National Library of Energy BETA

Sample records for depleted uf6 mailing

  1. NGSI: IAEA Verification of UF6 Cylinders

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2012-06-05

    The International Atomic Energy Agency (IAEA) is often ignorant of the location of declared, uranium hexafluoride (UF6) cylinders following verification, because cylinders are not typically tracked onsite or off. This paper will assess various methods the IAEA uses to verify cylinder gross defects, and how the task could be ameliorated through the use of improved identification and monitoring. The assessment will be restricted to current verification methods together with one that has been applied on a trial basis—short-notice random inspections coupled with mailbox declarations. This paper is part of the NNSA Office of Nonproliferation and International Security’s Next Generation Safeguards Initiative (NGSI) program to investigate the concept of a global monitoring scheme that uniquely identifies and tracks UF6 cylinders.

  2. Method and apparatus for measuring enrichment of UF6

    DOE Patents [OSTI]

    Hill, Thomas Roy; Ianakiev, Kiril Dimitrov

    2011-06-07

    A system and method are disclosed for determining the enrichment of .sup.235U in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which are directed at a container test zone containing a sample of UF6. A detector placed behind the container test zone then detects and counts the X-rays which pass through the container and the UF6. In order to determine the portion of the attenuation due to the UF6 gas alone, this count rate may then be compared to a calibration count rate of X-rays passing through a calibration test zone which contains a vacuum, the test zone having experienced substantially similar environmental conditions as the actual test zone. Alternatively, X-rays of two differing energy levels may be alternately directed at the container, where either the container or the UF6 has a high sensitivity to the difference in the energy levels, and the other having a low sensitivity.

  3. Thermo-mechanical study of bare 48Y UF6 containers exposed to the regulatory fire environment.

    SciTech Connect (OSTI)

    Ammerman, Douglas James; Lopez, Carlos; Morrow, Charles; Korbmacher, Tim; Charette, Marc-Andre

    2010-11-01

    Most of the regulatory agencies world-wide require that containers used for the transportation of natural UF6 and depleted UF6 must survive a fully-engulfing fire environment for 30 minutes as described in 10CFR71 and in TS-R-1. The primary objective of this project is to examine the thermo-mechanical performance of 48Y transportation cylinders when exposed to the regulatory hypothetical fire environment without the thermal protection that is currently used for shipments in those countries where required. Several studies have been performed in which UF6 cylinders have been analyzed to determine if the thermal protection currently used on UF6 cylinders of type 48Y is necessary for transport. However, none of them could clearly confirm neither the survival nor the failure of the 48Y cylinder when exposed to the regulatory fire environment without the additional thermal protection. A consortium of five companies that move UF6 is interested in determining if 48Y cylinders can be shipped without the thermal protection that is currently used. Sandia National Laboratories has outlined a comprehensive testing and analysis project to determine if these shipping cylinders are capable of withstanding the regulatory thermal environment without additional thermal protection. Sandia-developed coupled physics codes will be used for the analyses that are planned. A series of destructive and non-destructive tests will be performed to acquire the necessary material and behavior information to benchmark the models and to answer the question about the ability of these containers to survive the fire environment. Both the testing and the analysis phases of this project will consider the state of UF6 under thermal and pressure loads as well as the weakening of the steel container due to the thermal load. Experiments with UF6 are also planned to collect temperature- and pressure-dependent thermophysical properties of this material.

  4. Neutron spectrometry for UF6 enrichment verification in storage cylinders

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

    Mengesha, Wondwosen; Kiff, Scott D.

    2015-01-29

    Verification of declared UF6 enrichment and mass in storage cylinders is of great interest in nuclear material nonproliferation. Nondestructive assay (NDA) techniques are commonly used for safeguards inspections to ensure accountancy of declared nuclear materials. Common NDA techniques used include gamma-ray spectrometry and both passive and active neutron measurements. In the present study, neutron spectrometry was investigated for verification of UF6 enrichment in 30B storage cylinders based on an unattended and passive measurement approach. MCNP5 and Geant4 simulated neutron spectra, for selected UF6 enrichments and filling profiles, were used in the investigation. The simulated neutron spectra were analyzed using principalmore » component analysis (PCA). The PCA technique is a well-established technique and has a wide area of application including feature analysis, outlier detection, and gamma-ray spectral analysis. Results obtained demonstrate that neutron spectrometry supported by spectral feature analysis has potential for assaying UF6 enrichment in storage cylinders. The results from the present study also showed that difficulties associated with the UF6 filling profile and observed in other unattended passive neutron measurements can possibly be overcome using the approach presented.« less

  5. Two photon spectroscopy of UF6 in the near ultraviolet

    SciTech Connect (OSTI)

    Bernstein, E.R.; Kennedy, P.M.

    1981-03-01

    The two photon excited fluorescence excitation spectrum of UF6 was observed in the region 410 to 315 nm. The spectrum was virtually indistinguishable from the one photon absorption in this region. No vibronic structure was observed in absorption or dispersed emission. These data indicate a high density of u and g states for UF6 in this energy range and facile photochemical decomposition. Emission intensity was found to be proportional to laser power to the 3.0 to 3.6 power.

