- 0271 x 194, douchesd@msu.edu). Morphological and the Michigan Agricultural Experiment Station Plant Variety Protection: In application Strengths: Boulder

  20. ENG BE/ME/MS 504: Polymers and Soft Materials GRS PY 744: Polymer Physics.

    E-Print Network [OSTI]

    Vajda, Sandor

    ENG BE/ME/MS 504: Polymers and Soft Materials GRS PY 744: Polymer Physics. Prof. Rama Bansil Class will be assumed. The course will not emphasize synthetic polymer chemistry. Practical applications of polymers of classes TEXT BOOKS Main Text Book: Required: Polymer Chemistry, 2nd Edition, Hiemenz and Lodge, CRC Press

  1. Predicting the Permeability of Pervious Concretes from Planar Images M.S. Sumanasooriya1

    E-Print Network [OSTI]

    Bentz, Dale P.

    -dimensional material structures. Introduction Pervious concrete (also called Enhanced Porosity Concrete, or porous1 Predicting the Permeability of Pervious Concretes from Planar Images M.S. Sumanasooriya1 , D-dimensional material structures of pervious concretes using two-dimensional digital images obtained from actual

  2. MS/NMR: A Structure-Based Approach for Discovering Protein Ligands and for Drug Design

    E-Print Network [OSTI]

    Powers, Robert

    MS/NMR: A Structure-Based Approach for Discovering Protein Ligands and for Drug Design by Coupling to bind a target protein while obtaining structure-related information as part of a struc- ture-based drug for drug discovery is the utilization of a biological assay to screen a large library of compounds (>100

  3. The Department of Mechanical Engineering and the MS & E Program present: Sandeep Kumar, Ph.D.

    E-Print Network [OSTI]

    JC ME MSE The Department of Mechanical Engineering and the MS & E Program present: Sandeep Kumar, Ph.D. Assistant Professor, Mechanical Engineering Department University of California Riverside-electronics, data storage, sensors and actuators, energy conversion and micro-electro-mechanical systems, where

  4. Calibration and Optimization of PTR-MS for Measurement of Methyl Hydroperoxide (CH3OOH)

    E-Print Network [OSTI]

    Collins, Gary S.

    is to optimize and calibrate a Proton Transfer Reaction Mass Spectrometer (PTR-MS) for the analysis of MHP with the sensitivity to measure this species in air. A promising technique is proton transfer reaction mass by a NSF Research Experience for Undergraduates (REU) grant ATM- 0754990. I would like to thank all

  5. Delineating Diseases by IMS-MS Profiling of Serum N-linked Glycans Dragan Isailovic,,,

    E-Print Network [OSTI]

    Clemmer, David E.

    the number density of the gas is much less than that for condensed phases, this separation can be carried out spectrometry (MS) measurements, with principal component analysis (PCA) for characterizing serum N. Proteome Res. 2008, 7, 1109-1117] of isomers associated with a single glycan (S1H5N4) in which PCA analysis

  6. Profiling of Human Serum Glycans Associated with Liver Cancer and Cirrhosis by IMS-MS

    E-Print Network [OSTI]

    Clemmer, David E.

    in their mobilities through the gas.5 IMS-MS is similar in many ways to electrophoretic migration in the condensed mobility spectrometry/mass spectrometry analysis of N-linked glycans from human serum. Distributions about glycan conformational and isomeric composition. Statistical analysis of data from 22 apparently

  7. Southwest Jiaotong University, Chengdu, China, 19992006 M.S. Materials Science and Engineering, 2006

    E-Print Network [OSTI]

    Pennycook, Steve

    Jiaotong University, Chengdu, China, 1999­2006 M.S. Materials Science and Engineering, 2006 B.S. Materials (865)241-0731 wangk@ornl.gov Publications #12;U.S. Patent Zhou, W. L.; Chen, J. J.; Wang, K. "Aligned

  8. Aggregate production: Fines generation during rock crushing M.S. Guimaraes a

    E-Print Network [OSTI]

    Palomino, Angelica M.

    Aggregate production: Fines generation during rock crushing M.S. Guimaraes a , J.R. Valdes b , A.M.: +1 814 865 9427; fax: +1 814 863 7304. E-mail address: amp26@psu.edu (A.M. Palomino). 0301

  9. MS2a: Bioinformatics and Computational Biology -16MT Recommended Prerequisites

    E-Print Network [OSTI]

    Goldschmidt, Christina

    MS2a: Bioinformatics and Computational Biology - 16MT Recommended Prerequisites None. In particular of statistical analysis and modelling to be properly interpreted. The fields of Bioinformatics and Computational Biology have this as their subject matter and there is no sharp boundary between them. Bioinformatics has

  10. Influence of zirconium and niobium on cathodic deposition of uranium dioxide from alkali chloride melts

    SciTech Connect (OSTI)

    Komarov, V.E.; Borodina, N.P.; Martem`yanova, Z.S. [Institute of High-Temperature Electrochemistry, Ekaterinburg (Russian Federation)

    1995-07-01T23:59:59.000Z

    Electrocrystallization of uranium dioxide from molten chloride electrolytes in the presence of zirconium(IV) and niobium(V) was studied by voltammetry. Zirconium(IV) was found to react with uranium dioxide according to exchange mechanism to form (1 - x)UO{sub 2}{center_dot}xZrO{sub 2} solid solutions. Niobium(IV), a product of cathodic reduction of niobium(V), enters into the exchange reaction with uranium dioxide to yield (1 - y)UO{sub 2{center_dot}y}NbO{sub 2} solid solutions. In the case of simultaneous presence of Nb(V) and Zr(IV) in electrolyte, ternary (1 - x - y)UO{sub 2 {center_dot}x}ZrO{sub 2{center_dot}y}NbO{sub 2} solid solutions are obtained at the cathode surface. Nucleation of the solid solutions phase was shown to occurs at the most active sites of the crystalline precipitate of uranium dioxide.

  11. Kinetics of laser pulse vaporization of uranium dioxide by mass spectrometry

    SciTech Connect (OSTI)

    Tsai, C.

    1981-11-01T23:59:59.000Z

    Safety analyses of nuclear reactors require knowledge of the evaporation behavior of UO/sub 2/ at temperatures well above the melting point of 3140 K. In this study, rapid transient heating of a small spot on a UO/sub 2/ specimen was accomplished by a laser pulse, which generates a surface temperature excursion. This in turn vaporizes the target surface and the gas expands into vacuum. The surface temperature transient was monitored by a fast-response automatic optical pyrometer. The maximum surface temperatures investigated range from approx. 3700 K to approx. 4300 K. A computer program was developed to simulate the laser heating process and calculate the surface temperature evolution. The effect of the uncertainties of the high temperature material properties on the calculation was included in a sensitivity study for UO/sub 2/ vaporization. The measured surface temperatures were in satisfactory agreements.

  12. Effects of air oxidation on the dissolution rate of LWR spent fuel

    SciTech Connect (OSTI)

    Gray, W.J.; Thomas, L.E.; Einziger, R.E.

    1992-11-01T23:59:59.000Z

    Dissolution rates for air-oxidized spent fuel were measured in flowthrough tests. Results from two types of specimens, separated grains and multigrain particles, both in oxidized (U[sub 4]O[sub 9+x]) and unoxidized (UO[sub 2]) conditions indicated only minor effects of oxidation on the surface-area-normalized rates. Similar results were obtained for unirradiated specimens in three different oxidation states (UO[sub 2], U[sub 3]O[sub 7], and U[sub 3]O[sub 8]). These observations have important practical implications for disposal of spent fuel in a geologic repository as well as implications regarding the oxidative dissolution mechanism of UO[sub 2] fuel.

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

    SciTech Connect (OSTI)

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

    2014-01-01T23:59:59.000Z

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

  14. The effect of geometry on symbology recognition

    E-Print Network [OSTI]

    Boyless, James Andrus

    1979-01-01T23:59:59.000Z

    comparisions of these sub-divisions and their advantages and disadvantages' ~dl C ' . H 'df 1d (19649 9 6 d researchers have performed studies using color (Erikson, 1952; Cohen and Senders, 1952; and Muller, 1955) ~ Among these researchers a cons nsus...AaTA fiue 1e Tte1ap 1sa[[errrs aq1 uJaosrp o1 1o[rd aq1 aJTnbaJ uot1eurJogut go sadfi1 q1oH srUa1sfis fieydstp pue s1uaurnJ1sut 1geJoJre aq1 rrroJQ pa~taoaJ st uo rlerUJogut 1oaJTpuZ '1geJoJ&e aq1 go 1uarUuoJznua TeuJa1xa aq1 rUoJg pawTaoaJ st uoT, 1errr...

  15. Using Entrez Utilities Web Service with C# and MS Visual Studio Entrez Utilities Web Service has been tested with

    E-Print Network [OSTI]

    Levin, Judith G.

    Using Entrez Utilities Web Service with C# and MS Visual Studio 2008 Entrez Utilities Web Service Version 9.0.30729.1 SP Creating a Web Service Client Project The following walkthrough describes how to create a new C# project to access the NCBI Entrez Utilities Web Service using MS Visual Studio 2008

  16. Simulating the FTICR-MS Signal of a Decaying Beryllium-7 Ion Plasma in a 2D Electrostatic PIC Code

    E-Print Network [OSTI]

    Hart, Gus

    Simulating the FTICR-MS Signal of a Decaying Beryllium-7 Ion Plasma in a 2D Electrostatic PIC Code the FTICR-MS Signal of a Decaying Beryllium-7 Ion Plasma in a 2D Electrostatic PIC Code Michael Takeshi Nakata Department of Physics and Astronomy Doctor of Philosophy Beryllium-7 (Be-7) only decays

  17. Master's Degree in Agriculture Plant Health Management Option Option Title: Master of Science (MS) in Agriculture: Plant Health

    E-Print Network [OSTI]

    Collins, Gary S.

    Master's Degree in Agriculture ­ Plant Health Management Option Option Title: Master of Science (MS) in Agriculture: Plant Health Management Department(s) or Program(s): Supported of Agricultural, Human, and Natural Resource Sciences (CAHNRS) Contact Name: Dr. Kim Kidwell, Director MS

  18. Evaluation of pneumatic nebulization and ns-laser ablation ICP-MS for bulk elemental analysis and 2-dimensional

    E-Print Network [OSTI]

    Claeys, Philippe

    Evaluation of pneumatic nebulization and ns-laser ablation ICP-MS for bulk elemental analysis and 2 nebulization and ns-laser ablation ICP-MS for bulk elemental analysis and 2-dimensional element mapping of iron 20XX DOI: 10.1039/b000000x The capabilities and limitations of nanosecond laser ablation ICP ­ mass

  19. Elemental fractionation during LA-ICP-MS analysis of silicate glasses: implications for matrix-independent standardization

    E-Print Network [OSTI]

    Weston, Ken

    Elemental fractionation during LA-ICP-MS analysis of silicate glasses: implications for matrix-element solution and from the laser ablation of a range of silicate reference materials (SRM 61X series, MPI-independent standardization of LA- ICP-MS analysis of non-transparent silicates and ceramics, then, is an accurate and viable

  20. UGA IACUC Guidelines for the Use of Tricaine Methanesulfonate (MS-222) in Fishes and Other Aquatic Animals

    E-Print Network [OSTI]

    Hall, Daniel

    UGA IACUC Guidelines for the Use of Tricaine Methanesulfonate (MS-222) in Fishes and Other Aquatic Animals MS-222 is used for anesthesia and euthanasia of fishes and other aquatic species. See widely between species and is affected by water temperature, hardness, and size of the individual fish

  1. New Catalytic DNA Biosensors for Radionuclides and Metal ions

    SciTech Connect (OSTI)

    Lu, Yi

    2005-06-01T23:59:59.000Z

    In vitro selection for DNAzymes that are catalytically active with UO22+ ions as the metal cofactor has been completed. The 10th generation pool of DNA was cloned and sequenced. A total of 84 clones were sequenced and placed into families based on sequence alignments. Selected members of each family were 5-labeled with 32P and amplified using PCR. Activity assays were conducted using the isotopically labeled DNAzymes in order to determine which sequences were the most active. The secondary structures of the two most active sequences, called Clone 13 and Clone 39, were determined using the computer program Mfold. A cleavage rate of approximately 1 min-1 in the presence of 10 uM UO22+ was observed for both clones. Clone 39 was determined to be the best candidate for truncation to create a trans-cleaving DNAzyme, based on its secondary structure. An enzyme strand, called 39E, and a substrate strand, called 39DS, were designed by truncating the cis-cleaving DNAzyme. An alternative enzyme strand, called 39Ec, was also assayed with the 39DS substrate. This strand was designed so that the two binding arms were perfectly complimentary, unlike 39E, which formed three mismatched base pairs with 39DS. Both 39E and 39Ec were found to be active, with a rate of approximately 1 min-1 in the presence of 10 uM UO22+. A preliminary UO22+ binding curve was obtained for the 39Ec/39DS trans-cleaving system. The enzyme is active with UO22+ concentrations as low as 1 nM. Based on the preliminary binding curve data, the apparent UO22+ binding constant is approximately 330 nM, and kmax is approximately 1 min-1.

  2. Source term evaluation for postulated UF{sub 6} release accidents in gaseous diffusion plants -- Summer ventilation mode (non-seismic cases)

    SciTech Connect (OSTI)

    Kim, S.H.; Chen, N.C.J.; Taleyarkhan, R.P.; Wendel, M.W.; Keith, K.D.; Schmidt, R.W. [Oak Ridge National Lab., TN (United States); Carter, J.C. [J.C. Carter Associates, Inc., Knoxville, TN (United States); Dyer, R.H. [Dyer Enterprises, Harriman, TN (United States)

    1996-12-30T23:59:59.000Z

    Computer models have been developed to simulate the transient behavior of aerosols and vapors as a result of a postulated accident involving the release of uranium hexafluoride (UF{sub 6}) into the process building of a gaseous diffusion plant. For the current study, gaseous UF{sub 6} is assumed to get released in the cell housing atmosphere through B-line break at 58.97 kg/s for 10 min and 30 min duration at the Paducah and Portsmouth Gaseous Diffusion Plants. The released UF{sub 6} undergoes an exothermic chemical reaction with moisture (H{sub 2}O) in the air to form hydrogen fluoride (HF) and radioactive uranyl fluoride (UO{sub 2}F{sub 2}) while it disperses throughout the process building. As part of a facility-wide safety evaluation, this study evaluated source terms consisting of UO{sub 2}F{sub 2} as well as HF during a postulated UF{sub 6} release accident in a process building. UO{sub 2}F{sub 2} mainly remains as airborne-solid particles (aerosols), and HF is in a vapor form. Some UO{sub 2}F{sub 2} aerosols are removed from the air flow due to gravitational settling. The HF and the remaining UO{sub 2}F{sub 2} are mixed with air and exhausted through the building ventilation system. The MELCOR computer code was selected for simulating aerosols and vapor transport in the process building. To characterize leakage flow through the cell housing wall, 3-D CFD tool (CFDS-FLOW3D) was used. About 57% of UO{sub 2}F{sub 2} was predicted to be released into the environment. Since HF was treated as vapor, close to 100% was estimated to get released into the environment.

  3. Greening academia: Developing sustainable waste management at Higher Education Institutions

    SciTech Connect (OSTI)

    Zhang, N. [School of Civil Engineering and the Environment, University of Southampton, University Rd., Highfield, Southampton, Hampshire SO17 1BJ (United Kingdom); Williams, I.D., E-mail: idw@soton.ac.uk [School of Civil Engineering and the Environment, University of Southampton, University Rd., Highfield, Southampton, Hampshire SO17 1BJ (United Kingdom); Kemp, S. [School of Civil Engineering and the Environment, University of Southampton, University Rd., Highfield, Southampton, Hampshire SO17 1BJ (United Kingdom); Smith, N.F. [Estates and Facilities Management, University of Southampton, University Rd., Highfield, Southampton, Hampshire SO17 1BJ (United Kingdom)

    2011-07-15T23:59:59.000Z

    Higher Education Institutions (HEIs) are often the size of small municipalities. Worldwide, the higher education (HE) sector has expanded phenomenally; for example, since the 1960s, the United Kingdom (UK) HE system has expanded sixfold to >2.4 million students. As a consequence, the overall production of waste at HEIs throughout the world is very large and presents significant challenges as the associated legislative, economic and environmental pressures can be difficult to control and manage. This paper critically reviews why sustainable waste management has become a key issue for the worldwide HE sector to address and describes some of the benefits, barriers, practical and logistical problems. As a practical illustration of some of the issues and problems, the four-phase waste management strategy developed over 15 years by one of the largest universities in Southern England - the University of Southampton (UoS) - is outlined as a case study. The UoS is committed to protecting the environment by developing practices that are safe, sustainable and environmentally friendly and has developed a practical, staged approach to manage waste in an increasingly sustainable fashion. At each stage, the approach taken to the development of infrastructure (I), service provision (S) and behavior change (B) is explained, taking into account the Political, Economic, Social, Technological, Legal and Environmental (PESTLE) factors. Signposts to lessons learned, good practice and useful resources that other institutions - both nationally and internationally - can access are provided. As a result of the strategy developed at the UoS, from 2004 to 2008 waste costs fell by around Pounds 125k and a recycling rate of 72% was achieved. The holistic approach taken - recognizing the PESTLE factors and the importance of a concerted ISB approach - provides a realistic, successful and practical example for other institutions wishing to effectively and sustainably manage their waste.

  4. Testing improved staggered fermions with $m_s$ and $B_K$

    E-Print Network [OSTI]

    Lee, W; Fleming, G T; Gupta, R; Kilcup, G; Sharpe, S R; Lee, Weonjong; Bhattacharya, Tanmoy; Fleming, George T.; Gupta, Rajan; Kilcup, Gregory; Sharpe, Stephen R.