  6. Integrating UF6 Cylinder RF Tracking With Continuous Load Cell Monitoring for Verifying Declared UF6 Feed and Withdrawal Operations Verifying Declared UF6 Feed and Withdrawal Operations

    SciTech Connect (OSTI)

    Krichinsky, Alan M; Miller, Paul; Pickett, Chris A; Richardson, Dave; Rowe, Nathan C; Whitaker, J Michael; Younkin, James R

    2009-01-01

    Oak Ridge National Laboratory is demonstrating the integration of UF6 cylinder tracking, using RF technology, with continuous load cell monitoring (CLCM) at mock UF6 feed and withdrawal (F&W) stations. CLCM and cylinder tracking are two of several continuous-monitoring technologies that show promise in providing integrated safeguards of F&W operations at enrichment plants. Integrating different monitoring technologies allows advanced, automated event processing to screen innocuous events thereby minimizing false alerts to independent inspectors. Traditionally, international inspectors rely on batch verification of material inputs and outputs derived from operator declarations and periodic on-site inspections at uranium enrichment plants or other nuclear processing facilities. Continuously monitoring F&W activities between inspections while providing filtered alerts of significant operational events will substantially increase the amount of valuable information available to inspectors thereby promising to enhance the effectiveness of safeguards and to improve efficiency in conducting on-site inspections especially at large plants for ensuring that all operations are declared.

  7. Onsite Gaseous Centrifuge Enrichment Plant UF6 Cylinder Destructive Analysis

    SciTech Connect (OSTI)

    Anheier, Norman C.; Cannon, Bret D.; Qiao, Hong; Carter, Jennifer C.; McNamara, Bruce K.; O'Hara, Matthew J.; Phillips, Jon R.; Curtis, Michael M.

    2012-07-17

    The IAEA safeguards approach for gaseous centrifuge enrichment plants (GCEPs) includes measurements of gross, partial, and bias defects in a statistical sampling plan. These safeguard methods consist principally of mass and enrichment nondestructive assay (NDA) verification. Destructive assay (DA) samples are collected from a limited number of cylinders for high precision offsite mass spectrometer analysis. DA is typically used to quantify bias defects in the GCEP material balance. Under current safeguards measures, the operator collects a DA sample from a sample tap following homogenization. The sample is collected in a small UF6 sample bottle, then sealed and shipped under IAEA chain of custody to an offsite analytical laboratory. Current practice is expensive and resource intensive. We propose a new and novel approach for performing onsite gaseous UF6 DA analysis that provides rapid and accurate assessment of enrichment bias defects. DA samples are collected using a custom sampling device attached to a conventional sample tap. A few micrograms of gaseous UF6 is chemically adsorbed onto a sampling coupon in a matter of minutes. The collected DA sample is then analyzed onsite using Laser Ablation Absorption Ratio Spectrometry-Destructive Assay (LAARS-DA). DA results are determined in a matter of minutes at sufficient accuracy to support reliable bias defect conclusions, while greatly reducing DA sample volume, analysis time, and cost.

  8. Advancements of the Hybrid Method UF6 Container Inspection System

    SciTech Connect (OSTI)

    Mace, Emily K.; Orton, Christopher R.; Jordan, David V.; McDonald, Benjamin S.; Smith, Leon E.

    2011-07-17

    Safeguards inspectors currently visit uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are performed with handheld high-resolution detectors on a limited number of cylinders taken to be representative of the plant’s cylinder inventory. These enrichment assay methods interrogate only a small fraction of the total cylinder volume, and are time-consuming and expensive to execute. Pacific Northwest National Laboratory (PNNL) is developing an automated UF6 cylinder verification station concept based on the combined collection of traditional enrichment-meter data (186 keV photons from 235U) and non-traditional, neutron-induced, high-energy gamma-ray signatures (3-8 MeV) with an array of collimated, medium-resolution scintillators. Previous work at PNNL (2010) demonstrated proof-of-principle that this hybrid method yields accurate, full-volume assay of the cylinder enrichment, reduces systematic errors when compared to several other enrichment assay methods, and provides simplified instrumentation and algorithms suitable for long-term, unattended operations. This system aims to increase the number of inspected cylinders at higher accuracy and with lower cost than when compared to inspectors with hand-held instruments. Several measurement campaigns of 30B cylinder populations and a refined MCNP model will be reported. The MCNP model consists of per-gram basis vectors for the different uranium isotopes and several fill geometries, enabling fast generation of any UF6 enrichment level and multiple configurations. The refined model was used to optimize collimator design and detector configuration for the hybrid method. In addition, a new field prototype based on model results was utilized in a set of field measurements.

  9. Enrichment Assay Methods for a UF6 Cylinder Verification Station

    SciTech Connect (OSTI)

    Smith, Leon E.; Jordan, David V.; Misner, Alex C.; Mace, Emily K.; Orton, Christopher R.