    2004-01-01T23:59:59.000Z

    We study the improvement of staggered fermions using hypercubically smeared (HYP) links. We calculate the strange quark mass and the kaon B-parameter, $B_K$, in quenched QCD on a $16^3 \\times 64$ lattice at $\\beta=6.0$ ($1/a=1.95 GeV$). We find $m_s(\\bar{\\rm MS},2 {\\rm GeV})=101.2\\pm1.3\\pm4 $MeV and $B_K(\\bar{\\rm MS},2 {\\rm GeV}) = 0.580 \\pm 0.018\\pm 0.041$, where the first error is from statistics and fitting, and the second from using one-loop matching factors. Comparing to quenched results obtained using unimproved staggered fermions and other discretizations, we argue that the size of discretization errors are substantially reduced by improvement.

  5. Solid-phase chelation for the determination of trace elements by ICP-MS

    SciTech Connect (OSTI)

    Taylor, D.B.; Kingston, H.M.; Nogay, D. [Duquesne Univ., Pittsburgh, PA (United States)

    1995-12-31T23:59:59.000Z

    A low pressure method for the concentration of analytes and elimination of matrix elements prior to determination by ICP-MS is described. The method reduces the interferences caused by high concentrations of matrix elements in samples and biases caused by differences between samples and standards by delivering the analytes to the ICP-MS in a consistent nitric acid matrix. The method uses a commercially available low pressure sample manipulation system (PrepLab, Fisons) to perform Solid Phase Chelation (SPC) on an iminodiacetate column. The effectiveness of the method is demonstrated for the determination of Cd, Co, Cu, Mn, Ni, Pb, U, and Zn in the certified reference materials CASS-2, near shore seawater, NASS-4, open ocean seawater, and 1643b, trace elements in water. The detection limits for 10 mL samples ranged from 0.4 ng L{sup -1} for Co to 5.6 ng L{sup -1} for Ni and Zn.

  6. Improved DESI-MS Performance using Edge Sampling and aRotational Sample Stage

    SciTech Connect (OSTI)

    Kertesz, Vilmos [ORNL; Van Berkel, Gary J [ORNL

    2008-01-01T23:59:59.000Z

    The position of the surface to be analyzed relative to the sampling orifice or capillary into the mass spectrometer has been known to dramatically affect the observed signal levels in desorption electrospray ionization mass spectrometry (DESIMS). In analyses of sample spots on planar surfaces, DESI-MS signal intensities as much as five times greater were routinely observed when the bottom of the sampling capillary was appropriately positioned beneath the surface plane ( edge sampling") compared to when the capillary just touched the surface. To take advantage of the optimum "edge sampling" geometry and to maximize the number of samples that could be analyzed in this configuration, a rotational sample stage was integrated into a typical DESI-MS setup. The rapid quantitative determination of caffeine in two diet sport drinks (Diet Turbo Tea, Speed Stack Grape) spiked with an isotopically labeled internal standard demonstrated the utility of this approach.

  7. DECAY HEAT CONDITIONS OF CURRENT AND NEXT GENERATION REACTORS

    E-Print Network [OSTI]

    Choe, JongSoo 1985-

    2012-05-04T23:59:59.000Z

    expects to operate the VHTR by 2021 (NGNP, A Report to Congress, 2008). Advanced Burner 3 Reactors (ABR) are Sodium-Cooled Fast Reactors (SFR) which are fast neutron spectrum and closed fuel cycle system reactors. Its management of actinides... enriched uranium dioxide(UO2 ) less than 5 wt% and gadolinia-uranium dioxide(Gd,UO2). The cladding material is ZIRLO which is a zirconium based alloy for improved corrosion resistance (US-APWR, 2011). The operation power of the ABWR is 3926 MWth. Its...

  8. Congrs "Matriaux 2006", Colloque "Matrise des microstructures des matriaux", 13-17 nov. 2006, Dijon. Actes dits sur DVD, ISBN 978-2-9528-1400-3.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    France par une conversion en voie sèche d'UF6 gazeux. Le procédé comporte deux étapes : hydrolyse en UO2F combustible nucléaire peut être produite par le procédé de conversion en voie sèche d'UF6 gazeux. Ce procédé réalise successivement une hydrolyse de l'UF6 gazeux en poudre de difluorure d'uranyle UO2F2, puis une

  9. Preparation of thorium-uranium gel spheres

    SciTech Connect (OSTI)

    Spence, R.D.; Haas, P.A.

    1980-01-01T23:59:59.000Z

    Ceramic oxide spheres with diameters of 15 to 1500 ..mu..m are being evaluated for fabrication of power reactor fuel rods. (Th,U)O/sub 2/ spheres can be prepared by internal or external chemical gelation of nitrate solutions or oxide sols. Two established external gelation techniques were tested but proved to be unsatisfactory for the intended application. Established internal gelation techniques for UO/sub 2/ spheres were applied with minor modifications to make 75% ThO/sub 2/-25% UO/sub 2/ spheres that sinter to diameters of 200 to 1400 ..mu..m (99% T.D.).

  10. Effects of Time, Heat, and Oxygen on K Basin Sludge Agglomeration, Strength, and Solids Volume

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Daniel, Richard C.; Burns, Carolyn A.

    2011-01-04T23:59:59.000Z

    Sludge disposition will be managed in two phases under the K Basin Sludge Treatment Project. The first phase is to retrieve the sludge that currently resides in engineered containers in the K West (KW) Basin pool at ~10 to 18°C. The second phase is to retrieve the sludge from interim storage in the sludge transport and storage containers (STSCs) and treat and package it in preparation for eventual shipment to the Waste Isolation Pilot Plant. The work described in this report was conducted to gain insight into how sludge may change during long-term containerized storage in the STSCs. To accelerate potential physical and chemical changes, the tests were performed at temperatures and oxygen partial pressures significantly greater than those expected in the T Plant canyon cells where the STSCs will be stored. Tests were conducted to determine the effects of 50°C oxygenated water exposure on settled quiescent uraninite (UO2) slurry and a full simulant of KW containerized sludge to determine the effects of oxygen and heat on the composition and mechanical properties of sludge. Shear-strength measurements by vane rheometry also were conducted for UO2 slurry, mixtures of UO2 and metaschoepite (UO3•2H2O), and for simulated KW containerized sludge. The results from these tests and related previous tests are compared to determine whether the settled solids in the K Basin sludge materials change in volume because of oxidation of UO2 by dissolved atmospheric oxygen to form metaschoepite. The test results also are compared to determine if heating or other factors alter sludge volumes and to determine the effects of sludge composition and settling times on sludge shear strength. It has been estimated that the sludge volume will increase with time because of a uranium metal ? uraninite ? metaschoepite oxidation sequence. This increase could increase the number of containers required for storage and increase overall costs of sludge management activities. However, the volume might decrease because of decreases in the water-volume fraction caused by sludge solid reactions, compaction, or intergrowth and recrystallization of metaschoepite. In that case, fewer STSCs may be needed, but the shear strength would increase, and this could challenge recovery by water jet erosion and require more aggressive retrieval methods. Overall, the tests described herein indicate that the settled solids volume remains the same or decreases with time. The only case for which the sludge solids volumes increase with time is for the expansion factor attendant upon the anoxic corrosion of uranium metal to produce UO2 and subsequent reaction with oxygen to form equimolar UO2.25 and UO3•2H2O.

  11. Capacitance-based prover for gas flow meters

    E-Print Network [OSTI]

    Pipkins, Sean Patrick

    1995-01-01T23:59:59.000Z

    ;?= enthalpy of the air at the inlet. H Uo =U +RT Uo =Cv(T To)+RT, (36) 24 Equation (35) can be written as c (T-T)=[c (T?? T)+RT. , ?] Il ? ' n j (37) Solving Equation (37) for T gives the equation used to calculate the temperature profiles of the air.... . . . . Relation of Capacitance Change to Molar Flow Rate. DiIferential Method Integral Method THEORETICAL CALCULATIONS. Calculated C. Experimental C. Thermal Expansion Effects . . Capacitance Change Due to Length Change Capacitance Change Due to Radius...

  12. Evaluation of ultra-low background materials for uranium and thorium using ICP-MS

    SciTech Connect (OSTI)

    Hoppe, E. W.; Overman, N. R.; LaFerriere, B. D. [Pacific Northwest National Laboratory, Richland, WA 99354 (United States)] [Pacific Northwest National Laboratory, Richland, WA 99354 (United States)

    2013-08-08T23:59:59.000Z

    An increasing number of physics experiments require low background materials for their construction. The presence of Uranium and Thorium and their progeny in these materials present a variety of unwanted background sources for these experiments. The sensitivity of the experiments continues to drive the necessary levels of detection ever lower as well. This requirement for greater sensitivity has rendered direct radioassay impractical in many cases requiring large quantities of material, frequently many kilograms, and prolonged counting times, often months. Other assay techniques have been employed such as Neutron Activation Analysis but this requires access to expensive facilities and instrumentation and can be further complicated and delayed by the formation of unwanted radionuclides. Inductively Coupled Plasma Mass Spectrometry (ICP-MS) is a useful tool and recent advancements have increased the sensitivity particularly in the elemental high mass range of U and Th. Unlike direct radioassay, ICP-MS is a destructive technique since it requires the sample to be in liquid form which is aspirated into a high temperature plasma. But it benefits in that it usually requires a very small sample, typically about a gram. This paper discusses how a variety of low background materials such as copper, polymers, and fused silica are made amenable to ICP-MS assay and how the arduous task of maintaining low backgrounds of U and Th is achieved.

  13. Evaluation of Ultra-Low Background Materials for Uranium and Thorium Using ICP-MS

    SciTech Connect (OSTI)

    Hoppe, Eric W.; Overman, Nicole R.; LaFerriere, Brian D.

    2013-08-08T23:59:59.000Z

    An increasing number of physics experiments require low background materials for their construction. The presence of Uranium and Thorium and their progeny in these materials present a variety of unwanted background sources for these experiments. The sensitivity of the experiments continues to drive the necessary levels of detection ever lower as well. This requirement for greater sensitivity has rendered direct radioassay impractical in many cases requiring large quantities of material, frequently many kilograms, and prolonged counting times, often months. Other assay techniques have been employed such as Neutron Activation Analysis but this requires access to expensive facilities and instrumentation and can be further complicated and delayed by the formation of unwanted radionuclides. Inductively Coupled Plasma Mass Spectrometry (ICP-MS) is a useful tool and recent advancements have increased the sensitivity particularly in the elemental high mass range of U and Th. Unlike direct radioassay, ICP-MS is a destructive technique since it requires the sample to be in liquid form which is aspirated into a high temperature plasma. But it benefits in that it usually requires a very small sample, typically about a gram. Here we will discuss how a variety of low background materials such as copper, polymers, and fused silica are made amenable to ICP-MS assay and how the arduous task of maintaining low backgrounds of U and Th is achieved.

  14. Sources of Technical Variability in Quantitative LC-MS Proteomics: Human Brain Tissue Sample Analysis.

    SciTech Connect (OSTI)

    Piehowski, Paul D.; Petyuk, Vladislav A.; Orton, Daniel J.; Xie, Fang; Moore, Ronald J.; Ramirez Restrepo, Manuel; Engel, Anzhelika; Lieberman, Andrew P.; Albin, Roger L.; Camp, David G.; Smith, Richard D.; Myers, Amanda J.

    2013-05-03T23:59:59.000Z

    To design a robust quantitative proteomics study, an understanding of both the inherent heterogeneity of the biological samples being studied as well as the technical variability of the proteomics methods and platform is needed. Additionally, accurately identifying the technical steps associated with the largest variability would provide valuable information for the improvement and design of future processing pipelines. We present an experimental strategy that allows for a detailed examination of the variability of the quantitative LC-MS proteomics measurements. By replicating analyses at different stages of processing, various technical components can be estimated and their individual contribution to technical variability can be dissected. This design can be easily adapted to other quantitative proteomics pipelines. Herein, we applied this methodology to our label-free workflow for the processing of human brain tissue. For this application, the pipeline was divided into four critical components: Tissue dissection and homogenization (extraction), protein denaturation followed by trypsin digestion and SPE clean-up (digestion), short-term run-to-run instrumental response fluctuation (instrumental variance), and long-term drift of the quantitative response of the LC-MS/MS platform over the 2 week period of continuous analysis (instrumental stability). From this analysis, we found the following contributions to variability: extraction (72%) >> instrumental variance (16%) > instrumental stability (8.4%) > digestion (3.1%). Furthermore, the stability of the platform and its’ suitability for discovery proteomics studies is demonstrated.

  15. Performance characteristics of cryofocusing GC/MS system at BWXT Pantex Plant.

    SciTech Connect (OSTI)

    Brown, Jason R.; Banet, Judith F.; Ithaca, Jerry (BWXT Pantex Plant, Amarillo, TX); Thornberg, Steven Michael; Woods, Lorelei (BWXT Pantex Plant, Amarillo, TX)

    2006-07-01T23:59:59.000Z

    Ensuring the reliability of all components within a weapon system becomes increasingly important as the stockpile ages. One of the most noteworthy surveillance techniques designed to circumvent (or take place alongside) traditional D&I operations is to collect a sample of gas from within the internal atmosphere of a particular region in a weapon. While a wealth of information about the weapon may be encoded within the composition of its gas sample, our access to that information is only as good as the method used to analyze the sample. It has been shown that cryofocusing-GC/MS offers advantages in terms of sensitivity, ease of sample collection, and robustness of the equipment/hardware used. Attention is therefore focused on qualifying a cryo-GC/MS system for routine stockpile surveillance operations at Pantex. A series of tests were performed on this instrument to characterize the linearity and repeatability of its response using two different standard gas mixes (ozone precursor and TO-14) at various concentrations. This paper outlines the methods used and the results of these tests in order to establish a baseline by which to compare future cryo-GC/MS analyses. A summary of the results is shown.

  16. The West Virginia University College of Engineering and Mineral Resources has seven academic departments with undergraduate and graduate (M.S. and Ph.D.)

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    ............................. MSE · Industrial Engineering ............. BS / MS / PhD · Industrial Hygiene.................... MS.S. programs in Industrial Hygiene and Safety Management are ABET accredited. Biometrics is a unique departments with undergraduate and graduate (M.S. and Ph.D.) degree programs and the Mining and Industrial

  17. SUMMARY OF PROPOSED AMENDMENT TO REGULATION FSU-2.024, TUITION AND FEES; MS-NURSE ANESTHESIA PROGRAM; MD TUITION

    E-Print Network [OSTI]

    Weston, Ken

    SUMMARY OF PROPOSED AMENDMENT TO REGULATION FSU-2.024, TUITION AND FEES; MS-NURSE ANESTHESIA for a new Master of Science in Nurse Anesthesia program at the Panama City Florida Campus. The new program

  18. Combined thermogravimetric and mass spectroscopic analysis (TG/MS). Quarterly report, April 1, 1995--June 30, 1995

    SciTech Connect (OSTI)

    Kopp, O.C.

    1995-09-01T23:59:59.000Z

    Progress is reported on the analysis of coals using thermogravimetric (TG) and mass spectrographic (MS) analysis and adding information to the database. Samples were analyzed using oxidative pyrolysis. Various types (coal rank) of coal were utilized.

  19. M.S. Economic Geology, Oregon State University College of Earth, Ocean, and Atmospheric Sciences, Corvallis, OR Expected Spring, 2015

    E-Print Network [OSTI]

    Kurapov, Alexander

    EDUCATION M.S. Economic Geology, Oregon State University College of Earth, Ocean. Dilles Relevant Courses Interpretation of Geologic Maps Igneous Petrology Tectonic Geomorphology B.S. Geology, University of Idaho College of Science, Moscow, ID; GPA: 3

  20. Proteome Profiling for Assessing Diversity: Analysis of Individual Heads of Drosophila melanogaster Using LC-Ion Mobility-MS

    E-Print Network [OSTI]

    Clemmer, David E.

    Proteome Profiling for Assessing Diversity: Analysis of Individual Heads of Drosophila melanogaster dimensions of condensed-phase separations with mass spec- trometry (MS).4 In this approach, mass-to-charge (m-speed, gas-phase sep

  1. A Novel Self-Calibration Scheme for 12-bit 50MS/s In-Seok Jung

    E-Print Network [OSTI]

    Ayers, Joseph

    A Novel Self-Calibration Scheme for 12-bit 50MS/s SAR ADC In-Seok Jung Department of Electrical@ece.neu.edu Abstract-- This paper presents a low-power 12-bit 50MS/s suc- cessive approximation register (SAR) analog-to-digital converter (ADC) using single input condition for Built-In Self Test (BIST) that uses a novel self-calibration

  2. Market Research Survey of Commercial Off-The-Shelf (COTS) Portable MS Systems for IAEA Safeguards Applications

    SciTech Connect (OSTI)

    Hart, Garret L.; Hager, George J.; Barinaga, Charles J.; Duckworth, Douglas C.

    2013-02-01T23:59:59.000Z

    This report summarizes the results for the market research survey of mass spectrometers that are deemed pertinent to International Atomic Energy Agency (IAEA) needs and strategic objectives. The focus of the report is on MS instruments that represent currently available (or soon to be) commercial off-the shelf (COTS) technology and weigh less than 400 pounds. A compilation of all available MS instruments (36 COTS and 2 R&D) is presented, along with pertinent information regarding each instrument.

  3. 22c-MS&PMS-III AGB Thermal Pulsing and Dredge-ups

    E-Print Network [OSTI]

    Sitko, Michael L.

    22c-MS&PMS-III DREDGE-UP AGB Thermal Pulsing and Dredge-ups Pre-AGB Dredge-ups 1st ­ on the RGB;Pre-Dredge-up C:N:O ~ 1 2 : 1 6 :1 After 1st C:N:O~ 1 3 : 1 3 :1 After 2nd C:N:O~0 to the surface. This is the 3rd Dredge-up phase that can bring C-rich material to the surface, changing the star

  4. 25c-MS&PMS-III AGB Thermal Pulsing and Dredge-ups

    E-Print Network [OSTI]

    Sitko, Michael L.

    25c-MS&PMS-III DREDGE-UP AGB Thermal Pulsing and Dredge-ups Pre-AGB Dredge-ups 1st ­ on the RGB;Pre-Dredge-up C:N:O ~ 1 2 : 1 6 :1 After 1 st C:N:O~ 1 3 : 1 3 :1 After 2 nd C:N:O~0. This is the 3rd Dredge-up phase that can bring C-rich material to the surface, changing the star from an M

  5. Toward Joint Hypothesis-Tests Seismic Event Screening Analysis: Ms|mb and Event Depth

    SciTech Connect (OSTI)

    Anderson, Dale [Los Alamos National Laboratory; Selby, Neil [AWE Blacknest

    2012-08-14T23:59:59.000Z

    Well established theory can be used to combine single-phenomenology hypothesis tests into a multi-phenomenology event screening hypothesis test (Fisher's and Tippett's tests). Commonly used standard error in Ms:mb event screening hypothesis test is not fully consistent with physical basis. Improved standard error - Better agreement with physical basis, and correctly partitions error to include Model Error as a component of variance, correctly reduces station noise variance through network averaging. For 2009 DPRK test - Commonly used standard error 'rejects' H0 even with better scaling slope ({beta} = 1, Selby et al.), improved standard error 'fails to rejects' H0.

  6. Ms Linda Cerrone | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurTheBrookhaven National LaboratoryJeffreyMs. Linda Cerrone Scientific User

  7. Ms Van T Nguyen | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurTheBrookhaven National LaboratoryJeffreyMs. Linda Cerrone Scientific

  8. Ms. Chris Andres, Chief Bureau of Federal Facilities Division of Environmental Protection

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTuba City, Arizona, DisposalFourth Five-Year38Report3DepartmentE-23TimMs.

  9. Detailed lensing properties of the MS2137-2353 core and reconstruction of sources

    E-Print Network [OSTI]

    Hammer, F; Shaya, E J; Gioia, I M; Luppino, G A; Lefèvre, O

    1996-01-01T23:59:59.000Z

    A deep HST image of the MS 2137-2353 core has revealed detailed morphological structures in two arc systems, which are modelled and well reproduced after a complete analysis of the lensing properties of the dark matter component. Latter could have a simple elliptical mass distribution with ellipticity and angular orientation similar to those of the visible and X-ray light, which suggests that the MS 2137-2353 is a relaxed cluster at z=0.313. The predicted density profile ($\\rho$ $\\sim$ $r^{-1.56\\pm0.1}$ with $r_{c}$ $\\le$ 22.5$h_{50}^{-1}$ kpc) within 150$h_{50}^{-1}$ kpc implies increasing M/L ratio with the radius, and could be in agreement with predictions from standard CDM simulations. At least two faint sources (unlensed magnitude, R=23.9 and 26, respectively) are aligned with the cluster core and are responsible of the arc systems. They have been reconstructed with details as small as 0".02 (or 160$h_{50}^{-1}$ pc in the source assumed at z= 1), one could be a nearly edge-on barred spiral galaxy, and th...

  10. Characterization of CMPO and its radiolysis products by Direct Infusion ESI-MS

    SciTech Connect (OSTI)

    G. S. Groenewold; G. Elias; B. J. Mincher; S. P. Mezyk

    2012-09-01T23:59:59.000Z

    Direct infusion electrospray ionization-mass spectrometry (ESI-MS) approaches were developed for rapid identification of octyl,phenyl,(N,N-(diisobutyl)carbamoylmethyl) phosphine oxide (CMPO) and impurity compounds formed during alpha and gamma irradiation experiments. CMPO is an aggressive Lewis base, and produces extremely abundant metal complex ions in the ESI-MS analysis that make identification of low abundance compounds that are less nucleophilic challenging. Radiolysis products were identified using several approaches including restricting ion trapping so as to exclude the abundant natiated CMPO ions, extraction of acidic products using aqueous NaOH, and extraction of basic products using HNO3. These approaches generated protonated, natiated and deprotonated species derived from CMPO degradation products formed via radiolytic cleavages of several different bonds. Cleavages of the amide and methylene-phosphoryl bonds appear to be favored by both forms of irradiation, while alpha irradiation also appears to induce cleavage of the methylene-carbonyl bond. The degradation products observed are formed from recombination of the initially formed radicals with hydrogen, methyl, isopropyl and hydroxyl radicals that are derived either from CMPO, or the dodecane solvent.

  11. Separation of Yeast Cells from MS2 Viruses Using Acoustic Radiation Force

    SciTech Connect (OSTI)

    Jung, B; Fisher, K; Ness, K; Rose, K A; Mariella, Jr., R P

    2008-03-27T23:59:59.000Z

    We report a rapid and robust separation of Saccharomyces cerevisiae and MS2 bacteriophage using acoustic focusing in a microfluidic device. A piezoelectric transducer (PZT) generates acoustic standing waves in the microchannel. These standing waves induce acoustic radiation force fields that direct microparticles towards the nodes (i.e., pressure minima) or the anti-nodes (i.e., pressure maxima) of the standing waves depending on the relative compressidensity between the particle and the suspending liquid.[1] For particles larger than 2 {micro}m, the transverse velocities generated by these force fields enable continuous, high throughput separation. Extensive work in the last decade [2-4] has demonstrated acoustic focusing for manipulating microparticles or biological samples in microfluidic devices. This prior work has primarily focused on experimental realization of acoustic focusing without modeling or with limited one-dimensional modeling estimates. We recently developed a finite element modeling tool to predict the two-dimensional acoustic radiation force field perpendicular to the flow direction in microfluidic devices.[1] Here we compare results from this model with experimental parametric studies including variations of the PZT driving frequencies and voltages as well as various particle sizes and compressidensities. These experimental parametric studies also provide insight into the development of an adjustable 'virtual' pore-size filter as well as optimal operating conditions for various microparticle sizes. Figure 1 shows a typical experimental acoustic focusing result for microparticles (diameter = 2.0 {micro}m) in a 500 {micro}m wide by 200 {micro}m deep microchannel. In this case, the PZT driving frequency and voltage are, respectively, 1.459 MHz and 6.6 V. The microparticles tightly focus (full width half maximum (FWHM) {approx}30 {micro}m) less than 30 s after the initiation of the acoustic field. We simulated the same geometry and operating conditions for comparison. The surface plot in Figure 2 illustrates the two-dimensional pressure field orthogonal to the flow direction (x-direction) from the simulation. The superimposed vector plot shows the acoustic radiation force in this plane. The dark regions and the light regions respectively represent the nodes and anti-nodes of the acoustic pressure field. The corresponding force field predicts acoustic focusing at the center of the microchannel, which is confirmed by the experimental results shown in Figure 1. We demonstrated the separation of Saccharomyces cerevisiae (typical cell size of 4-6 {micro}m depending on the cell growth stage, measured using a Coulter counter) and MS2 bacteriophage (typical diameter {approx}30 nm [5]) using acoustic focusing (Figure 3). A mixture of S. cerevisiae and MS2 labeled with Ribogreen was prepared and injected into one inlet of the microchip (i.e., half of the microchannel was filled with the sample). We varied driving voltages from 1.96 to 4.76 V, while fixing the driving frequency at 1.459 MHz and flow rate at 20 {micro}l/min. The acoustic radiation force did not affect the MS2 viruses, and their concentration profile remained unchanged. Increased driving voltages enhanced the acoustic focusing of the yeast cells thereby achieving good separation. We are able to achieve yields of > 80% and sample purities of > 90% in this continuous-flow sample preparation device.

  12. Mass Spectrometry Data from the Biological MS Data and Software Distribution Center

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Anderson, Gordon

    The mass spectrometry capabilities at Pacific Northwest National Laboratory (PNNL) are primarily applied to biological research, with an emphasis on proteomics and metabolomics. Many of these cutting-edge mass spectrometry capabilities and bioinformatics methods are housed in the Department of Energy's Environmental Molecular Sciences Laboratory (EMSL), a national scientific user facility operated by PNNL. These capabilities have been developed and acquired through cooperation between the EMSL national scientific user program and PNNL programmatic research. At the website of the Biological MS Data and Software Distribution Center, the following resources are made available: PNNL-developed software tools and source code, PNNL-generated raw data and processed results, links to publications that used the data and results available on this site, and tutorials and user manuals. [taken from http://omics.pnl.gov/

  13. Studies on the content of heavy metals in Aries River using ICP-MS

    SciTech Connect (OSTI)

    Voica, Cezara, E-mail: Cezara.Voica@itim-cj.ro; Kovacs, Melinda, E-mail: Cezara.Voica@itim-cj.ro; Feher, Ioana, E-mail: Cezara.Voica@itim-cj.ro [National Institute for Research and Development of Isotopic and Molecular Technologies, 65-103 Donath Str., 400293 Cluj-Napoca (Romania)] [National Institute for Research and Development of Isotopic and Molecular Technologies, 65-103 Donath Str., 400293 Cluj-Napoca (Romania)

    2013-11-13T23:59:59.000Z

    Among the industrial branches, the mining industry has always been an important source of environmental pollution, both aesthetically and chemically. Through this paper results of ICP-MS characterization of Aries River Basin are reported. Mining activities from this area has resulted in contamination of environment and its surrounding biota. This is clearly evidenced in analyzed water samples, especially from Baia de Aries site where increased amount of trace elements as Cr, Zn, As, Se, Cd, Pb and U were founded. Also in this site greater amount of rare earth elements was evidenced also. Through monitoring of Aries River from other non-mining area it was observed that the quantitative content of heavy metals was below the maximum permissible levels which made us to conclude that the water table wasn't seriously affected (which possibly might be attributed to the cessation of mining activities in this area from a few years ago)

  14. Top-Down Mass Spectrometry Imaging of Intact Proteins by LAESI FT-ICR MS

    E-Print Network [OSTI]

    Kiss, András; Reschke, Brent R; Powell, Matthew J; Heeren, Ron M A

    2013-01-01T23:59:59.000Z

    Laser Ablation Electrospray Ionization is a recent development in mass spectrometry imaging. It has been shown that lipids and small metabolites can be imaged in various samples such as plant material, tissue sections or bacterial colonies without anysample pre-treatment. Further, laser ablation electrospray ionization has been shown to produce multiply charged protein ions from liquids or solid surfaces. This presents a means to address one of the biggest challenges in mass spectrometry imaging; the identification of proteins directly from biological tissue surfaces. Such identification is hindered by the lack of multiply charged proteins in common MALDI ion sources and the difficulty of performing tandem MS on such large, singly charged ions. We present here top-down identification of intact proteins from tissue with a LAESI ion source combined with a hybrid ion-trap FT-ICR mass spectrometer. The performance of the system was first tested with a standard protein with ECD and IRMPD fragmentation to prove the...

  15. A New Weak Lensing Analysis of MS1224.7+2007

    E-Print Network [OSTI]

    Philippe Fischer

    1999-01-29T23:59:59.000Z

    Galaxy cluster mass distributions are useful probes of Omega_0 and the nature of the dark matter. Large clusters will distort the observed shapes of background galaxies through gravitational lensing allowing the measurement of the cluster mass distributions. For most cases, the agreement between weak lensing and radial velocity mass measurements of clusters is reasonably good. There is, however, one significant exception, the z=0.32 cluster MS1224.7+2007, which has a lensing mass substantially larger than the virial mass and also a very high mass-to-light ratio. Since this controversial object might be an unusually dark mass a follow-up study is definitely warranted. In this paper we study the mass and light distributions of MS1224+2007 out to a projected radius of 800/h kpc by measuring the gravitationally-induced distortions of background galaxies. We detect a shear signal in the background galaxies in the radial range 27.5 arcsec < r < 275 arcsec at the 5.5 sigma level. The resultant mass map exhibits a peak centered on the dominant cluster galaxy and strong evidence for substructure which is even more strongly seen in the galaxy distribution. Assuming all the detected shear is due to mass at z=0.32 we find cluster mass-to-light ratio of M/L_R = 640 +/- 150. The mass profile is quite flat compared to other clusters, disagreeing with a pseudo-singular isothermal sphere at the 95% confidence level. Our mass and M/L estimates are consistent with the previous weak lensing result. The discrepancy between the lensing and virial mass remains although it might be partially explained by subclustering and infall perpendicular to the line-of-site. This cluster remains a candidate dark object deficient in baryons and as such severely tests cosmological models.

  16. Groundwater Chemistry Changes as a Result of CO2 Injection at the ZERT Field Site in Bozeman, Montana

    E-Print Network [OSTI]

    Apps, J.A.

    2010-01-01T23:59:59.000Z

    Co +2 Cu + Cd +2 PbSe CrO + AsSe(OH)(SeH) - FeSe MoO 4-2 UOCo +2 Cu + Cd +2 PbSe CrO + AsSe(OH)(SeH) - FeSe MoO 4-2 UO

  17. Nagoya University Description

    E-Print Network [OSTI]

    Bristol, University of

    is a friendly, bustling industrial port city, and is the site of Toyota HQ (whose plant you can visit to watch their amazing robot workforce). Don't miss the festivals at Atsuta-jing, one of the most important Shinto for a JASSO Scholarship. Apply Once you have completed the UoB online application and been allocated a space

  18. Structural similarities between biogenic uraninites produced by phylogenetically and metabolically diverse bacteria.

    SciTech Connect (OSTI)

    Sharp, Jonathan; Schofield, Eleanor J.; Veeramani, Harish; Suvorova, Elena; Kennedy, David W.; Marshall, Matthew J.; Mehta, Apurva; Bargar, John R.; Bernier-Latmani, Rizlan

    2009-11-01T23:59:59.000Z

    While the product of microbial uranium reduction is often reported to be“UO2”, a comprehensive characterization including stoichiometry and unit cell determination is available for only one Shewanella species. Here, we compare the products of batch uranyl reduction by a collection of dissimilatory metal- and sulfate-reducing bacteria of the genera Shewanella, Geobacter, Anaeromyxobacter, and Desulfovibrio under similar laboratory conditions. Our results demonstrate that U(VI) bioreduction by this assortment of commonly studied, environmentally relevant bacteria leads to the precipitation of uraninite with a composition between UO2.00 and UO2.075, regardless of phylogenetic or metabolic diversity. Coupled analyses, including electron microscopy, X-ray absorption spectroscopy, and powder diffraction, confirm that structurally and chemically analogous uraninite solids are produced. These biogenic uraninites have particle diameters of about 2-3 nm and lattice constants consistent with UO2.0 and exhibit a high degree of intermediate-range order. Results indicate that phylogenetic and metabolic variability within delta- and gamma-proteobacteria has little effect on nascent biouraninite structure or crystal size under the investigated conditions.

  19. Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties

    E-Print Network [OSTI]

    Cuvelier, Marie-Hermine

    2012-07-16T23:59:59.000Z

    evaluations are indeed intensively used in reactors' calculations. Discrepancies higher than 10% have been computed among nuclear data libraries for energies above 8MeV for 235U. TRU arising from a 3wt% 235U-enriched UO2-fueled AP1000 were incinerated in a...

  20. Preparation and Characterization of Uranium Oxides in Support of the K Basin Sludge Treatment Project

    SciTech Connect (OSTI)

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

    2008-07-08T23:59:59.000Z

    Uraninite (UO2) and metaschoepite (UO3·2H2O) are the uranium phases most frequently observed in K Basin sludge. Uraninite arises from the oxidation of uranium metal by anoxic water and metaschoepite arises from oxidation of uraninite by atmospheric or radiolytic oxygen. Studies of the oxidation of uraninite by oxygen to form metaschoepite were performed at 21°C and 50°C. A uranium oxide oxidation state characterization method based on spectrophotometry of the solution formed by dissolving aqueous slurries in phosphoric acid was developed to follow the extent of reaction. This method may be applied to determine uranium oxide oxidation state distribution in K Basin sludge. The uraninite produced by anoxic corrosion of uranium metal has exceedingly fine particle size (6 nm diameter), forms agglomerates, and has the formula UO2.004±0.007; i.e., is practically stoichiometric UO2. The metaschoepite particles are flatter and wider when prepared at 21°C than the particles prepared at 50°C. These particles are much smaller than the metaschoepite observed in prolonged exposure of actual K Basin sludge to warm moist oxidizing conditions. The uraninite produced by anoxic uranium metal corrosion and the metaschoepite produced by reaction of uraninite aqueous slurries with oxygen may be used in engineering and process development testing. A rapid alternative method to determine uranium metal concentrations in sludge also was identified.

  1. Analysis of a proposed fuel freezing mechanism in a rod bundle 

    E-Print Network [OSTI]

    Nguyen-Wayne, David Loc

    1983-01-01T23:59:59.000Z

    void thermite fuel simulant (80 w/o UO2, 20 w/o Mo at about 3470 K, approximately 330 K superheat) and stainless steel walls. The main system variables in these tests were the initial wall temperatures and the fuel downward injection pressures...

  2. Quantifying submarine groundwater discharge in the coastal zone via multiple methods

    E-Print Network [OSTI]

    South Florida Water Management District, USA i University of Western Australia, Australia j Department, Tallahassee, FL 32306, USA b Isotope Hydrology Section, International Atomic Energy Agency, Austria c, Turkey n Marine Environment Laboratory, International Atomic Energy Agency, Monaco o U.O. 4.17 of the G

  3. HMSC Sustainability Committee Meeting Minutes: January 13, 2009

    E-Print Network [OSTI]

    for Sustainability Committee Oregon Climate Dialog/ National Teach-in Recycle Mania Earth Tub Industrial audit about tax and energy rebates and home energy conservation. Actions: Devin will get a blurb from. Devin concluded that UO and OSU both had excellent websites, and that the University of Pennsylvania

  4. LCLS USERS' ORGANIZATION CHARTER AND BY-LAWS A. Terms and definitions

    E-Print Network [OSTI]

    Wechsler, Risa H.