    2010-11-30

    International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders taken to be representative of the facility’s entire cylinder inventory. These enrichment assay methods interrogate only a small fraction of the total cylinder volume, and are time-consuming and expensive to execute for inspectors. Pacific Northwest National Laboratory (PNNL) is developing an unattended measurement system capable of automated enrichment measurements over the full volume of Type 30B and Type 48 cylinders. This Integrated Cylinder Verification System (ICVS) could be located at key measurement points to positively identify each cylinder, measure its mass and enrichment, store the collected data in a secure database, and maintain continuity of knowledge on measured cylinders until IAEA inspector arrival. The focus of this paper is the development of nondestructive assay (NDA) methods that combine “traditional” enrichment signatures (e.g. 185-keV emission from U-235) and more-penetrating “non-traditional” signatures (e.g. high-energy neutron-induced gamma rays spawned primarily from U-234 alpha emission) collected by medium-resolution gamma-ray spectrometers (i.e. sodium iodide or lanthanum bromide). The potential of these NDA methods for the automated assay of feed, tail and product cylinders is explored through MCNP modeling and with field measurements on a cylinder population ranging from 0.2% to 5% in U-235 enrichment.

  10. HGSYSTEMUF6. Model for Simulating Dispersion due to Atmospheric Release of UF6

    SciTech Connect (OSTI)

    Hanna, G; Chang, J.C.; Zhang, J.X.; Bloom, S.G.; Goode, W.D. Jr; Lombardi, D.A.; Yambert, M.W.

    1998-08-01

    HGSYSTEMUF6 is a suite of models designed for use in estimating consequences associated with accidental, atmospheric release of Uranium Hexafluoride (UF6) and its reaction products, namely Hydrogen Fluoride (HF), and other non-reactive contaminants which are either negatively, neutrally, or positively buoyant. It is based on HGSYSTEM Version 3.0 of Shell Research LTD., and contains specific algorithms for the treatment of UF6 chemistry and thermodynamics. HGSYSTEMUF6 contains algorithms for the treatment of dense gases, dry and wet deposition, effects due to the presence of buildings (canyon and wake), plume lift-off, and the effects of complex terrain. The models components of the suite include (1) AEROPLUME/RK, used to model near-field dispersion from pressurized two-phase jet releases of UF6 and its reaction products, (2) HEGADAS/UF6 for simulating dense, ground based release of UF6, (3) PGPLUME for simulation of passive, neutrally buoyant plumes (4) UF6Mixer for modeling warm, potentially reactive, ground-level releases of UF6 from buildings, and (5) WAKE, used to model elevated and ground-level releases into building wake cavities of non-reactive plumes that are either neutrally or positively buoyant.

  11. Model for Simulating Dispersion due to Atmospheric Release of UF6

    Energy Science and Technology Software Center (OSTI)

    1997-01-01

    HGSYSTEMUF6 is a suite of models designed for use in estimating consequences associated with accidental, atmospheric release of Uranium Hexafluoride (UF6) and its reaction products, namely Hydrogen Fluoride (HF), and other non-reactive contaminants which are either negatively, neutrally, or positively buoyant. It is based on HGSYSTEM Version 3.0 of Shell Research LTD., and contains specific algorithms for the treatment of UF6 chemistry and thermodynamics. HGSYSTEMUF6 contains algorithms for the treatment of dense gases, dry andmore » wet deposition, effects due to the presence of buildings (canyon and wake), plume lift-off, and the effects of complex terrain. The models components of the suite include (1) AEROPLUME/RK, used to model near-field dispersion from pressurized two-phase jet releases of UF6 and its reaction products, (2) HEGADAS/UF6 for simulating dense, ground based release of UF6, (3) PGPLUME for simulation of passive, neutrally buoyant plumes (4) UF6Mixer for modeling warm, potentially reactive, ground-level releases of UF6 from buildings, and (5) WAKE, used to model elevated and ground-level releases into building wake cavities of non-reactive plumes that are either neutrally or positively buoyant.« less

  12. Automated UF6 Cylinder Enrichment Assay: Status of the Hybrid Enrichment Verification Array (HEVA) Project: POTAS Phase II

    SciTech Connect (OSTI)

    Jordan, David V.; Orton, Christopher R.; Mace, Emily K.; McDonald, Benjamin S.; Kulisek, Jonathan A.; Smith, Leon E.

    2012-06-01

    Pacific Northwest National Laboratory (PNNL) intends to automate the UF6 cylinder nondestructive assay (NDA) verification currently performed by the International Atomic Energy Agency (IAEA) at enrichment plants. PNNL is proposing the installation of a portal monitor at a key measurement point to positively identify each cylinder, measure its mass and enrichment, store the data along with operator inputs in a secure database, and maintain continuity of knowledge on measured cylinders until inspector arrival. This report summarizes the status of the research and development of an enrichment assay methodology supporting the cylinder verification concept. The enrichment assay approach exploits a hybrid of two passively-detected ionizing-radiation signatures: the traditional enrichment meter signature (186-keV photon peak area) and a non-traditional signature, manifested in the high-energy (3 to 8 MeV) gamma-ray continuum, generated by neutron emission from UF6. PNNL has designed, fabricated, and field-tested several prototype assay sensor packages in an effort to demonstrate proof-of-principle for the hybrid assay approach, quantify the expected assay precision for various categories of cylinder contents, and assess the potential for unsupervised deployment of the technology in a portal-monitor form factor. We refer to recent sensor-package prototypes as the Hybrid Enrichment Verification Array (HEVA). The report provides an overview of the assay signatures and summarizes the results of several HEVA field measurement campaigns on populations of Type 30B UF6 cylinders containing low-enriched uranium (LEU), natural uranium (NU), and depleted uranium (DU). Approaches to performance optimization of the assay technique via radiation transport modeling are briefly described, as are spectroscopic and data-analysis algorithms.