    LCLS USERS' ORGANIZATION CHARTER AND BY-LAWS A. Terms and definitions Several definitions and acronyms used in this document are defined below LCLS Linac Coherent Light Source LCLS/UO LCLS Users' Organization LCLS/UOEC LCLS Users' Organization Executive Committee SLAC Stanford Linear Accelerator Center

  5. IAEA-TECDOC-1450 Thorium fuel cycle --Potential

    E-Print Network [OSTI]

    Laughlin, Robert B.

    in liquid metal cooled fast breeder reactor (LMFBR) and for neutron flux flattening of the initial core neutron reactor has been recognized. Several experimental and prototype power reactors were successfully operated during the mid 1950s to the mid 1970s using (Th, U)O2 and (Th, U)C2 fuels in high temperature gas

  6. Rational Ligand Design for U(VI) and Pu(IV)

    E-Print Network [OSTI]

    Szigethy, Geza

    2010-01-01T23:59:59.000Z

    Murali, M. S. ; Nash, K. L. Solv. Extr. Ion Exch. 2001, 19,D. C. ; Raymond, K. N. Solv. Extr. Ion Exch. 2004, 22, (22)DMF) and UO 2 (bis-Me-3,2-HOPO)(solv) tabulated in Table 2-

  7. Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01

    E-Print Network [OSTI]

    McDermott, Patrick 1987-

    2012-11-15T23:59:59.000Z

    and blanket unit (SBU) configuration, where the seed region contains standard UO2 fuel, and the blanket region contains an inert matrix (Pu,Np,Am)O2-MgO-ZrO2 fuel. The research efforts of this thesis are first to consider the higher burnup effects on DUPLEX...

  8. Thermodynamics of fission products in dispersion fuel designs - first principles modeling of defect behavior in bulk and at interfaces

    SciTech Connect (OSTI)

    Liu, Xiang-yand [Los Alamos National Laboratory; Uberuaga, Blas P [Los Alamos National Laboratory; Nerikar, Pankaj [Los Alamos National Laboratory; Sickafus, Kurt E [Los Alamos National Laboratory; Stanek, Chris R [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    Density functional theory (DFT) calculations of fission product (Xe, Sr, and Cs) incorporation and segregation in alkaline earth metal oxides, HfO{sub 2} and UO{sub 2} oxides, and the MgO/(U, Hf, Ce)O{sub 2} interfaces have been carried out. In the case of UO{sub 2}, the calculations were performed using spin polarization and with a Hubbard U term characterizing the on-sit Coulomb repulsion between the localized 5f electrons. The fission product solution energies in bulk UO{sub 2{+-}x} have been calculated as a function of non-stoichiometry x, and were compared to that in MgO. These calculations demonstrate that the fission product incorporation energies in MgO are higher than in HfO{sub 2}. However, this trend is reversed or reduced for alkaline earth oxides with larger cation sizes. The solution energies of fission products in MgO are substantially higher than in UO{sub 2{+-}x}, except for the case of Sr in the hypostoichiometric case. Due to size effects, the thermodynamic driving force of segregation for Xe and Cs from bulk MgO to the MgO/fluorite interface is strong. However, this driving force is relatively weak for Sr.

  9. Modeling the performance of high burnup thoria and urania PWR fuel

    E-Print Network [OSTI]

    Long, Yun, 1972-

    2002-01-01T23:59:59.000Z

    Fuel performance models have been developed to assess the performance of ThO?-UO? fuels that can be operated to a high burnup up to 80-100MWd/kgHM in current and future Light Water Reactors (LWRs). Among the various issues ...

  10. Latest Neoproterozoic to Mid-Cambrian age for the main deformation phases of the Transantarctic Mountains: new stratigraphic and isotopic constraints from the Pensacola Mountains, Antarctica

    E-Print Network [OSTI]

    Rowell, A. J.; Van Schmus, W. R.; Storey, B. C.; Fetter, A. H.; Evans, K. R.

    2001-03-01T23:59:59.000Z

    and monitored by analysis of NBS SRM-983 radiogenic Pb. Uranium was loaded on the same filament with the Pb and analysed as UO 2 + ; uranium fractionation was monitored using NBS SRM U-500. Uncertainties in U/Pb ratios due to uncertainties in fractionation...

  11. Complexation of the uranyl ion with the aminomethylenediphosphonates MAMDP and AMDP

    SciTech Connect (OSTI)

    Bollinger, J.E.; Roundhill, D.M. [Tulane Univ., New Orleans, LA (United States)

    1994-12-21T23:59:59.000Z

    The use of uranium as a nuclear energy source has made it a valuable mineral resource over the past forty years. Processing uranium generally involves leaching the metal as the uranyl ion (UO{sub 2}){sup 2+} from ore, followed by solvent extraction, precipitation or batch adsorption onto ion exchange-type resins. Uranium reserves exist also in the form of UO{sub 2}(CO{sub 3}){sub 3}{sup 4{minus}} dissolved in seawater, and although these concentrations are very low they represent globally some 4.9 x 10{sup 9} tons. In the interest of tapping this resource efforts toward developing more efficient and selective means of UO{sub 2}{sup 2+} ion sequestering have been underway for some time. The authors have measured the stability and protonation constants of the different complexes formed in aqueous solution between the UO{sub 2}{sup 2+} ion and the compounds N,N{prime}-dimethylaminomethylenebis(phosphonic acid) (MAMDP) and aminomethylenebis(phosphonic acid) (AMDP). From these data one can evaluate the potential for compounds of this type to be useful as uranyl ion sequestering agents.

  12. Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code 

    E-Print Network [OSTI]

    Bellanger, Philippe

    1999-01-01T23:59:59.000Z

    The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited...

  13. The Power of Mesoscale Modeling... Mul$physics mesoscale simula$on provides a powerful tool for designing materials to

    E-Print Network [OSTI]

    Chen, Long-Qing

    , neutronics, geomechanics, reac+ve transport, microstructure modeling, computa+onal fluid in verba+m from Schwen, D., E. Mar/nez, and A. Caro, J. Nuclear Mater (cv) in UO2 fuel. Also shown are the switching func+on h, the order

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

    E-Print Network [OSTI]

    Fayek, Mostafa

    of Nuclear Engineering and Radiological Sciences, The University of Michigan, 2958A Cooley Building, 2355­30 Am, thus providing relatively accurate information regarding the timing of fluid interactions of migration of uranium and other radionuclides from a spent fuel repository because uraninite, UO2 + x (the

  15. Effective flow surface of porous materials with two populations of voids under internal pressure: I. a GTN model

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ). Such a microstructure is typical of the highly irradiated uranium dioxide (UO2), a nuclear fuel commonly used in nuclear several studies on the mechanical behavior of highly irradiated nuclear fuels at different scales (Vincent to the effective plastic flow surface of a bi-porous material saturated by a fluid. The material under

  16. Radiative heat transfer in porous uranium dioxide

    SciTech Connect (OSTI)

    Hayes, S.L. [Texas A and M Univ., College Station, TX (United States)] [Texas A and M Univ., College Station, TX (United States)

    1992-12-01T23:59:59.000Z

    Due to low thermal conductivity and high emissivity of UO{sub 2}, it has been suggested that radiative heat transfer may play a significant role in heat transfer through pores of UO{sub 2} fuel. This possibility was computationally investigated and contribution of radiative heat transfer within pores to overall heat transport in porous UO{sub 2} quantified. A repeating unit cell was developed to model approximately a porous UO{sub 2} fuel system, and the heat transfer through unit cells representing a wide variety of fuel conditions was calculated using a finite element computer program. Conduction through solid fuel matrix as wekk as pore gas, and radiative exchange at pore surface was incorporated. A variety of pore compositions were investigated: porosity, pore size, shape and orientation, temperature, and temperature gradient. Calculations were made in which pore surface radiation was both modeled and neglected. The difference between yielding the integral contribution of radiative heat transfer mechanism to overall heat transport. Results indicate that radiative component of heat transfer within pores is small for conditions representative of light water reactor fuel, typically less than 1% of total heat transport. It is much larger, however, for conditions present in liquid metal fast breeder reactor fuel; during restructuring of this fuel type early in life, the radiative heat transfer mode was shown to contribute as much as 10-20% of total heat transport in hottest regions of fuel.

  17. For the Meyer Fund for Sustainable Development and the University of Oregon Department of Physics and the Solar Radiation Monitoring Laboratory

    E-Print Network [OSTI]

    Oregon, University of

    and the Solar Radiation Monitoring LaboratoryG:SourcesforBackgroundInformation© Useful Web Sites: UO Solar Radiation Monitoring Laboratory Website: http://solardata.uoregon.edu/Educational Solar Radiation Basics Solar Electric Lesson Plans o What is a KiloWatt Hour? o Experiments

  18. VII. SOLAR RADIATION DATA COMPARISONS In this section some of the solar radiation data

    E-Print Network [OSTI]

    Oregon, University of

    18 VII. SOLAR RADIATION DATA COMPARISONS In this section some of the solar radiation data gathered by the UO Solar Monitoring Network is presented in tabular and pictorial form and related to similar information from other Western U.S. sites. A comparison of the amount of incident solar radiation is made us

  19. Water-Moderated and -Reflected Slabs of Uranium Oxyfluoride

    SciTech Connect (OSTI)

    Margaret A. Marshall; John D. Bess; J. Blair Briggs; Clinton Gross

    2010-09-01T23:59:59.000Z

    A series of ten experiments were conducted at the Oak Ridge National Laboratory Critical Experiment Facility in December 1955, and January 1956, in an attempt to determine critical conditions for a slab of aqueous uranium oxyfluoride (UO2F2). These experiments were recorded in an Oak Ridge Critical Experiments Logbook and results were published in a journal of the American Nuclear Society, Nuclear Science and Engineering, by J. K. Fox, L. W. Gilley, and J. H. Marable (Reference 1). The purpose of these experiments was to obtain the minimum critical thickness of an effectively infinite slab of UO2F2 solution by extrapolation of experimental data. To do this the slab thickness was varied and critical solution and water-reflector heights were measured using two different fuel solutions. Of the ten conducted experiments eight of the experiments reached critical conditions but the results of only six of the experiments were published in Reference 1. All ten experiments were evaluated from which five critical configurations were judged as acceptable criticality safety benchmarks. The total uncertainty in the acceptable benchmarks is between 0.25 and 0.33 % ?k/keff. UO2F2 fuel is also evaluated in HEU-SOL-THERM-043, HEU-SOL-THERM-011, and HEU-SOL-THERM-012, but these those evaluation reports are for large reflected and unreflected spheres. Aluminum cylinders of UO2F2 are evaluated in HEU-SOL-THERM-050.

  20. NEAMSUpdateQuarterly report for January March 2013 Published May 2013 Nuclear Energy

    E-Print Network [OSTI]

    Kemner, Ken

    of fracture behavior in UO2 were performed (page 2). }} A new model for fuel restructuring by void/pore, and structural mechanics modules were integrated in SHARP to perform high-fidelity, multiphysics simulations (page 3). }} Collaborations with Russia and Euratom continue to assess models of thermal fluid flows

  1. Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives

    SciTech Connect (OSTI)

    baney, Ronald; Tulenko, James

    2012-11-20T23:59:59.000Z

    The objective of this research is to increase the thermal conductivity of uranium oxide (UO{sub 2}) without significantly impacting its neutronic properties. The concept is to incorporate another high thermal conductivity material, silicon carbide (SiC), in the form of whiskers or from nanoparticles of SiC and a SiC polymeric precursor into UO{sub 2}. This is expected to form a percolation pathway lattice for conductive heat transfer out of the fuel pellet. The thermal conductivity of SiC would control the overall fuel pellet thermal conductivity. The challenge is to show the effectiveness of a low temperature sintering process, because of a UO{sub 2}-SiC reaction at 1,377°C, a temperature far below the normal sintering temperature. Researchers will study three strategies to overcome the processing difficulties associated with pore clogging and the chemical reaction of SiC and UO{sub 2} at temperatures above 1,300°C:

  2. APOLLO 16 VOICE TRANSCRIPT PERTAINING TO THE GEOLOGY OF THE LANDING SITE

    E-Print Network [OSTI]

    Rathbun, Julie A.

    * * *: {( APOLLO 16 VOICE TRANSCRIPT PERTAINING TO THE GEOLOGY OF THE LANDING SITE #12;- APOLLO 16 VOICE TRANSCRIPT Pertaining to the geology of the landIng site by N.G. Bai loey and G.E. Ulrich U.s. Geol:ogical Survey Branch of Astrogeology F]agstaff~ Arizona 1915 #12;FORM NTlS·315 UO-70

  3. Nanocrystalline Metals Andy Howe, Corus RD&T

    E-Print Network [OSTI]

    Cambridge, University of

    for single phase polygonal structures · Concentrate on refinement of dual phase structures ­ Dual Phase & with the emphasis on steel! Andy Howe, Corus RD&T Super Bainite Workshop, 6/05/2010 #12;Outline · Ultra-fine Ferrite iron to whatever strength you want! FIB-cut and imaged sub-micron IF steel Corus ­ UoManchester +FEI

  4. Continued on back UNIVERSITY OF OREGON

    E-Print Network [OSTI]

    Oregon, University of

    Continued on back UNIVERSITY OF OREGON MOBILE TECHNOLOGY ACCESS AND PAYMENT OPTION REQUEST Please complete this form to apply for access to mobile technology (e.g., cell phones, smart phones, etc device use. Information on the UO policies regarding access to mobile technology and payment options can

  5. Research Strategy February 2014

    E-Print Network [OSTI]

    Paxton, Anthony T.

    3.1 Priority areas of research Marine Renewable Energy The marine group has an established track in each discipline. 3. The School has a number of strategic international network connectionsA27) and Town & Country Planning (UoA31). The outcome is summarised in Table 1. Table 1 Percentage

  6. An economic analysis of investment in agricultural land

    E-Print Network [OSTI]

    Cherry, Russell Cather

    1966-01-01T23:59:59.000Z

    . DED KCATXOM ~isieia dedioar-Xa teats a mi quixida esposa . sou tuba amabile a@ada y dsfueruo incesagte yo uo pudiexa habet texmioado mi maestxia ~bar X ~ XNTPtODUCTXOM AMD STATIPIEMT OF THE PROBLEM a ~ o 0 o o 0 ~ XXe THE THEORETXCAL ~RK ~ 'a o oo...

  7. Spin-lattice coupling in uranium dioxide probed by magnetostriction measurements at high magnetic fields (P08358-E001-PF)

    SciTech Connect (OSTI)

    K. Gofryk; M. Jaime

    2014-12-01T23:59:59.000Z

    Conclusions Our preliminary magnetostriction measurements have already shown a strong interplay of lattice dynamic and magnetism in both antiferromagnetic and paramagnetic states, and give unambiguous evidence of strong spin- phonon coupling in uranium dioxide. Further studies are planned to address the puzzling behavior of UO2 in magnetic and paramagnetic states and details of the spin-phonon coupling.

  8. The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

    SciTech Connect (OSTI)

    Prof. Simon Phillpot; Prof. Susan B. Sinnott; Prof. Hans Seifert; Prog. James Tulenko

    2009-01-26T23:59:59.000Z

    Demonstrated that FRAPCON can be modified to accept data generated from first principles studies, and that the result obtained from the modified FRAPCON make sense in terms of the inputs. Determined the temperature dependence of the thermal conductivity of single crystal UO2 from atomistic simulation.

  9. Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code

    E-Print Network [OSTI]

    Bellanger, Philippe

    1999-01-01T23:59:59.000Z

    The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited...

  10. Design and Optimization of Neuro-Fuzzy-Based Recognition of Musical Rhythm Patterns

    E-Print Network [OSTI]

    Weyde, Tillman

    Design and Optimization of Neuro-Fuzzy-Based Recognition of Musical Rhythm Patterns Tillman Weyde framework to support computer models and applications has not yet been established. Musical Pattern@uos.de Abstract The task of recognizing patterns and assigning rhythmic structure to unquan- tized musical input

  11. Bioremediation of Uranium Plumes with Nano-scale

    E-Print Network [OSTI]

    Fay, Noah

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

  12. Timetable of events Knowledge exchange seminars 23 to 26 september 2013

    E-Print Network [OSTI]

    Reading, University of

    Estate Valuation Methods Welcome and Introduction Michael Newey President RICS seminar 9:30 Eliane Monetti USP Valuation Methods in Brazil seminar 10:00 Fernando Burone UB Urban Land Valuations of Development Project in Argentina seminar 10:30 Coffee break 11:00 Real Estate Valuation Methods Neil Crosby Uo

  13. Curriculum vitae of Viviana Mascardi (updated to September Personal data

    E-Print Network [OSTI]

    Mascardi, Viviana

    rock carvings. #12;Role: Principal investigator, UO coordinator Funding source and programme: MIUR FIRB: Mobilit`a Intelligente Ecosostenibile (MIE) Role: Participant Funding source and programme: MIUR, progetto for Reliable Large-Scale Software Systems (BETTY) Role: Participant Funding source and programme: ICT COST

  14. Hydrofluoric Acid Corrosion Testing on Unplated and Electroless Gold-Plated Samples

    SciTech Connect (OSTI)

    Osborne, P.E.; Icenhour, A.S.; Del Cul, G.D.

    2000-08-01T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) remediation requires that almost 40 kg of uranium hexafluoride (UF6) be converted to uranium oxide (UO). In the process of this conversion, six moles of hydrofluoric acid (HP) are produced for each mole of UF6 converted.

  15. Characterizing solution and solid-phase amorphous uranyl silicates q

    E-Print Network [OSTI]

    Illinois at Chicago, University of

    . Skanthakumar a , D. Gorman-Lewis a , M.P. Jensen a , K.L. Nagy b a Chemistry Division, Argonne National 2007 Elsevier Ltd. All rights reserved. 1. INTRODUCTION Dissolved uranium, as the uranyl ion UO2 2þ relevant conditions is severely ham- pered by its chemistry in near neutral or basic groundwater, where

  16. Diffusion model of the non-stoichiometric uranium dioxide

    SciTech Connect (OSTI)

    Moore, Emily, E-mail: emily.moore@cea.fr [CEA Saclay, DEN-DPC-SCCME, 91191 Gif-sur-Yvette Cedex (France); Guéneau, Christine, E-mail: christine.gueneau@cea.fr [CEA Saclay, DEN-DPC-SCCME, 91191 Gif-sur-Yvette Cedex (France); Crocombette, Jean-Paul, E-mail: jean-paul.crocombette@cea.fr [CEA Saclay, DEN DEN, Service de Recherches de Métallurgie Physique, 91191 Gif-sur-Yvette Cedex (France)

    2013-07-15T23:59:59.000Z

    Uranium dioxide (UO{sub 2}), which is used in light water reactors, exhibits a large range of non-stoichiometry over a wide temperature scale up to 2000 K. Understanding diffusion behavior of uranium oxides under such conditions is essential to ensure safe reactor operation. The current understanding of diffusion properties is largely limited by the stoichiometric deviations inherent to the fuel. The present DICTRA-based model considers diffusion across non-stoichiometric ranges described by experimentally available data. A vacancy and interstitial model of diffusion is applied to the U–O system as a function of its defect structure derived from CALPHAD-type thermodynamic descriptions. Oxygen and uranium self and tracer diffusion coefficients are assessed for the construction of a mobility database. Chemical diffusion coefficients of oxygen are derived with respect to the Darken relation and migration energies of defects are evaluated as a function of stoichiometric deviation. - Graphical abstract: Complete description of Oxygen–Uranium diffusion as a function of composition at various temperatures according to the developed Dictra model. - Highlights: • Assessment of a uranium–oxygen diffusion model with Dictra. • Complete description of U–O diffusion over wide temperature and composition range. • Oxygen model includes terms for interstitial and vacancy migration. • Interaction terms between defects help describe non-stoichiometric domain of UO{sub 2±x}. • Uranium model is separated into mobility terms for the cationic species.

  17. Morphological and ultrastructural study of extrusion texturized defatted soy flour

    E-Print Network [OSTI]

    Kazemzadeh, Massoud

    1980-01-01T23:59:59.000Z

    and the speed of the cutting knii'e. Moist extrudate is then dried, ;:cooled, and, packaged. Dried, textured products contain 6 ? 8'fo mois- ture, 50-53%%uo protein, 1'%%d fat, 3% fiber, and 5 ? 6% ash. Den- sities may range from 9-25 1b/cu. ft. (Ziemba...

  18. ENDF/B-V, ENDF/B-VI, AND ENDF/B-VII.0 RESULTS FOR THE DOPPLER-DEFECT BENCHMARK (U)

    SciTech Connect (OSTI)

    MOSTELLER, RUSSELL D. [Los Alamos National Laboratory

    2007-02-09T23:59:59.000Z

    A set of computational benchmarks for the Doppler reactivity defect has been specified for an infinite array of identical fuel pin cells containing normal or enriched UO{sub 2} fuel, reactor-recycle mixed-oxide (MOX) fuel, or weapons-grade MOX fuel. The Doppler coefficient of reactivity, as well as the Doppler defect, can be computed for each of the cells. The MCNP5 Monte Carlo code was used to perform calculations for these benchmarks using cross sections derived from the ENDF/B-V, ENDF/B-VI, and ENDF/B-VII.0 nuclear data sets. The Doppler coefficients obtained from the three data sets exhibit very similar behavior. The Doppler coefficient for UO{sub 2} fuel becomes less negative with increasing enrichment, with a generally asymptotic shape. The Doppler coefficient for the reactor-recycle MOX becomes less negative with increasing PuO{sub 2} content but exhibits less curvature than that for UO{sub 2} fuel. The Doppler coefficient for weapons-grade MOX shows a pronounced shoulder between 1 wt.% and 2 wt.% PuO{sub 2}, with a nearly constant value thereafter. The Doppler coefficient for heavily loaded MOX fuel, whether reactor-recycle or weapons-grade, is significantly more negative than that for highly enriched UO{sub 2} fuel.

  19. Refinement in the ultrasonic velocity data and estimation of the critical parameters for molten uranium dioxide

    E-Print Network [OSTI]

    Azad, Abdul-Majeed

    accurate exper- imental measurements on the density, and heat capacity of liquid UO2 up to $8000 K density and isobaric heat capacity, much more easily than other conventional methods [3,4]. Many of state for liquid urania has also been developed which predicts a critical temperature (Tc) % 10500 K

  20. *EH&S has hire date, date of birth, employee's gender and hours of employment on file University of Washington

    E-Print Network [OSTI]

    Wilcock, William

    /Parking Lot: Room: Other: Incident Details: Classification (Please select level and check an item below) Uo Violence: Patient, Staff, Visitors h Radiation h Motor Vehicles h Non-human Primates h Drugs h None h Other Housekeeping h Inclement Weather h Slippery/Uneven surface h Ergonomics Issues h Sharp Objects h Hot Objects h

  1. Proceedings of IMECE04 2004 ASME International Mechanical Engineering Congress

    E-Print Network [OSTI]

    Motta, Arthur T.

    of uranium dioxide (UO2) encased in long thin tubes (called fuel cladding) made of zirconium alloys as coolant to remove the heat from the core and produce power. The fuel cladding has the functions procedures of Zr alloys so that corrosion of the zirconium alloy cladding tubing in nuclear reactors

  2. CX-011566: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Mechanical Behavior of Uranium Oxide (UO2) at Sub-grain Length Scales: Quantification of Elastic, Plastic and Creep Properties via Microscale Testing CX(s) Applied: B3.6 Date: 11/18/2013 Location(s): Arizona Offices(s): Idaho Operations Office

  3. Oldest and Largest The Weather

    E-Print Network [OSTI]

    one spot to fourth place in the U,S. News and World Report college rankings this year but remained in FILGs This year, 30 ~ambridge stu- CMI, Page 17 FRANK DABEK-THE TECH Pamela ThUo and her sons ~icholas

  4. A strategic partnership with the University of Exeter A logo representing an equal partenership or collaboration should be displayed at

    E-Print Network [OSTI]

    Bristol, University of

    Example B A strategic partnership with the University of Exeter · A logo representing an equal partenership or collaboration should be displayed at the bottom left of the letter. The logo can be smaller or equal size to the UoB logo but MUST NOT be larger (see Example A). A brief caption should also

  5. Reduction and desymmetrisation of the uranyl dication in a macrocyclic framework 

    E-Print Network [OSTI]

    Patel, Dipti

    The transamination reaction between a Schiff base polypyrrolic macrocycle, H4Ltet/oct, where tet = tetramethyl (C38H36N8), oct = octamethyl (C42H44N8), and [UO2(THF)2{N(SiMe3)2}] results in the sole formation of mono ...

  6. Incorporation of radionuclides in the alteration phases of spent nuclear fuel.

    SciTech Connect (OSTI)

    Buck, E. C.; Kim, C.-W.; Wronkiewicz, D. J.

    1999-08-25T23:59:59.000Z

    Alteration may be expected for spent nuclear fuel exposed to groundwater under oxidizing conditions such as that which exist at the proposed nuclear waste repository at Yucca Mountain, Nevada. The actinide elements released during the corrosion of spent fuel may be incorporated into the structures of secondary U{sup 6+} phases. The incorporation of transuranics into the crystal structures of the alteration products may significantly decrease their mobility. A series of precipitation tests were conducted at 90 C to determine the potential incorporation of Ce{sup 4+} and Nd{sup 3+} (surrogates for Pu{sup 4+} and Am{sup 3+}, respectively) into uranyl phase. Dehydrated schoepite (UO{sub 3}{center_dot}0.8-1.0HP{sub 2}O) was produced by hydrolysis of a uranium oxyacetate solution containing either cerium or neodymium. ICP-MS analysis of the leachant, leachate, and solid phase reaction products which were dissolved in a HNO{sub 3} solution indicates that 26 ppm of Ce was incorporated into dehydrated schoepite. ICP-MS results from the Nd-doped tests indicate significant neodymium incorporation as well, however, the heterogeneous distribution of Nd in the solid phase noted during the AEM/EELS examination implies that neodymium may not incorporate into the structure of dehydrated schoepite.

  7. A comparison of the y-Radiolysis of TODGA and T(EH)DGA using UHPLC-ESI-MS analysis

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

    Zarzana, Christopher A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Groenewold, Gary S. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mincher, Bruce J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mezyk, Stephen P. [California State Uni; Wilden, Andreas [Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung-Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Jülich (Germany); Schmidt, Holger [Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung-Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Jülich (Germany); Modolo, Giuseppe [Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung-Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Jülich (Germany); Wishart, James F. [Brookhaven National Lab. (BNL), Upton, NY (United States); Cook, Andrew R. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27T23:59:59.000Z

    Solutions of the diglycolamide extractants TODGA and T(EH)DGA in n-dodecane were subjected to ?- irradiation in the presence and absence of an acidic aqueous phase. These solutions were then analyzed using UHPLC-ESI-MS to determine the rates of radiolytic decay of the two extractants neat and in contact with respect to the acidity of the contacted aqueous phase, as well as to identify radiolysis products. The presence or absence of an acidic aqueous phase was shown to have no influence on the measured decay rates, nor did the side-chain have an influence. A number of radiolysis products were identified, consistent with those previously identified for these two compounds using GC-MS. The identity of these radiolysis products suggests that the bonds most vulnerable to radiolytic attack are those in the dyglycolamide center of these molecules, and not on the side-chains.  The agreement of these results with previous work using GC-MS indicates supports the further use of UHPLC-ESI-MS as a tool for studying diglycolamide extractant systems.

  8. Zi-Wei Lin Oct 5, 2004 UAH / NASA Space Radiation Shielding Program, MS Determine Important Nuclear Fragmentation Processes

    E-Print Network [OSTI]

    Lin, Zi-wei

    Zi-Wei Lin Oct 5, 2004 UAH / NASA Space Radiation Shielding Program, MS Determine Important Nuclear Fragmentation Processes for Space Radiation Protection in Human Space Explorations Why do we need to study? Conclusions Zi-Wei Lin University of Alabama in Huntsville/ NASA Space Radiation Shielding Program, MSFC #12

  9. Bogazici University, Istanbul, Turkey Chemical Engineering B.S., 2006 Bogazici University, Istanbul, Turkey Chemical Engineering M.S., 2008

    E-Print Network [OSTI]

    Pennycook, Steve

    Education Bogazici University, Istanbul, Turkey Chemical Engineering B.S., 2006 Bogazici University, Istanbul, Turkey Chemical Engineering M.S., 2008 The Ohio State University, Columbus, Ohio Chemical study awarded from The Scientific and Technological Research Council of Turkey Ibrahim Ilgaz Soykal

  10. A Review of "Nicholas Oldisworth’s Manuscript (Bodleian MS. Don.c.24)" edited by John Gouws

    E-Print Network [OSTI]

    De Quehen, A. H.

    2011-01-01T23:59:59.000Z

    of George Herbert. John Gouws, ed. Nicholas Oldisworth?s Manuscript (Bodleian MS. Don.c.24). Tempe, AZ: Arizona Center for Medieval and Renaissance Studies, 2009. xlv + 256 pp. $54.00. Review by a.h. de quehen, university of toronto. Nicholas Oldisworth...

  11. MS#040418-01 1 Abstract--The fine scale swimming behavior of fish can now be

    E-Print Network [OSTI]

    Linder, Stephen

    MS#040418-01 1 Abstract--The fine scale swimming behavior of fish can now be studied because evaluation of the performance of these tracking algorithms for the analysis of fine scale behavior of fish was performed using a data set of 100 fish track tracks recorded simultaneously with a multibeam sonar

  12. 48 28th ANNUAL eMS CHROMIUM(llI) INDUCED SOLID PHASE TRANSFORMATION OF o-Mn02

    E-Print Network [OSTI]

    Sparks, Donald L.

    48 28th ANNUAL eMS CHROMIUM(llI) INDUCED SOLID PHASE TRANSFORMATION OF o-Mn02 Fendorf S pathways which will allow for transformations between oxidation states (redox reactions). Manganese oxides implications for environmental quality. The highly redox reactive a-Mn02 is transformed into a redox stable

  13. Ultrafast laser ablation ICP-MS: role of spot size, laser fluence, and repetition rate in signal intensity

    E-Print Network [OSTI]

    Harilal, S. S.

    Ultrafast laser ablation ICP-MS: role of spot size, laser fluence, and repetition rate in signal,a Richard E. Russob and Ahmed Hassaneina Ultrafast laser ablation inductively coupled plasma mass system. Though ultrafast laser ablation sample introduction provides better accuracy and precision

  14. Sorption of MS2 Bacteriophage to Layered Double Hydroxides: Effects of Reaction Time, pH, and Competing Anions

    E-Print Network [OSTI]

    Sparks, Donald L.

    that some materials such as coal-based media, clay minerals, metal oxides­hydroxides, and activated very high retention capacities for from an aqueous solution by bituminous coal (Oza and MS2. Sorption) from 5.2 102 plaque-forming units (pfu)/mL solution by Mg­Al reported that some coal-based media

  15. A self-consistent nonlinear force-free solution for a solar active region magnetic M.S. Wheatland

    E-Print Network [OSTI]

    Régnier, Stéphane

    fields 1. Introduction Solar coronal magnetic fields provide the source of energy for solar flaresA self-consistent nonlinear force-free solution for a solar active region magnetic field M.S. Wheatland Sydney Institute for Astronomy, School of Physics, University of Sydney, NSW 2006, Australia m

  16. SURFACE OXIDATION OF DIESEL PARTICULATE MATTER IN PRESENCE OF O3 +NOX: NEW TD/GC/MS ANALYSIS METHOD

    E-Print Network [OSTI]

    Holmén, Britt A.

    SURFACE OXIDATION OF DIESEL PARTICULATE MATTER IN PRESENCE OF O3 +NOX: NEW TD/GC/MS ANALYSIS METHOD+08 2.6e+08 2.8e+08 3e+08 Time--> Abundance TIC: 0914S4.D INTRODUCTION Diesel exhaust is one into the atmosphere diesel particles can be transformed through physical and chemical processes resulting

  17. A comparison of the y-Radiolysis of TODGA and T(EH)DGA using UHPLC-ESI-MS analysis

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

    Zarzana, Christopher A.; Groenewold, Gary S.; Mincher, Bruce J.; Mezyk, Stephen P.; Wilden, Andreas; Schmidt, Holger; Modolo, Giuseppe; Wishart, James F.; Cook, Andrew R.

    2015-04-27T23:59:59.000Z

    Solutions of the diglycolamide extractants TODGA and T(EH)DGA in n-dodecane were subjected to ?- irradiation in the presence and absence of an acidic aqueous phase. These solutions were then analyzed using UHPLC-ESI-MS to determine the rates of radiolytic decay of the two extractants neat and in contact with respect to the acidity of the contacted aqueous phase, as well as to identify radiolysis products. The presence or absence of an acidic aqueous phase was shown to have no influence on the measured decay rates, nor did the side-chain have an influence. A number of radiolysis products were identified, consistent with thosemore »previously identified for these two compounds using GC-MS. The identity of these radiolysis products suggests that the bonds most vulnerable to radiolytic attack are those in the dyglycolamide center of these molecules, and not on the side-chains.  The agreement of these results with previous work using GC-MS indicates supports the further use of UHPLC-ESI-MS as a tool for studying diglycolamide extractant systems.« less

  18. Non-Darcy natural convection in high porosity metal foams M.S. Phanikumar a,*, R.L. Mahajan b

    E-Print Network [OSTI]

    ­Forchheimer-extended Darcy flow model and a semi-heuristic two-equation energy model obtained by relaxing the local thermalNon-Darcy natural convection in high porosity metal foams M.S. Phanikumar a,*, R.L. Mahajan b but only a heated plate. Thermal dispersion effects and the effects of Darcy number on heat transfer

  19. Taxonomic Classification of Planning Decisions in Health Care: a Review of the State of the Art in OR/MS

    E-Print Network [OSTI]

    Boucherie, Richard J.

    Taxonomic Classification of Planning Decisions in Health Care: a Review of the State of the Art Classification of Planning Decisions in Health Care: a Review of the State of the Art in OR/MS 2 1. Introduction a comprehensive bibliography on operating room management articles. `ORCHID' [181] is a reference library, which

  20. DETECTION OF ALUMINUM WASTE REACTIONS AND WASTE FIRES Jeffrey W. Martin, M.S., P.G., R.S.

    E-Print Network [OSTI]

    combustion of the surrounding solid waste. The landfill liner and explosive gas extraction and leachate, landfill, leachate, leachate recirculation, salt cake, slope stability, smoldering, solid waste, Subtitle DDETECTION OF ALUMINUM WASTE REACTIONS AND WASTE FIRES Jeffrey W. Martin, M.S., P.G., R

  1. SUMUKH V., engineering educator; b. Maharashlra. India; S. BabWekar. MS in Mech. Engring. The V. Toledo, Ohio. 2002.

    E-Print Network [OSTI]

    Baica, Malvina

    and Zhenyu Bai; m, Yan Wang, Feb. 25,1958; I child, Xoe, MS. Beijing Inst. Tech,. 1987; BS. Tsinghua Br. V .· Beijing. 1983; PhD. Aa. Atlantic V .· Boca Raton, 2000. Sr. software engr. Lam Rsch. Corp.. Fremont. Calif

  2. Application for theAnn and Bill Fisher Graduate Scholarship 1. Your name Mr. Miss, Ms., Mrs.

    E-Print Network [OSTI]

    Rock, Chris

    Application for theAnn and Bill Fisher Graduate Scholarship 1. Your name Mr. Miss, Ms., Mrs): _____________________________________________ _____________________________________________ 6. Date of birth: (month, day, year): Page 1 of 3 Eligibility: You are eligible for this scholarship; and You are proficient in at least two languages; and You are able to demonstrate 1) outstanding academic

  3. Application for theAnn and Bill Fisher Graduate Scholarship 1. Your name Mr. Miss, Ms., Mrs.

    E-Print Network [OSTI]

    Rock, Chris

    Application for theAnn and Bill Fisher Graduate Scholarship 1. Your name Mr. Miss, Ms., Mrs): _____________________________________________ _____________________________________________ 5. Date of birth: (month, day, year): Page 1 of 3 Eligibility: You are eligible for this scholarship, and You are proficient in at least two languages, and You are able to demonstrate 1)outstanding academic

  4. Yucca Mountain Project - Argonne National Laboratory annual progress report, FY 1994

    SciTech Connect (OSTI)

    Bates, J.K.; Fortner, J.A.; Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Buck, E.C.; Wolf, S.F.