  13. DEVELOPMENT OF A PORTAL MONITOR FOR UF6 CYLINDER VERIFICATION

    SciTech Connect (OSTI)

    Smith, Leon E.; Curtis, Michael M.; Shaver, Mark W.; Benz, Jacob M.; Misner, Alex C.; Mace, Emily K.; Jordan, David V.; Noss, Daniel; Ford, Herbert

    2009-10-06

    International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are performed with handheld high-resolution sensors on a sampling of cylinders taken to be representative of the facility’s operations. As additional enrichment plans come online to support the expansion of nuclear power, reducing person-days of inspection will take on greater importance. Pacific Northwest National Laboratory (PNNL) is developing a concept to automate the verification of enrichment plant cylinders to enable 100% product-cylinder verification and potentially, mass-balance calculations on the facility as a whole (by also measuring feed and tails cylinders). The Automated Cylinder Enrichment Verification System (ACEVS) would be located at key measurement points and will positively identify each cylinder, measure its mass and enrichment, store the data along with operator inputs in a secure database, and maintain continuity of knowledge on measured cylinders until IAEA inspector arrival. Given the potential for reduced inspector presence, the operational and manpower-reduction benefits of the portal concept are clear. However, it is necessary to assess whether the cylinder portal concept can meet, or potentially improve upon, today’s U-235 enrichment assay performance. PNNL’s ACEVS concept utilizes sensors that could be operated in an unattended mode: moderated He-3 neutron detectors and large NaI(Tl) scintillators for gamma-ray spectroscopy. The medium-resolution NaI(Tl) scintillators are a sacrifice in energy resolution but do provide high collection efficiency for signatures above 1 MeV. The He-3/NaI sensor combination allows the exploitation of additional, more-penetrating signatures than those currently utilized: Neutrons produced from F-19(?,n) reactions (spawned primarily from U-234 alpha emission) and high-energy gamma rays (extending up to 10 MeV) induced by neutrons interacting in the steel cylinder. These signatures are indirect measures of U-235 that require a relatively stable U-234/U-235 ratio in the product material in order to be useful. The hypothesis of this work is that the U-234/U-235 ratio is sufficiently constant, for the specific facility where the automated system is installed, to rely on neutron and high-energy gamma-ray signatures for indirect measurement of U-235. Further, these highly penetrating signatures can be combined with a modified form of NaI-based 185-keV enrichment measurements to meet target uncertainties for the verification of product cylinders, with the additional benefits of full-volume assay of the cylinder and 100% product-cylinder verification (as opposed to today’s sampling-based approach). This paper focuses on the enrichment measurement aspects of the ACEVS concept: neutron and high-energy gamma-ray signatures, the radiation sensors designed to collect those signatures, and proof-of-principle cylinder measurements and analysis. Preliminary analysis indicates that an automated cylinder verification approach has the potential to meet target uncertainty values for 30B products cylinders (5%), assuming ore-based enrichment feed and a facility-specific calibration. Also described is the additional work needed to more definitively assess the concept’s viability, particularly through a better understanding of the U-234/U-235 ratio variability in modern enrichment plants.

  14. Conceptual Ideas for New Nondestructive UF6 Cylinder Assay Techniques

    SciTech Connect (OSTI)

    Miller, Karen A.