    1995-02-01T23:59:59.000Z

    This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form. Studies are also underway to evaluate the performance of spent fuel samples and unirradiated UO{sub 2} in projected repository conditions. Tests with UO{sub 2} have been ongoing for nine years and show that the oxidation of UO{sub 2} occurs rapidly, and the resulting paragenetic sequence of secondary phases that form on the sample surface is similar to that observed in natural analogues. The reaction of spent fuel samples under conditions similar to those used with UO{sub 2} have been in progress for nearly two years, and the results suggest that spent fuel follows the same reaction progress as UO{sub 2}. The release of individual fission products and transuranic elements was not congruent, with the release being controlled by the formation of small particles or colloids that are suspended in solution and transported away from the waste form. The reaction progress depends on the composition of the spent fuel samples used and, likely, on the composition of the groundwater that contacts the waste form.

  5. New insights into uranium (VI) sol-gel processing

    SciTech Connect (OSTI)

    King, C.M.; Thompson, M.C.; Buchanan, B.R. (Westinghouse Savannah River Co., Aiken, SC (USA)); King, R.B. (Georgia Univ., Athens, GA (USA). Dept. of Chemistry); Garber, A.R. (South Carolina Univ., Columbia, SC (USA). Dept. of Chemistry)

    1990-01-01T23:59:59.000Z

    Nuclear Magnetic Resonance (NMR) investigations on the Oak Ridge National Laboratory process for sol-gel synthesis of microspherical nuclear fuel (UO{sub 2}), has been extremely useful in sorting out the chemical mechanism in the sol-gel steps. {sup 13}C, {sup 15}N, and {sup 1}H NMR studies on the HMTA gelation agent (Hexamethylene tetramine, C{sub 6}H{sub 12}N{sub 4}) has revealed near quantitative stability of this adamantane-like compound in the sol-gel process, contrary to its historical role as an ammonia source for gelation from the worldwide technical literature. {sup 17}O NMR of uranyl (UO{sub 2}{sup ++}) hydrolysis fragments produced in colloidal sols has revealed the selective formation of a uranyl trimer, ((UO{sub 2}){sub 3}({mu}{sub 3}-O)({mu}{sub 2}-OH){sub 3}){sup +}, induced by basic hydrolysis with the HMTA gelation agent. Spectroscopic results will be presented to illustrate that trimer condensation occurs during sol-gel processing leading to layered polyanionic hydrous uranium oxides in which HMTAH{sup +} is occluded as an intercalation'' cation. Subsequent sol-gel processing of microspheres by ammonia washing results in in-situ exchange and formation of a layered hydrous ammonium uranate with a proposed structural formula of (NH{sub 4}){sub 2} ((UO{sub 2}){sub 8} O{sub 4} (OH){sub 10}) {center dot} 8H{sub 2}O. This compound is the precursor to sintered UO{sub 2} ceramic fuel. 23 refs., 10 figs.

  6. Modeling and analyses of postulated UF{sub 6} release accidents in gaseous diffusion plant

    SciTech Connect (OSTI)

    Kim, S.H.; Taleyarkhan, R.P.; Keith, K.D.; Schmidt, R.W. [Oak Ridge National Lab., TN (United States); Carter, J.C. [J.C. Carter Associates, Inc., Oak Ridge, TN (United States); Dyer, R.H. [Dyer Enterprises, Oak Ridge, TN (United States)

    1995-10-01T23:59:59.000Z

    Computer models have been developed to simulate the transient behavior of aerosols and vapors as a result of a postulated accident involving the release of uranium hexafluoride (UF{sub 6}) into the process building of a gaseous diffusion plant. UF{sub 6} undergoes an exothermic chemical reaction with moisture (H{sub 2}O) in the air to form hydrogen fluoride (HF) and radioactive uranyl fluoride (UO{sub 2}F{sub 2}). As part of a facility-wide safety evaluation, this study evaluated source terms consisting of UO{sub 2}F{sub 2} as well as HF during a postulated UF{sub 6} release accident in a process building. In the postulated accident scenario, {approximately}7900 kg (17,500 lb) of hot UF{sub 6} vapor is released over a 5 min period from the process piping into the atmosphere of a large process building. UO{sub 2}F{sub 2} mainly remains as airborne-solid particles (aerosols), and HF is in a vapor form. Some UO{sub 2}F{sub 2} aerosols are removed from the air flow due to gravitational settling. The HF and the remaining UO{sub 2}F{sub 2} are mixed with air and exhausted through the building ventilation system. The MELCOR computer code was selected for simulating aerosols and vapor transport in the process building. MELCOR model was first used to develop a single volume representation of a process building and its results were compared with those from past lumped parameter models specifically developed for studying UF{sub 6} release accidents. Preliminary results indicate that MELCOR predicted results (using a lumped formulation) are comparable with those from previously developed models.

  7. Discovery of Optical Bursts from MS1603.6+2600 = UW CrB

    E-Print Network [OSTI]

    R. I. Hynes; E. L. Robinson; E. Jeffery

    2004-05-11T23:59:59.000Z

    We report the discovery of several optical burst-like events from the low-mass X-ray binary MS1603.6+2600 (UW CrB). The events last for a few tens of seconds, exhibit a very fast rise and slow decay, and involve optical brightening of a factor of 2-3. The flares appear distinct from the lower level flickering and instead strongly resemble reprocessed type-I X-ray bursts as seen in a number of other neutron star low-mass X-ray binaries. In conjunction with the previously reported candidate X-ray burst, these confirm that the compact object in UW CrB is a neutron star. We examine the optical burst brightness and recurrence times and discuss how the nature of the system can be constrained. We conclude that the source is most likely an accretion disk corona source at an intermediate distance, rather than a nearby quiescent system or very distant dipper.

  8. Web Site: http://www.coop-program.engr.uga.edu/ms.html UGA Cooperative Engineering Program Development Key Points and Notes.docx

    E-Print Network [OSTI]

    Arnold, Jonathan

    Web Site: http://www.coop-program.engr.uga.edu/ms.html UGA Cooperative Engineering Program;Web Site: http://www.coop-program.engr.uga.edu/ms.html UGA Cooperative Engineering Program Development Development Key Points and Notes.docx Latest Update: October 3, 2012 Mission Statement: The UGA Engineering

  9. Handbook of M.S. Programs -Industrial & Systems Engineering Department, Wayne State University Revised: May 8, 2013 Pg. 1 of 10

    E-Print Network [OSTI]

    Berdichevsky, Victor

    Handbook of M.S. Programs - Industrial & Systems Engineering Department, Wayne State University Revised: May 8, 2013 Pg. 1 of 10 M.S. Programs Handbook Industrial & Systems Engineering Department Wayne Engineering at Wayne State University: Master of Science in Industrial Engineering Master of Science

  10. Surface Cleaning Techniques: Ultra-Trace ICP-MS Sample Preparation and Assay of HDPE

    SciTech Connect (OSTI)

    Overman, Nicole R.; Hoppe, Eric W.; Addleman, Raymond S.

    2013-06-01T23:59:59.000Z

    The world’s most sensitive radiation detection and assay systems depend upon ultra-low background (ULB) materials to reduce unwanted radiological backgrounds. Herein, we evaluate methods to clean HDPE, a material of interest to ULB systems and the means to provide rapid assay of surface and bulk contamination. ULB level material and ultra-trace level detection of actinide elements is difficult to attain, due to the introduction of contamination from sample preparation equipment such as pipette tips, sample vials, forceps, etc. and airborne particulate. To date, literature available on the cleaning of such polymeric materials and equipment for ULB applications and ultra-trace analyses is limited. For these reasons, a study has been performed to identify an effective way to remove surface contamination from polymers in an effort to provide improved instrumental detection limits. Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) was utilized to assess the effectiveness of a variety of leachate solutions for removal of inorganic uranium and thorium surface contamination from polymers, specifically high density polyethylene (HDPE). HDPE leaching procedures were tested to optimize contaminant removal of thorium and uranium. Calibration curves for thorium and uranium ranged from 15 ppq (fg/mL) to 1 ppt (pg/mL). Detection limits were calculated at 6 ppq for uranium and 7 ppq for thorium. Results showed the most effective leaching reagent to be clean 6 M nitric acid for 72 hour exposures. Contamination levels for uranium and thorium found in the leachate solutions were significant for ultralow level radiation detection applications.

  11. Project Final Report: Ubiquitous Computing and Monitoring System (UCoMS) for Discovery and Management of Energy Resources

    SciTech Connect (OSTI)

    Tzeng, Nian-Feng; White, Christopher D.; Moreman, Douglas

    2012-07-14T23:59:59.000Z

    The UCoMS research cluster has spearheaded three research areas since August 2004, including wireless and sensor networks, Grid computing, and petroleum applications. The primary goals of UCoMS research are three-fold: (1) creating new knowledge to push forward the technology forefronts on pertinent research on the computing and monitoring aspects of energy resource management, (2) developing and disseminating software codes and toolkits for the research community and the public, and (3) establishing system prototypes and testbeds for evaluating innovative techniques and methods. Substantial progress and diverse accomplishment have been made by research investigators in their respective areas of expertise cooperatively on such topics as sensors and sensor networks, wireless communication and systems, computational Grids, particularly relevant to petroleum applications.

  12. 10.30.2001 1Soon Cho -AVS01 MS-TuA8 Thickness Metrology and Real-Time

    E-Print Network [OSTI]

    Rubloff, Gary W.

    Electronics Box Lamp Heater #12;10.30.2001 5Soon Cho - AVS01 MS-TuA8 Metrology Development in 0.5 Torr SiH4/WF) + SiH4 (g) èèèè W (s) + 2 SiHF3 (g) + 3 H2 (g) SiH4SignalH2Signal Step # 1 & 2 3 4 5 6 P (Mtorr) 100

  13. Aufgabe 3-7: Luft tritt mit 1 = 2,21 kg/m und v1 = 40 m/s kontinuierlich in eine Dse ein und verlsst diese mit 2 = 0,762 kg/m und v2 = 180 m/s. Die Einlassflche der Dse betrgt 90

    E-Print Network [OSTI]

    Peters, Norbert

    Aufgabe 3-7: Luft tritt mit 1 = 2,21 kg/m³ und v1 = 40 m/s kontinuierlich in eine Düse ein und, 800 kPa) tritt mit 10 m/s in eine Düse ein (siehe Abbildung 1). In der Düse verliert der Dampf Wärme

  14. M.S. ABDULLAH, I. BENEST, A. EVANS, and C. KIMBLE, Knowledge Modelling Techniques For Developing Knowledge Management Systems, 3rd European Conference on

    E-Print Network [OSTI]

    Kimble, Chris

    modelling, knowledge management, knowledge management system, knowledge, knowledge engineering. 1M.S. ABDULLAH, I. BENEST, A. EVANS, and C. KIMBLE, Knowledge Modelling Techniques For Developing Knowledge Management Systems, 3rd European Conference on Knowledge Management, Dublin, Ireland, September

  15. Quantitative 3-D Elemental Mapping by LA-ICP-MS of a Basaltic Clast from the Hanford 300 Area, Washington, USA

    E-Print Network [OSTI]

    Hu, Qinhong "Max"

    : Laser ablation with inductively coupled plasma- mass spectrometry (LA-ICP-MS) was used to measure (XAS2,8 ), and by cryogenic laser-induced fluorescence spectroscopy (CLIFS7 ). Both XAS and CLIFS

  16. TECHBOOKS Journal: AGAG MS Code: 529 PIPS No: 5271116 DISK 1-4-2004 18:38 Pages: 43 Annals of Global Analysis and Geometry xxx: 143, 2004.

    E-Print Network [OSTI]

    Belaud, Yves

    UNCO RRECTED PRO O F TECHBOOKS Journal: AGAG MS Code: 529 PIPS No: 5271116 DISK 1-4-2004 18 et Phys. Parc de Grandmont, 37200 Tours, France. e-mail: belaud@univ-tours.fr 5 6 (Received: 25

  17. {sup 99}Tc bioassay: A direct comparison of liquid scintillation radiation detection and ICP-MS mass detection of the {sup 99}Tc isotope

    SciTech Connect (OSTI)

    Lewis, L.A. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States). Analytical Services Organization; Schweitzer, G.K. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Chemistry

    1998-12-31T23:59:59.000Z

    A means of analyzing {sup 99}Tc in urine by inductively coupled plasma mass spectrometry (ICP-MS) has been developed. Historically, {sup 99}Tc analysis was based on the radiometric detection of the 293 keV E{sub Max.} beta decay product by liquid scintillation or gas flow proportional counting. A separation scheme for {sup 99}Tc detection by ICP-MS is given and is proven to be a sensitive and robust analytical alternative. A comparison of methods using radiometric and mass quantitation of {sup 99}Tc has been conducted in water, artificial urine, and real urine matrices at activity levels between 700 and 2,200 dpm/L. Liquid scintillation results based on an external standard manual quench correction and an automatic quench curve correction method are compared with results obtained by ICP-MS. Each method produced accurate results; however, the precision of the ICP-MS results is superior to that of liquid scintillation results.

  18. A 12b 50MS/s 2.1mW SAR ADC with redundancy and digital background calibration

    E-Print Network [OSTI]

    Chang, Albert H.

    A 12-bit 50MS/s SAR ADC implemented in 65nm CMOS technology is presented. The design employs redundancy to relax the DAC settling requirement and to provide sufficient room for errors such that the static nonlinearity ...

  19. Measurement of elemental speciation by liquid chromatography -- inductively coupled plasma mass spectrometry (LC-ICP-MS) with the direct injection nebulizer (DIN)

    SciTech Connect (OSTI)

    Shum, S.

    1993-05-01T23:59:59.000Z

    This thesis is divided into 4 parts: elemental speciation, speciation of mercury and lead compounds by microbore column LC-ICP-MS with direct injection nebulization, spatially resolved measurements of size and velocity distributions of aerosol droplets from a direct injection nebulizer, and elemental speciation by anion exchange and size exclusion chromatography with detection by ICP-MS with direct injection nebulization. Tabs, figs, refs.

  20. Radionuclide content of simulated and fully radioactive SRLLL waste gl;asses: comparison of results from ICP-MS, gamma spectrometry and alpha spectrometry

    SciTech Connect (OSTI)

    Wolf, S.F.; Bates, J.K.

    1995-12-31T23:59:59.000Z

    We have measured the transuranic content of two transuranic=doped, simulated waste glasses, using inductively coupled plasma-mass spectrometry (ICP-MS), {gamma}-spectrometry, and {alpha}-spectrometry. Average concentrations measured by each technique were within {+-} 10% of the as-doped concentrations. We also report the transuranic content of three fully radioactive SRL waste glasses that were determined using {gamma}- and {alpha}-spectrometry measurements to deconvolute isobaric interferences present in the ICP-MS analyses.

  1. Department Name Degrees Phone Email Website Aerospace Engineering MS, PhD 303-492-6416 aerograd@colorado.edu http://www.colorado.edu/aerospace

    E-Print Network [OSTI]

    Mulligan, Jane

    Department Name Degrees Phone Email Website Aerospace Engineering MS, PhD 303-492-6416 aerograd@colorado.edu http://www.colorado.edu/aerospace Anthropology MA, PhD 303-492-7947 anthro@colorado.edu http://www.colorado.edu/anthropology Applied Mathematics MS, PhD 303-492-1238 amgradco@colorado.edu http://amath.colorado.edu Art and Art

  2. Alkali vapor pressure modulation on the 100 ms scale in a single-cell vacuum system for cold atom experiments

    SciTech Connect (OSTI)

    Dugrain, Vincent; Reichel, Jakob [Laboratoire Kastler Brossel, ENS, UPMC, CNRS, 24 rue Lhomond, 75005 Paris (France); Rosenbusch, Peter [LNE-SYRTE, Observatoire de Paris, CNRS, UPMC, 61 av de l’Observatoire, 75014 Paris (France)

    2014-08-15T23:59:59.000Z

    We describe and characterize a device for alkali vapor pressure modulation on the 100 ms timescale in a single-cell cold atom experiment. Its mechanism is based on optimized heat conduction between a current-modulated alkali dispenser and a heat sink at room temperature. We have studied both the short-term behavior during individual pulses and the long-term pressure evolution in the cell. The device combines fast trap loading and relatively long trap lifetime, enabling high repetition rates in a very simple setup. These features make it particularly suitable for portable atomic sensors.

  3. A study of the relationship between recreational user-day visits and the physical and economic characteristics of Texas water impoundment areas

    E-Print Network [OSTI]

    Jones, Ronnie D

    1966-01-01T23:59:59.000Z

    ILTsy ~ QLLkeC %ltd'708 XW$@~p4. Che . ccQKSPgetds Gx KBBQp' @?oee ~ +~ 3. sx'gN ~S the RgK'9. ~ EtQS t ~ e&G, %@GC G BtM e VBAhLXX P, QQ'O~~~V~s dNXV A@ NQ 84 )J? p I& Fig. 1. --Location of Standard Metropolitan Statistical Areas of' Texas. 6 g UO...EigoX'iG~44 QQE9pSZ'2, Bono 9 'C&MQ 8'RSCG VMS ZMW$. C4'G8, 3. n@Q 8& Z QX'8@8 y Zn QQ88. ggfn CLn~~ '5hn ~&on& pnztl. e+3e~ . @Ments. on +@8 gLvav. 'ao eneh Zeeitme ea t@W'8'Q~l' y MS' ~~i@f'@3. 3?e @ho 64kkn '@8K'5 +G3. 38$'58d; Ltp' CRS sGLL Gonso...

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    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 ...

  5. Uranyl fluoride luminescence in acidic aqueous solutions

    SciTech Connect (OSTI)

    Beitz, J.V.; Williams, C.W. [Argonne National Lab., IL (United States). Chemistry Div.

    1996-08-01T23:59:59.000Z

    Luminescence emission spectra and decay rates are reported for uranyl species in acidic aqueous solutions containing HF or added NaF. The longest luminescence lifetime, 0.269 {+-} 0.006 ms, was observed from uranyl in 1 M HF + 1 M HClO{sub 4} at 296 K and decreased with increasing temperature. Based on a luminescence dynamics model that assumes equilibrium among electronically excited uranyl fluoride species and free fluoride ion, this long lived uranyl luminescence in aqueous solution is attributed primarily to UO{sub 2}F{sub 2}. Studies on the effect of added LiNO{sub 3} or Na{sub 2}WO{sub 4}{center_dot}2H{sub 2}O showed relatively weak quenching of uranyl fluoride luminescence which suggests that high sensitivity determination of the UF{sub 6} content of WF{sub 6} gas should be feasible via uranyl luminescence analysis of hydrolyzed gas samples of impure WF{sub 6}.