    2012-05-02

    Nondestructive assay (NDA) measurements of uranium cylinders play an important role in helping the International Atomic Energy Agency (IAEA) safeguard uranium enrichment plants. Traditionally, these measurements have consisted of a scale or load cell to determine the mass of UF{sub 6} in the cylinder combined with a gamma-ray measurement of the 186 keV peak from {sup 235}U to determine enrichment. More recently, Los Alamos National Laboratory (LANL) and Pacific Northwest National Laboratory (PNNL) have developed systems that exploit the passive neutron signal from UF{sub 6} to determine uranium mass and/or enrichment. These include the Uranium Cylinder Assay System (UCAS), the Passive Neutron Enrichment Meter (PNEM), and the Hybrid Enrichment Verification Array (HEVA). The purpose of this report is to provide the IAEA with new ideas on technologies that may or may not be under active development but could be useful for UF{sub 6} cylinder assay. To begin, we have included two feasibility studies of active interrogation techniques. There is a long history of active interrogation in the field of nuclear safeguards, especially for uranium assay. Both of the active techniques provide a direct measure of {sup 235}U content. The first is an active neutron method based on the existing PNEM design that uses a correlated {sup 252}Cf interrogation source. This technique shows great promise for UF{sub 6} cylinder assay and is based on advanced technology that could be implemented in the field in the near term. The second active technique is nuclear resonance fluorescence (NRF). In the NRF technique, a bremsstrahlung photon beam could be used to illuminate the cylinder, and high-resolution gamma-ray detectors would detect the characteristic de-excitation photons. The results of the feasibility study show that under certain measurement geometries, NRF is impractical for UF6 cylinder assay, but the 'grazing transmission' and 'secant transmission' geometries have more potential for this application and should be assessed quantitatively. The next set of techniques leverage scintillator detectors that are sensitive to both neutron and gamma radiation. The first is the BC-523A capture-gated organic liquid scintillator. The detector response from several different neutron energies has been characterized and is included in the study. The BC-523A has not yet been tested with UF{sub 6} cylinders, but the application appears to be well suited for this technology. The second detector type is a relatively new inorganic scintillator called CLYC. CLYC provides a complementary detection approach to the HEVA and PNEM systems that could be used to determine uranium enrichment in UF{sub 6} cylinders. In this section, the conceptual idea for an integrated CLYC-HEVA/PNEM system is explored that could yield more precision and robustness against systemic uncertainties than any one of the systems by itself. This is followed by a feasibility study on using alpha-particle-induced reaction gamma-rays as a way to estimate {sup 234}U abundance in UF{sub 6}. Until now, there has been no readily available estimate of the strength of these reaction gamma-rays. Thick target yields of the chief reaction gammas are computed and show that they are too weak for practical safeguards applications. In special circumstances where long count times are permissible, the 1,275 keV F({alpha},x{gamma}) is observable. Its strength could help verify an operator declaration provided other knowledge is available (especially the age). The other F({alpha},x{gamma}) lines are concealed by the dominant uranium line spectrum and associated continuum. Finally, the last section provides several ideas for electromagnetic and acoustic nondestructive evaluation (NDE) techniques. These can be used to measure cylinder wall thickness, which is a source of systematic uncertainty for gamma-ray-based NDA techniques; characterize the UF{sub 6} filling profile inside the cylinder, which is a source of systematic uncertainty for neutron-based NDA techniques; locate hidden objects inside the cylinder; a

  15. Neutron spectrometry for ${\\rm UF}_6$ enrichment verification in storage cylinders

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

    Mengesha, Wondwosen; Kiff, Scott D.

    2015-01-29

    Verification of declared UF6 enrichment and mass in storage cylinders is of great interest in nuclear material nonproliferation. Nondestructive assay (NDA) techniques are commonly used for safeguards inspections to ensure accountancy of declared nuclear materials. Common NDA techniques used include gamma-ray spectrometry and both passive and active neutron measurements. In the present study, neutron spectrometry was investigated for verification of UF6 enrichment in 30B storage cylinders based on an unattended and passive measurement approach. MCNP5 and Geant4 simulated neutron spectra, for selected UF6 enrichments and filling profiles, were used in the investigation. The simulated neutron spectra were analyzed using principalmore »component analysis (PCA). The PCA technique is a well-established technique and has a wide area of application including feature analysis, outlier detection, and gamma-ray spectral analysis. Results obtained demonstrate that neutron spectrometry supported by spectral feature analysis has potential for assaying UF6 enrichment in storage cylinders. The results from the present study also showed that difficulties associated with the UF6 filling profile and observed in other unattended passive neutron measurements can possibly be overcome using the approach presented.« less

  16. Hybrid Enrichment Assay Methods for a UF6 Cylinder Verification Station: FY10 Progress Report

    SciTech Connect (OSTI)

    Smith, Leon E.; Jordan, David V.; Orton, Christopher R.; Misner, Alex C.; Mace, Emily K.

    2010-08-01

    Pacific Northwest National Laboratory (PNNL) is developing the concept of an automated UF6 cylinder verification station that would be located at key measurement points to positively identify each cylinder, measure its mass and enrichment, store the collected data in a secure database, and maintain continuity of knowledge on measured cylinders until the arrival of International Atomic Energy Agency (IAEA) inspectors. At the center of this unattended system is a hybrid enrichment assay technique that combines the traditional enrichment-meter method (based on the 186 keV peak from 235U) with non-traditional neutron-induced high-energy gamma-ray signatures (spawned primarily by 234U alpha emissions and 19F(alpha, neutron) reactions). Previous work by PNNL provided proof-of-principle for the non-traditional signatures to support accurate, full-volume interrogation of the cylinder enrichment, thereby reducing the systematic uncertainties in enrichment assay due to UF6 heterogeneity and providing greater sensitivity to material substitution scenarios. The work described here builds on that preliminary evaluation of the non-traditional signatures, but focuses on a prototype field system utilizing NaI(Tl) and LaBr3(Ce) spectrometers, and enrichment analysis algorithms that integrate the traditional and non-traditional signatures. Results for the assay of Type-30B cylinders ranging from 0.2 to 4.95 wt% 235U, at an AREVA fuel fabrication plant in Richland, WA, are described for the following enrichment analysis methods: 1) traditional enrichment meter signature (186 keV peak) as calculated using a square-wave convolute (SWC) algorithm; 2) non-traditional high-energy gamma-ray signature that provides neutron detection without neutron detectors and 3) hybrid algorithm that merges the traditional and non-traditional signatures. Uncertainties for each method, relative to the declared enrichment for each cylinder, are calculated and compared to the uncertainties from an attended HPGe verification station at AREVA, and the IAEA’s uncertainty target values for feed, tail and product cylinders. A summary of the major findings from the field measurements and subsequent analysis follows: • Traditional enrichment-meter assay using specially collimated NaI spectrometers and a Square-Wave-Convolute algorithm can achieve uncertainties comparable to HPGe and LaBr for product, natural and depleted cylinders. • Non-traditional signatures measured using NaI spectrometers enable interrogation of the entire cylinder volume and accurate measurement of absolute 235U mass in product, natural and depleted cylinders. • A hybrid enrichment assay method can achieve lower uncertainties than either the traditional or non-traditional methods acting independently because there is a low degree of correlation in the systematic errors of the two individual methods (wall thickness variation and 234U/235U variation, respectively). This work has indicated that the hybrid NDA method has the potential to serve as the foundation for an unattended cylinder verification station. When compared to today’s handheld cylinder-verification approach, such a station would have the following advantages: 1) improved enrichment assay accuracy for product, tail and feed cylinders; 2) full-volume assay of absolute 235U mass; 3) assay of minor isotopes (234U and 232U) important to verification of feedstock origin; single instrumentation design for both Type 30B and Type 48 cylinders; and 4) substantial reduction in the inspector manpower associated with cylinder verification.

  17. Summary of Field Measurement on UF6 Cylinders Using Electro-Mechanically Cooled Systems

    SciTech Connect (OSTI)

    McGinnis, Brent R; Smith, Steven E; Solodov, Alexander A; Whitaker, J Michael; Morgan, James B; MayerII, Richard L.; Montgomery, J. Brent

    2009-01-01

    Measurement of the enrichment of solid state UF6 stored within large metal cylinders is a task commonly performed by plant operators and inspectors. The measurement technologies typically used range from low-resolution, high-efficiency sodium iodide detectors to high-resolution, moderate-efficiency high-purity germanium (HPGe) detectors. The technology used and methods deployed are dependent upon the material being measured, environmental conditions, time constraints, and measurement-precision requirements. Operators and inspectors typically use specially designed, HPGe detectors that are cooled with liquid nitrogen in situations where high-resolution measurements are required. However, the requirement for periodically refilling the system with liquid nitrogen makes remote usage cumbersome and slow. The task of cooling the detector reduces the available time for the inspector to perform other safeguards activities while on site. If the inspector has to reduce the count time for each selected cylinder to ensure that all preselected cylinders are measured during the inspection, the resulting measurement uncertainties may be increased, making it more difficult to detect and verify potential discrepancies in the operator's declarations. However, recent advances in electromechanically cooled HPGe detectors may provide the inspector with an improved verification tool by eliminating the need for liquid nitrogen. This report provides a summary of test results for field measurements performed using electromechanically cooled HPGe detectors on depleted, natural, and low-enriched uranium cylinders. The results of the study provide valuable information to inspectors and operators regarding the capabilities and limitations of electromechanically cooled systems based on true field-measurement conditions.

  18. Photoelectron Spectroscopy and Theoretical Studies of UF5 ? and UF6 ?

    SciTech Connect (OSTI)

    Dau, Phuong D.; Su, Jing; Liu, Hong-Tao; Huang, Dao-Ling; Wei, Fan; Li, Jun; Wang, Lai S.

    2012-05-17

    The UF5 ? and UF6 ? anions are produced using electrospray ionization and investigated by photoelectron spectroscopy and relativistic quantum chemistry. An extensive vibrational progression is observed in the spectra of UF5 ?, indicating significant geometry changes between the anion and neutral ground state. Franck-Condon factor simulations of the observed vibrational progression yield an adiabatic electron detachment energy of 3.82 ± 0.05 eV for UF5 ?. Relativistic quantum calculations using density functional and ab initio theories are performed on UF5 ? and UF6 ? and their neutrals. The ground states of UF5 ? and UF5 are found to have C4v symmetry, but with a large U?F bond length change. The ground state of UF5 ? is a triplet state (3B2) with the two 5f electrons occupying a 5fz3-based 8a1 highest occupied molecular orbital (HOMO) and the 5fxyz-based 2b2 HOMO-1 orbital. The detachment cross section from the 5fxyz orbital is observed to be extremely small and the detachment transition from the 2b2 orbital is more than ten times weaker than that from the 8a1 orbital at the photon energies available. The UF6 ? anion is found to be octahedral, similar to neutral UF6 with the extra electron occupying the 5fxyz-based a2u orbital. Surprisingly, no photoelectron spectrum could be observed for UF6 ? due to the extremely low detachment cross section from the 5fxyz-based HOMO of UF6 ?.