  6. GC/MS characterization of condensable tars in the output stream of a stirred fixed-bed gasifier

    SciTech Connect (OSTI)

    Lamey, S.C.; McCaskill, K.B.; Smith, R.R.

    1981-12-01T23:59:59.000Z

    The output stream of the stirred fixed-bed gasifier at the Morgantown Energy Technology Center was sampled for total entrained material. A major portion of the entrained material, in addition to particles, is condensable tar that is subsequently removed from the process gas by wet scrubbing. Characterization of the entrained materials, specifically the tar, is important to establish contaminant levels and to evaluate performance of downstream cleanup units. Samples of tars were collected from the process unit in a combined ice, dry ice, and liquid nitrogen sampler and stored in a refrigerator. The tar samples were then separated into asphaltene, neutral oil, tar acid, and base fractions by solvent extraction using toluene, pentane, sulfuric acid, and potassium hydroxide extraction. Characterization of the fractions obtained from these tars include IR, UV, GC, and GC/MS analysis. The mass spectrometer analysis of the various isolates shows that many individual peaks in the gas chromatograph are in fact mixtures that can be readily identified by the mass spectrometer. It was found that many of the species identified in these fractions were members of aromatic homologous series consisting of parent, mono, di, and tri substituted compounds. Compound identification was made by comparison of the data system library and standard reference spectra. This paper will discuss the instrumental approach and limitation of the GC/MS and the results of the characterization studies of entrained hydrocarbons collected from the gasifier stream.

  7. 1.0 1.5 2.0 2.5 3.0 3.5 kCounts RIC all trae4.ms

    E-Print Network [OSTI]

    O CH2OH O CHO 1.0 1.5 2.0 2.5 3.0 3.5 minutes 0 50 100 150 200 250 kCounts RIC all trae4.ms O CH2OH O CHO 1.0 1.5 2.0 2.5 3.0 3.5 minutes 0 50 100 150 200 250 kCounts RIC all trae4.ms 1.0 1.5 2.0 2.5 3.0 3.5 minutes 1.0 1.5 2.0 2.5 3.0 3.5 minutes 0 50 100 150 200 250 kCounts RIC all trae4.ms

  8. Determination of vapor liquid equilibrium for the ternary iso-propanol/atactic-polypropylene/n-heptane mixture at 105C and 140C, and the binary iso-propanol/atactic-polypropylene mixture at 85C using perturbation gas chromatography / cby Lamar Lane Joffrion 

    E-Print Network [OSTI]

    Joffrion, Lamar Lane

    1984-01-01T23:59:59.000Z

    Tg uoTquaqaz (T-u) p)aTZ (pter 'uozqzsoduroo uragsIs aqua pue aseqd ozzamEyod aqua qqtrr uoTgoezazut naqz uodn quapuadap saT&zooyarr ge urrrnyoo aqua Suts "accus 'suoTqeqsnqzad asaqg suotqeqznqzad urntzqtyTnba (y-u) asneo yyTrr aSueqo uox...&zooyaA aSeqd rruzaoyg avS uaqrr . (/e/ 'ae) = . "&r a?qa (t-u) x (~-u) azzs go sarrtqerrzsap maaqqosT uotgdsos go xtsqem = ?([ s, ?'I aqua go so&oars (y-u) x T e = ?Z (-, -u) x (y-u) azas go xzzqem Zqaquapz ('Le/ "Be) = '"?q pue ZV "?q = "r&V qeqg qons...

  9. AGR-2 irradiation test final as-run report, Rev. 1

    SciTech Connect (OSTI)

    Collin, Blaise P.

    2014-08-01T23:59:59.000Z

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities; (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing; and, (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The test contained six independently controlled and monitored capsules. Each U.S. capsule contained 12 compacts of either UCO or UO2 AGR coated fuel. No fuel particles failed during the AGR-2 irradiation. Final burnup values on a per compact basis ranged from 7.26 to 13.15% FIMA (fissions per initial heavy-metal atom) for UCO fuel, and 9.01 to 10.69% FIMA for UO2 fuel, while fast fluence values ranged from 1.94 to 3.47´1025 n/m2 (E >0.18 MeV) for UCO fuel, and from 3.05 to 3.53´1025 n/m2 (E >0.18 MeV) for UO2 fuel. Time-average volume-average (TAVA) temperatures on a capsule basis at the end of irradiation ranged from 987°C in Capsule 6 to 1296°C in Capsule 2 for UCO, and from 996 to 1062°C in UO2-fueled Capsule 3. By the end of the irradiation, all of the installed thermocouples (TCs) had failed. Fission product release-to-birth (R/B) ratios were quite low. In the UCO capsules, R/B values during the first three cycles were below 10-6 with the exception of the hotter Capsule 2, in which the R/Bs reached 2´10-6. In the UO2 capsule (Capsule 3), the R/B values during the first three cycles were below 10-7. R/B values for all following cycles are not reliable due to gas flow and cross talk issues.

  10. AGR-2 IRRADIATION TEST FINAL AS-RUN REPORT

    SciTech Connect (OSTI)

    Blaise, Collin

    2014-07-01T23:59:59.000Z

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The test contained six independently controlled and monitored capsules. Each U.S. capsule contained 12 compacts of either UCO or UO2 AGR coated fuel. No fuel particles failed during the AGR-2 irradiation. Final burnup values on a per compact basis ranged from 7.26 to 13.15% FIMA (fissions per initial heavy-metal atom) for UCO fuel, and 9.01 to 10.69% FIMA for UO2 fuel, while fast fluence values ranged from 1.94 to 3.47´1025 n/m2 (E >0.18 MeV) for UCO fuel, and from 3.05 to 3.53´1025 n/m2 (E >0.18 MeV) for UO2 fuel. Time-average volume-average (TAVA) temperatures on a capsule basis at the end of irradiation ranged from 987°C in Capsule 6 to 1296°C in Capsule 2 for UCO, and from 996 to 1062°C in UO2-fueled Capsule 3. By the end of the irradiation, all of the installed thermocouples (TCs) had failed. Fission product release-to-birth (R/B) ratios were quite low. In the UCO capsules, R/B values during the first three cycles were below 10-6 with the exception of the hotter Capsule 2, in which the R/Bs reached 2´10-6. In the UO2 capsule (Capsule 3), the R/B values during the first three cycles were below 10-7. R/B values for all following cycles are not reliable due to gas flow and cross talk issues.

  11. Geology of the Pontotoc North-Northwest area San Saba County, Texas

    E-Print Network [OSTI]

    Chauvin, Aaron Lawrence

    1962-01-01T23:59:59.000Z

    UTequneg uo qg . Iecgg9g QUGQseQlfg u'gBQUnog de@ i q8 'I' I r' 8 ~ ~ e . w ~ o e ~, s ~ i . ~ e ~~ggggg yp 1 ~, ~ ~ 0, 'I . ~ ~ 0 0 I 4 \\ 1 lk, , ~ 0 S ~ ~ 1 OggggQggQQ- gg ~ ~ ~ 5 fl 4 ~ ~ '. ' . ~ '. ; irajueegXsguag-greg ~ ~ 4, ~ ~ 4... -xoa gsam~nos a~ ~ ggyydn oueyg aqua yo query wsamqgxou a~ uo paqeaoy sy eaxe ps' qgxog-~xoH aogoguod aqua, DVHZ Sgg 5 r Apngs yo asm ~ ay yaaaas ~ spry duo e~ sg~ gym' eyuopa~ ~ Sao~' appose Imp yy~g$08 QQB SS~lgl 5$PClg QQ'f0+ Q~ '~ gpgOg g...

  12. Repellents to prevent cattle browsing of pine seedlings

    E-Print Network [OSTI]

    Duncan, Don Arlen

    1959-01-01T23:59:59.000Z

    Tm ZzaA ssA Zqyaywm. c". pqZ gso~qv ~ 'ZBTTsq=om qsmqsu 'BuTTfmzq zus Buys?ozq syqqev usqq usqqo eaeuss moTg sBomsTr Buy~aaB syqqso Zq pseuss sar~ cq. oqd: &~ssqo uo Zqyqs~~crz s~? ~o fiqTuopem sqq. puc 'eBuyqTsae Bssp go aBsquoozacT q. eaqDyu sctq...~ygi Zq paBccrsp azar' ppo~l; go sBv~aso r Zquo ~~~ cueqaoB qaz~ooB Zq;;aZozqgap ossa sax~ Bus eq. qqqaz Zq - zo uaqqyq a&as eBuZTSase or q. ZBuqe stqq go ssznoa sqq Buymg mIog Z. toquaAuy pgaTg aq, uo sB mp qyqqzu Zus Z~q, . og spam azaw suoTeTAo~ zou...

  13. Effect of Helium Accumulation on the Spent Fuel Microstructure

    SciTech Connect (OSTI)

    Ferry, Cecile [Department of Physico-chemistry, Commissariat a l'Energie Atomique, CEA-Saclay, Gif-sur-Yvette, 91191 (France); Piron, Jean-Paul [Commisariat a l'Energie Atomique, CEA - Cadarache, Saint-Paul Lez Durance, 13108 (France); Stout, Ray [Rho Beta Sigma Affaires, Livermore, CA, CA 94550 (United States)

    2007-07-01T23:59:59.000Z

    In a nuclear spent fuel repository, the aqueous rapid release of radio-activity from exposed spent fuel surfaces will depend on the pellet microstructure at the arrival time of water into the disposal container. Research performed on spent fuel evolution in a closed system has shown that the evolution of microstructure under disposal conditions should be governed by the cumulated {alpha}-decay damage and the subsequent helium behavior. The evolution of fission gas bubble characteristics under repository conditions has to be assessed. In UO{sub 2} fuels with a burnup of 47.5 GWd/t, the pressure in fission gas bubbles, including the pressure increase from {alpha}-decay helium atoms, is not expected to reach the critical bubble pressure that will cause failure, thus micro-cracking in UO{sub 2} spent fuel grains is not expected. (authors)

  14. Experimental Verification of a Cracked Fuel Mechanical Model

    SciTech Connect (OSTI)

    Williford, R. E.

    1982-12-01T23:59:59.000Z

    This report describes the results of a series of laboratory experiments conducted to independently verify a model that describes the nonlinear mechanical behavior of cracked fuel in pelletized UO{sub 2}/Zircaloy nuclear fuel rods under normal operating conditions. After a brief description of the analytical model, each experiment is discussed in detail. Experiments were conducted to verify the general behavior and numerical values for the three primary independent modelling parameters (effective crack roughness, effective gap roughness, and total crack length), and to verify the model predictions that the effective Young's moduli for cracked fuel systems were substantially less than those for solid UO{sub 2} pellets. In general, the model parameters and predictions were confirmed, and new insight was gained concerning the complexities of cracked fuel mechanics.

  15. Fuel System Compatibility Issues for Prometheus-1

    SciTech Connect (OSTI)

    DC Noe; KB Gibbard; MH Krohn

    2006-01-20T23:59:59.000Z

    Compatibility issues for the Prometheus-1 fuel system have been reviewed based upon the selection of UO{sub 2} as the reference fuel material. In particular, the potential for limiting effects due to fuel- or fission product-component (cladding, liner, spring, etc) chemical interactions and clad-liner interactions have been evaluated. For UO{sub 2}-based fuels, fuel-component interactions are not expected to significantly limit performance. However, based upon the selection of component materials, there is a potential for degradation due to fission products. In particular, a chemical liner may be necessary for niobium, tantalum, zirconium, or silicon carbide-based systems. Multiple choices exist for the configuration of a chemical liner within the cladding; there is no clear solution that eliminates all concerns over the mechanical performance of a clad/liner system. A series of tests to evaluate the performance of candidate materials in contact with real and simulated fission products is outlined.

  16. Sampling, characterization, and remote sensing of aerosols formed in the atmospheric hydrolysis of uranium hexafluoride

    SciTech Connect (OSTI)

    Bostick, W.D.; McCulla, W.H.; Pickrell, P.W.

    1984-05-01T23:59:59.000Z

    When gaseous uranium hexafluoride (UF/sub 6/) is released into the atmosphere, it rapidly reacts with ambient moisture to form an aerosol of uranyl fluoride (UO/sub 2/F/sub 2/) and hydrogen fluoride (HF). As part of our Safety Analysis program, we have performed several experimental releases of HF/sub 6/ in contained volumes in order to investigate techniques for sampling and characterizing the aerosol materials. The aggregate particle morphology and size distribution have been found to be dependent upon several conditions, including the temperature of the UF/sub 6/ at the time of its release, the relative humidity of the air into which it is released, and the elapsed time after the release. Aerosol composition and settling rate have been investigated using stationary samplers for the separate collection of UO/sub 2/F/sub 2/ and HF and via laser spectroscopic remote sensing (Mie scatter and infrared spectroscopy). 25 refs., 16 figs., 5 tabs.

  17. Electrochemical behavior of simulated debris from a severe accident using a molten salt system

    SciTech Connect (OSTI)

    Takahashi, Yuya; Nakamura, Hitoshi; Yamada, Akira; Mizuguchi, Koji; Fujita, Reiko [Toshiba Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan)

    2013-07-01T23:59:59.000Z

    In a severe nuclear accident, the fuel in the reactor may melt, forming debris, which contains a UO{sub 2}-ZrO{sub 2} stable oxide mixture and parts of the reactor, such as Zircaloy and iron components. Proper handling of the debris is a critically important issue. The debris does not have the same composition as spent fuel, and so it is impossible to apply conventional reprocessing technology directly. In this study, we successfully separated Zr and Fe from simulated debris using NaCl-KCl molten salt electrolysis, and we selectively recovered the Zr and Fe. The simulated debris was made from Zr, Fe, and CeO{sub 2}. The CeO{sub 2} was used for simulating stable UO{sub 2}-ZrO{sub 2}. With this approach, it should be possible to reduce the volume of the debris by recovering metals, which can then be treated as low level radioactive wastes.

  18. Depleted uranium hexafluoride: Waste or resource?

    SciTech Connect (OSTI)

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

    1995-07-01T23:59:59.000Z

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

  19. DU-AGG pilot plant design study

    SciTech Connect (OSTI)

    Lessing, P.A.; Gillman, H.

    1996-07-01T23:59:59.000Z

    The Idaho National Engineering Laboratory (INEL) is developing new methods to produce high-density aggregate (artificial rock) primarily consisting of depleted uranium oxide. The objective is to develop a low-cost method whereby uranium oxide powder (UO[sub 2], U[sub 3]O[sub ]8, or UO[sub 3]) can be processed to produce high-density aggregate pieces (DU-AGG) having physical properties suitable for disposal in low-level radioactive disposal facilities or for use as a component of high-density concrete used as shielding for radioactive materials. A commercial company, G-M Systems, conducted a design study for a manufacturing pilot plant to process DU-AGG. The results of that study are included and summarized in this report. Also explained are design considerations, equipment capacities, the equipment list, system operation, layout of equipment in the plant, cost estimates, and the proposed plan and schedule.

  20. AGR-2 Irradiation Test Final As-Run Report, Rev 2

    SciTech Connect (OSTI)

    Blaise Collin

    2014-08-01T23:59:59.000Z

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The test contained six independently controlled and monitored capsules. Each U.S. capsule contained 12 compacts of either UCO or UO2 AGR coated fuel. No fuel particles failed during the AGR-2 irradiation. Final burnup values on a per compact basis ranged from 7.26 to 13.15% FIMA (fissions per initial heavy-metal atom) for UCO fuel, and 9.01 to 10.69% FIMA for UO2 fuel, while fast fluence values ranged from 1.94 to 3.47´1025 n/m2 (E >0.18 MeV) for UCO fuel, and from 3.05 to 3.53´1025 n/m2 (E >0.18 MeV) for UO2 fuel. Time-average volume-average (TAVA) temperatures on a capsule basis at the end of irradiation ranged from 987°C in Capsule 6 to 1296°C in Capsule 2 for UCO, and from 996 to 1062°C in UO2-fueled Capsule 3. By the end of the irradiation, all of the installed thermocouples (TCs) had failed. Fission product release-to-birth (R/B) ratios were quite low. In the UCO capsules, R/B values during the first three cycles were below 10-6 with the exception of the hotter Capsule 2, in which the R/Bs reached 2´10-6. In the UO2 capsule (Capsule 3), the R/B values during the first three cycles were below 10-7. R/B values for all following cycles are not reliable due to gas flow and cross talk issues.

  1. Naturalistic interpersonal reactions to assertive and unassertive styles

    E-Print Network [OSTI]

    Paquette, Raymond Joseph

    1988-01-01T23:59:59.000Z

    sinai awaJ)xa jo asneoaq pa&oaias Ai[ensn os(e aJa~ suogen(ena aug 6uiqew sgoa jqns auj. uogJasse jo s(ana[ &ua~ajjrp Ran 6ugeJgsuowap s(apow qgie sauaos pake(d a[oJ gJous paztlgn peq qojeasaJ sno[naJd aqi aa&Jasse aug uo uo[gjasse jo )oedwl aui... weeks ago, then failed to return them at the next class, thus forcing you to take notes on scrap paper. Now he/she is asking to borrow your notes again. Suppose that the person who borrowed your notes were someone you had only met in class and did...

  2. Simulation of the thermodynamic properties of organic extraction solutions

    SciTech Connect (OSTI)

    Kolker, A.R.

    1986-05-01T23:59:59.000Z

    A method is proposed for the simulation of the activity coefficients of the components, the excess volume, the heat of mixing, and other excess thermodynamic functions of organic extraction solutions. The method is based on a search in an assigned region for parameters of the NRTL equations of local composition for which the state of the solution satisfies the requirements of chemical thermodynamics, as well as the assigned recovery criteria. The following binary systems of the solvent-extractant, and solvent-solvate types have been simulated according to the program developed on an ES-1033 computer: C6H/sub 14/-TBP, CHC1/sub 3/-TBP, CC1/sub 4/-TBP, UO/sub 2/(NO/sub 3/)/sub 2/ X 2TBP-TBP, and CC1/sub 4/-UO/sub 2/(NO/sub 3/)/sub 2/ X 2TBP.