  19. Determination of the 235U Mass and Enrichment within Small UF6 Cylinders via a Neutron Coincidence Well Counting System

    SciTech Connect (OSTI)

    McElroy, Robert Dennis; Croft, Dr. Stephen; Young, Brian M; Venkataraman, Ram

    2011-01-01

    The construction of three new uranium enrichment facilities in the United States has sparked renewed interest in the development and enhancement of methods to determine the enrichment and fissile mass content of UF6 cylinders. We describe the design and examine the expected performance of a UF6 bottle counter developed for the assay of Type 5A cylinders. The counter, as designed and subsequently constructed, is a tall passive neutron well counter with a clam-shell configuration and graphite end plugs operated in fast neutron mode. Factory performance against expectation is described. The relatively high detection efficiency and effectively 4 detection geometry provide a near-ideal measurement configuration, making the UF6 bottle counter a valuable tool for the evaluation of the neutron coincidence approach to UF6 cylinder assay. The impacts of non-uniform filling, voids, enrichment, and mixed enrichments are examined

  20. Testing the Floor Scale Designated for Pacific Northwest National Laboratory's UF6 Cylinder Portal Monitor

    SciTech Connect (OSTI)

    Curtis, Michael M.; Weier, Dennis R.

    2009-03-12

    Pacific Northwest National Laboratory (PNNL) obtained a Mettler Toledo floor scale for the purpose of testing it to determine whether it can replace the International Atomic Energy Agency’s (IAEA) cumbersome, hanging load cell. The floor scale is intended for use as a subsystem within PNNL’s nascent UF6 Cylinder Portal Monitor. The particular model was selected for its accuracy, size, and capacity. The intent will be to use it only for 30B cylinders; consequently, testing did not proceed beyond 8,000 lb.

  1. Modified biokinetic model for uranium from analysis of acute exposure to UF6

    SciTech Connect (OSTI)

    Fisher, D.R.; Kathren, R.L.; Swint, M.J. )

    1991-03-01

    Urinalysis measurements from 31 workers acutely exposed to uranium hexafluoride (UF6) and its hydrolysis product UO2F2 (during the 1986 Gore, Oklahoma UF6-release accident) were used to develop a modified recycling biokinetic model for soluble U compounds. The model is expressed as a five-compartment exponential equation: yu(t) = 0.086e-2.77t + 0.0048e-0.116t + 0.00069e-0.0267t + 0.00017 e-0.00231t + 2.5 x 10(-6) e-0.000187t, where yu(t) is the fractional daily urinary excretion and t is the time after intake, in days. The excretion constants of the five exponential compartments correspond to residence half-times of 0.25, 6, 26, 300, and 3,700 d in the lungs, kidneys, other soft tissues, and in two bone volume compartments, respectively. The modified recycling model was used to estimate intake amounts, the resulting committed effective dose equivalent, maximum kidney concentrations, and dose equivalent to bone surfaces, kidneys, and lungs.

  2. Prototype Radiation Detector Positioning System For The Automated Nondestructive Assay Of Uf6 Cylinders

    SciTech Connect (OSTI)

    Hatchell, Brian K.; Valdez, Patrick LJ; Orton, Christopher R.; Mace, Emily K.

    2011-08-07

    International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders taken to be representative of the facility’s entire cylinder inventory. These measurements are time-consuming, expensive, and assay only a small fraction of the total cylinder volume. An automated nondestructive assay system capable of providing enrichment measurements over the full volume of the cylinder could improve upon current verification practices in terms of efficiency and assay accuracy. This paper describes an approach denoted the Integrated Cylinder Verification Station (ICVS) that supports 100% cylinder verification, provides volume-averaged cylinder enrichment assay, and reduces inspector manpower needs. To allow field measurements to be collected to validate data collection algorithms, a prototype radiation detector positioning system was constructed. The system was designed to accurately position an array of radiation detectors along the length of a cylinder to measure UF6 enrichment. A number of alternative radiation shields for the detectors were included with the system. A collimated gamma-ray spectrometer module that allows translation of the detectors in the surrounding shielding to adjust the field of view, and a collimating plug in the end to further reduce the low-energy field of view, were also developed. Proof-of-principle measurements of neutron and high-energy gamma-ray signatures, using moderated neutron detectors and large-volume spectrometers in a fixed-geometry, portal-like configuration, supported an early assessment of the viability of the concept. The system has been used successfully on two testing campaigns at an AREVA fuel fabrication plant to scan over 30 product cylinders. This paper will describe the overall design of the detector positioning system and provide an overview of the Integrated Cylinder Verification Station (ICVS) approach.

  3. A Laser-Based Method for On-Site Analysis of UF6 at Enrichment Plants

    SciTech Connect (OSTI)

    Anheier, Norman C.; Cannon, Bret D.; Martinez, Alonzo; Barrett, Christopher A.; Taubman, Matthew S.; Anderson, Kevin K.; Smith, Leon E.