  3. Method for fluorination of uranium oxide

    DOE Patents [OSTI]

    Petit, George S. (Oak Ridge, TN)

    1987-01-01T23:59:59.000Z

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

  4. Synthesis of triglyceride by the intestinal mucosa

    E-Print Network [OSTI]

    Buell, George Christopher

    1958-01-01T23:59:59.000Z

    FE CT OF A MU CO SA L HO MO GE NA TE PR EP AR ED IN 92$ GL YC ER OL ON scuO! vO i?I C\\ivOm oIT\\ m 00rnrn o[>.rn QMo lJ-qQ)UOaoW W!coO ? CO...l i b r a r y A & M COLLEGE OF TEXAS A&MCOLAEA GF CTEXS&1LTE9L 5& COL EMCLACEM8S VI1GA8 8 9.PPrecuc.so 5f XLGTXL 1OTEACGlOLT 5ILSS Ayid.ccr- cs c3r Xeu-yucr A23ssp sa c3r 8te.2ypcyeup uo- Vr23uo.2up 1spprtr sa CrnuP .o Duec.up aypa...

  5. Measurement of the ratio [B(D(0)?K*(?)e(+)?e)] / [B(D(0)?K(?)e(+)?e)

    E-Print Network [OSTI]

    Baringer, Philip S.

    1991-12-01T23:59:59.000Z

    as a muon increases from 0.8%%uo at 1.4 GeV/c to 1.4%%uo at 2.0 GeV, and stays constant beyond. III. DETECTION OF D ~K e+v, D 's are required to be decay products of D*+'s from the reaction D*+~D m+. D*+ candidates are formed from three... and transverse polarizations [14]. We have checked our background estimates by using M(Ksvr )(Gev) FIG. 2. The histogram is the Kzm candidate mass for the decay mode D ~K* e+v, . The solid line is a fit to the data using a Breit-Wigner line shape for the signal...

  6. Feasibility Study of MOX Fuel Online Burnup Analysis

    SciTech Connect (OSTI)

    Dennis, M.L.; Usman, S. [University of Missouri-Rolla, 222 Fulton Hall, 1870 Miner Circle, Rolla, MO 65409-0170 (United States)

    2006-07-01T23:59:59.000Z

    This research is an extension of well established Non-Destructive Analysis of UO fuel using gamma spectroscopy of Cs-137 and other related isotopes. Given the performance similarities between UO fuel and MOX fuel, investigations are underway to develop similar correlation for MOX. MOX fuel burnup and decay simulations are being performed using ORIGEN-ARP (Oak Ridge Isotope Generation and Depletion Code - Automatic Rapid Processing). Simulation results are being analyzed and will be used to determine performance specifications of a detection system for field applications. Analysis of isotopic activity from irradiated fuel will be used to develop correlations to determine burn-up and Plutonium content of MOX fuel. These results will be particularly useful in view of the recent interest in MOX fuel. (authors)

  7. A view of treatment process of melted nuclear fuel on a severe accident plant using a molten salt system

    SciTech Connect (OSTI)

    Fujita, R.; Takahashi, Y.; Nakamura, H.; Mizuguchi, K. [Power and Industrial Research and Development Center, Toshiba Corporation Power Systems Company, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan); Oomori, T. [Chemical System Design and Engineering Department, Toshiba Corporation Power Systems Company, 8 Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan)

    2013-07-01T23:59:59.000Z

    At severe accident such as Fukushima Daiichi Nuclear Power Plant Accident, the nuclear fuels in the reactor would melt and form debris which contains stable UO2-ZrO2 mixture corium and parts of vessel such as zircaloy and iron component. The requirements for solution of issues are below; -) the reasonable treatment process of the debris should be simple and in-situ in Fukushima Daiichi power plant, -) the desirable treatment process is to take out UO{sub 2} and PuO{sub 2} or metallic U and TRU metal, and dispose other fission products as high level radioactive waste; and -) the candidate of treatment process should generate the smallest secondary waste. Pyro-process has advantages to treat the debris because of the high solubility of the debris and its total process feasibility. Toshiba proposes a new pyro-process in molten salts using electrolysing Zr before debris fuel being treated.

  8. High-harmonic XUV source for time- and angle-resolved photoemission spectroscopy

    SciTech Connect (OSTI)

    Dakovski, Georgi L [Los Alamos National Laboratory; Li, Yinwan [Los Alamos National Laboratory; Durakiewicz, Tomasz [Los Alamos National Laboratory; Rodriguez, George [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    We present a laser-based apparatus for visible pump/XUV probe time- and angle-resolved photoemission spectroscopy (TRARPES) utilizing high-harmonic generation from a noble gas. Femtosecond temporal resolution for each selected harmonic is achieved by using a time-delay-compensated monochromator (TCM). The source has been used to obtain photoemission spectra from insulators (UO{sub 2}) and ultrafast pump/probe processes in semiconductors (GaAs).

  9. Head-end process for the reprocessing of HTGR spent fuel

    SciTech Connect (OSTI)

    Chen, J.; Wen, M. [Institute of Nuclear and New Energy Technology, Tsinghua University, Bejing 10084 (China)

    2013-07-01T23:59:59.000Z

    The reprocessing of HTGR spent fuels is in favor of the sustainable development of nuclear energy to realize the maximal use of nuclear resource and the minimum disposal of nuclear waste. The head-end of HTGR spent fuels reprocessing is different from that of the LWR spent fuels reprocessing because of the difference of spent fuel structure. The dismantling of the graphite spent fuel element and the highly effective dissolution of fuel kernel is the most difficult process in the head end of the reprocessing. Recently, some work on the head-end has been done in China. First, the electrochemical method with nitrate salt as electrolyte was studied to disintegrate the graphite matrix from HTGR fuel elements and release the coated fuel particles, to provide an option for the head-end technology of reprocessing. The results show that the graphite matrix can be effectively separated from the coated particle without any damage to the SiC layer. Secondly, the microwave-assisted heating was applied to dissolve the UO{sub 2} kernel from the crashed coated fuel particles. The ceramic UO{sub 2} as the solute has a good ability to absorb the microwave energy. The results of UO{sub 2} kernel dissolution from crushed coated particles by microwave heating show that the total dissolution percentage of UO{sub 2} is more than 99.99% after 3 times cross-flow dissolution with the following parameters: 8 mol/L HNO{sub 3}, temperature 100 Celsius degrees, initial ratio of solid to liquid 1.2 g/ml. (authors)

  10. Magnetic resonance as a structural probe of a uranium (VI) sol-gel process

    SciTech Connect (OSTI)

    King, C.M.; Thompson, M.C.; Buchanan, B.R. (Westinghouse Savannah River Co., Aiken, SC (United States)); King, R.B. (Georgia Univ., Athens, GA (United States). Dept. of Chemistry); Garber, A.R. (South Carolina Univ., Columbia, SC (United States). Dept. of Chemistry)

    1989-01-01T23:59:59.000Z

    NMR investigations on the ORNL process for sol-gel synthesis of microspherical nuclear fuel (UO{sub 2}), has been useful in sorting out the chemical mechanism in the sol-gel steps. {sup 13}C, {sup 15}N, and {sup 1}H NMR studies on the HMTA gelation agent (Hexamethylene tetramine, C{sub 6}H{sub l2}N{sub 4}) has revealed near quantitative stability of this adamantane-like compound in the sol-Gel process, contrary to its historical role as an ammonia source for gelation from the worldwide technical literature. {sub 17}0 NMR of uranyl (UO{sub 2}{sup ++}) hydrolysis fragments produced in colloidal sols has revealed the selective formation of a uranyl trimer, ((UO{sub 2}){sub 3}({mu}{sub 3}-O)({mu}{sub 2}-OH){sub 3}){sup +}, induced by basic hydrolysis with the HMTA gelation agent. Spectroscopic results show that trimer condensation occurs during sol-gel processing leading to layered polyanionic hydrous uranium oxides in which HMTAH{sup +} is occluded as an intercalation'' cation. Subsequent sol-gel processing of microspheres by ammonia washing results in in-situ ion exchange and formation of a layered hydrous ammonium uranate with a proposed structural formula of (NH{sub 4}){sub 2}((UO{sub 2}){sub 8}O{sub 4}(OH){sub 10}) {center dot} 8H{sub 2}0. This compound is the precursor to sintered U0{sub 2} ceramic fuel.

  11. Magnetic resonance as a structural probe of a uranium (VI) sol-gel process

    SciTech Connect (OSTI)

    King, C.M.; Thompson, M.C.; Buchanan, B.R. [Westinghouse Savannah River Co., Aiken, SC (United States); King, R.B. [Georgia Univ., Athens, GA (United States). Dept. of Chemistry; Garber, A.R. [South Carolina Univ., Columbia, SC (United States). Dept. of Chemistry

    1989-12-31T23:59:59.000Z

    NMR investigations on the ORNL process for sol-gel synthesis of microspherical nuclear fuel (UO{sub 2}), has been useful in sorting out the chemical mechanism in the sol-gel steps. {sup 13}C, {sup 15}N, and {sup 1}H NMR studies on the HMTA gelation agent (Hexamethylene tetramine, C{sub 6}H{sub l2}N{sub 4}) has revealed near quantitative stability of this adamantane-like compound in the sol-Gel process, contrary to its historical role as an ammonia source for gelation from the worldwide technical literature. {sub 17}0 NMR of uranyl (UO{sub 2}{sup ++}) hydrolysis fragments produced in colloidal sols has revealed the selective formation of a uranyl trimer, [(UO{sub 2}){sub 3}({mu}{sub 3}-O)({mu}{sub 2}-OH){sub 3}]{sup +}, induced by basic hydrolysis with the HMTA gelation agent. Spectroscopic results show that trimer condensation occurs during sol-gel processing leading to layered polyanionic hydrous uranium oxides in which HMTAH{sup +} is occluded as an ``intercalation`` cation. Subsequent sol-gel processing of microspheres by ammonia washing results in in-situ ion exchange and formation of a layered hydrous ammonium uranate with a proposed structural formula of (NH{sub 4}){sub 2}[(UO{sub 2}){sub 8}O{sub 4}(OH){sub 10}] {center_dot} 8H{sub 2}0. This compound is the precursor to sintered U0{sub 2} ceramic fuel.

  12. Use of Savannah River Site facilities for blend down of highly enriched uranium

    SciTech Connect (OSTI)

    Bickford, W.E.; McKibben, J.M.

    1994-02-01T23:59:59.000Z

    Westinghouse Savannah River Company was asked to assess the use of existing Savannah River Site (SRS) facilities for the conversion of highly enriched uranium (HEU) to low enriched uranium (LEU). The purpose was to eliminate the weapons potential for such material. Blending HEU with existing supplies of depleted uranium (DU) would produce material with less than 5% U-235 content for use in commercial nuclear reactors. The request indicated that as much as 500 to 1,000 MT of HEU would be available for conversion over a 20-year period. Existing facilities at the SRS are capable of producing LEU in the form of uranium trioxide (UO{sub 3}) powder, uranyl nitrate [UO{sub 2}(NO{sub 3}){sub 2}] solution, or metal. Additional processing, and additional facilities, would be required to convert the LEU to uranium dioxide (UO{sub 2}) or uranium hexafluoride (UF{sub 3}), the normal inputs for commercial fuel fabrication. This study`s scope does not include the cost for new conversion facilities. However, the low estimated cost per kilogram of blending HEU to LEU in SRS facilities indicates that even with fees for any additional conversion to UO{sub 2} or UF{sub 6}, blend-down would still provide a product significantly below the spot market price for LEU from traditional enrichment services. The body of the report develops a number of possible facility/process combinations for SRS. The primary conclusion of this study is that SRS has facilities available that are capable of satisfying the goals of a national program to blend HEU to below 5% U-235. This preliminary assessment concludes that several facility/process options appear cost-effective. Finally, SRS is a secure DOE site with all requisite security and safeguard programs, personnel skills, nuclear criticality safety controls, accountability programs, and supporting infrastructure to handle large quantities of special nuclear materials (SNM).

  13. TREKiSM Issue 43

    E-Print Network [OSTI]

    1985-01-01T23:59:59.000Z

    .JO 'snJ02V"~ IIAaQ GmT IS uO lqau9Q A'~I 04. U&A& o. SnolAqo oq Pln04s { y ·Z ' I -78- *******Reader Survey ******* {c We realize that you new folk have Just sent one of these suckers, {c but would appreciate your feedback anyway, as we've added some...

  14. Multilevel modeling of social interactions and mood in lonely and socially connected individuals: The MacArthur Social Neuroscience Studies

    E-Print Network [OSTI]

    Hawkley, L. C.; Preacher, K. J.; Cacioppo, J. T.

    2007-01-01T23:59:59.000Z

    SUSIl asoqr aM '(OOOZ ''le ta qseqsel) NIM'lhtr puu (0002 'uop8uo3 4 '3uoaq3 'qsnq-uapneg '>lfrg) rutt se qrns sa8e>pud 611141 parpJrpap puu (0'ZI) SSdS pue (fS'S) feUStf ,o suorsral raivrau Surpnpur 'sa8eped aremryos Ie)rtsrlets lera^as ur PaPnPur 3rE sla...

  15. Universal fuel basket for use with an improved oxide reduction vessel and electrorefiner vessel

    DOE Patents [OSTI]

    Herrmann, Steven D. (Idaho Falls, ID); Mariani, Robert D. (Idaho Falls, ID)

    2002-01-01T23:59:59.000Z

    A basket, for use in the reduction of UO.sub.2 to uranium metal and in the electrorefining of uranium metal, having a continuous annulus between inner and outer perforated cylindrical walls, with a screen adjacent to each wall. A substantially solid bottom and top plate enclose the continuous annulus defining a fuel bed. A plurality of scrapers are mounted adjacent to the outer wall extending longitudinally thereof, and there is a mechanism enabling the basket to be transported remotely.

  16. Nuclear carrier business volume projections, 1980-2000

    SciTech Connect (OSTI)

    Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

    1980-05-01T23:59:59.000Z

    The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U/sub 3/O/sub 8/); natural, enriched and reprocessed uranium hexafluoride (UF/sub 6/); uranium dioxide powder (UO/sub 2/); plutonium dioxide powder (PuO/sub 2/); fresh UO/sub 2/ and mixed oxide (MOX) fuel; spent UO/sub 2/ fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO/sub 2/ fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991.

  17. Characterization Methodology for Decommissioning Low and Intermediate Level Fissile Nuclide Contaminated Buried Soils and Process Piping Using Photon Counting

    E-Print Network [OSTI]

    Pritchard, Megan L

    2014-05-03T23:59:59.000Z

    Tellurium CFR Code of Federal Regulations Ci Curie cm Centimeter cpm Counts per Minute CZT Cadmium Zinc Telluride D&D Decontamination and Decommissioning DU Depleted Uranium EAF European Activation File ENDF Evaluated Nuclear Data... an abundance of depleted uranium ( ? 0.96 wt. % 235U in UO2), thorium, and radium. These nuclides emit gammas and produce high count rates in a windowed NaI. Detection of these nuclides is pertinent for waste management and radiological exposure purposes...

  18. Draft report on melt point as a function of composition for urania-based systems

    SciTech Connect (OSTI)

    Valdez, James A [Los Alamos National Laboratory; Byler, Darrin D [Los Alamos National Laboratory

    2012-06-08T23:59:59.000Z

    This report documents the testing of a urania (UO{sub 2.00}) sample as a baseline and the attempt to determine the melt point associated with 4 compositions of urania-ceria and urania-neodymia pseudo binaries provided by ORNL, with compositions of 95/5, and 80/20 and of (U/Ce)O{sub 2.00} and (U/Nd)O{sub 2.00} in the newly developed ceramic melt point determination system. A redesign of the system using parts fabricated from tungsten was undertaken in order to help prevent contamination and tungsten carbide formation in the crucibles. The previously developed system employed mostly graphite parts that were shown to react with the sample containment black-body crucible leading to unstable temperature readings and crucible failure, thus the redesign. Measured melt point values of UO{sub 2.00} and U{sub 0.95}Ce{sub 0.05}O{sub 2.00}, U{sub 0.80}Ce{sub 0.20}O{sub 2.00}, U{sub 0.95}Nd{sub 0.05}O{sub 2.00} and U{sub 0.80}Nd{sub 0.20}O{sub 2.00} were measured using a 2-color pyrometer. The value measured for UO{sub 2.00} was consistent with the published accepted value 2845 C {+-} 25 C, although a wide range of values has been published by researchers and will be discussed later in the text. For comparison, values obtained from a published binary phase diagram of UO{sub 2}-Nd{sub 2}O{sub 3} were used for comparison with our measure values. No literature melt point values for comparison with the measurements performed in this study were found for (U/Ce)O{sub 2.00} in our stoichiometry range.

  19. COMBINED SOCIOLOGY Ph.D. / POPULATION HEALTH M.S. OR MINOR OPTIONS OPTION I--M.S. in Population Health with Integrated Sociology Dissertation/Population Health

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Health with Integrated Sociology Dissertation/Population Health Thesis (33 credit minimum) Core Courses complete a Ph.D. dissertation that will also satisfy the master's program thesis requirements (including on the Ph.D. Dissertation. That faculty member must serve as the MS advisor and, in that capacity, sign

  20. The MS-Q Force Field for Clay Minerals: Application to Oil Production Sungu Hwang, Mario Blanco, Ersan Demiralp, Tahir Cagin, and William A. Goddard, III*

    E-Print Network [OSTI]

    Çagin, Tahir

    The MS-Q Force Field for Clay Minerals: Application to Oil Production Sungu Hwang, Mario Blanco inhibitor oil production chemical. 1. Introduction Molecular modeling studies of clay and related zeolite of water, hydrocarbons, and polar organic compounds such as oil field production chemicals on clay mineral