    2014-11-23

    The International Atomic Energy Agency’s (IAEA’s) long-term research and development plan calls for more cost-effective and efficient safeguard methods to detect and deter misuse of gaseous centrifuge enrichment plants (GCEPs). The IAEA’s current safeguards approaches at GCEPs are based on a combination of routine and random inspections that include environmental sampling and destructive assay (DA) sample collection from UF6 in-process material and selected cylinders. Samples are then shipped offsite for subsequent laboratory analysis. In this paper, a new DA sample collection and onsite analysis approach that could help to meet challenges in transportation and chain of custody for UF6 DA samples is introduced. This approach uses a handheld sampler concept and a Laser Ablation, Laser Absorbance Spectrometry (LAARS) analysis instrument, both currently under development at the Pacific Northwest National Laboratory. A LAARS analysis instrument could be temporarily or permanently deployed in the IAEA control room of the facility, in the IAEA data acquisition cabinet, for example. The handheld PNNL DA sampler design collects and stabilizes a much smaller DA sample mass compared to current sampling methods. The significantly lower uranium mass reduces the sample radioactivity and the stabilization approach diminishes the risk of uranium and hydrogen fluoride release. These attributes enable safe sample handling needed during onsite LAARS assay and may help ease shipping challenges for samples to be processed at the IAEA’s offsite laboratory. The LAARS and DA sampler implementation concepts will be described and preliminary technical viability results presented.

  4. Remote Monitoring and Tracking of UF6 Cylinders Using Long-Range Passive Ultra-wideband (UWB) RFID Tags

    SciTech Connect (OSTI)

    Nekoogar, F; Dowla, F

    2007-06-06

    An IAEA Technical Meeting on Techniques for IAEA Verification of Enrichment Activities identified 'smart tags' as a technology that should be assessed for tracking and locating UF6 cylinders. Although there is vast commercial industry working on RFID systems, the vulnerabilities of commercial products are only beginning to emerge. Most of the commercially off-the-shelf (COTS) RFID systems operate in very narrow frequency bands, making them vulnerable to detection, jamming and tampering and also presenting difficulties when used around metals (i.e. UF6 cylinders). Commercial passive RFID tags have short range, while active RFID tags that provide long ranges have limited lifetimes. There are also some concerns with the introduction of strong (narrowband) radio frequency signals around radioactive and nuclear materials. Considering the shortcomings of commercial RFID systems, in their current form, they do not offer a promising solution for continuous monitoring and tracking of UF6 cylinders. In this paper, we identify the key challenges faced by commercial RFID systems for monitoring UF6 cylinders, and introduce an ultra-wideband approach for tag/reader communications that addresses most of the identified challenges for IAEA safeguards applications.

  5. A "Proof-of-Concept" Demonstration of RF-Based Technologies for UF6 Cylinder Tracking at Centrifuge Enrichment Plant

    SciTech Connect (OSTI)

    Pickett, Chris A; Younkin, James R; Kovacic, Donald N; Dixon, E. T.; Martinez, B.

    2007-01-01

    This effort describes how radio-frequency (RF) technology can be integrated into a uranium enrichment facility's nuclear materials accounting and control program to enhance uranium hexafluoride (UF6) cylinder tracking and thus provide benefits to both domestic and international safeguards. Approved industry-standard cylinders are used to handle and store UF6 feed, product, tails, and samples at uranium enrichment plants. In the international arena, the International Atomic Energy Agency (IAEA) relies on time-consuming manual cylinder inventory and tracking techniques to verify operator declarations and to detect potential diversion of UF6. Development of a reliable, automated, and tamper-resistant process for tracking and monitoring UF6 cylinders would greatly reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a "proof-of concept" system that was designed show the feasibility of using RF based technologies to track individual UF6 cylinders throughout their entire life cycle, and thus ensure both increased domestic accountability of materials and a more effective and efficient method for application of IAEA international safeguards at the site level. The proposed system incorporates RF-based identification devices, which provide a mechanism for a reliable, automated, and tamper-resistant tracking network. We explore how securely attached RF tags can be integrated with other safeguards technologies to better detect diversion of cylinders. The tracking system could also provide a foundation for integration of other types of safeguards that would further enhance detection of undeclared activities.

  6. Automated Nondestructive Assay of UF6 Cylinders: Detector Characterization and Initial Measurements

    SciTech Connect (OSTI)

    Mace, Emily K.; Smith, Leon E.

    2011-10-01

    International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders assumed to be representative of the facility's entire cylinder inventory. These measurements are time-consuming and assay only a small fraction of the total cylinder volume. An automated nondestructive assay system capable of providing enrichment measurements over the full volume of the cylinder could improve upon current verification practices in terms of manpower and assay accuracy. Pacific Northwest National Laboratory is developing an Integrated Cylinder Verification System (ICVS) intended for this purpose and has developed a field prototype of the nondestructive assay (NDA) components of an ICVS. The nondestructive assay methods would combine the 'traditional' enrichment-meter signature (i.e. 186-keV emission from 235U) as well as 'non-traditional' high-energy photon signatures derived from neutrons produced primarily by 19F({alpha},n) reactions. This paper describes the design, calibration and characterization of the NaI(Tl) and LaBr3(Ce) spectrometers utilized in the field prototype. An overview of a recent field measurement campaign is then provided, supported by example gamma-ray pulse-height spectra collected on cylinders of known enrichment.

  7. Technology Assessment for Proof-of-Concept UF6 Cylinder Unique Identification Task 3.1.2 Report – Survey and Assessment of Technologies

    SciTech Connect (OSTI)

    Wylie, Joann; Hockert, John

    2014-04-24

    The National Nuclear Security Administration (NNSA) Office of Nonproliferation and International Security’s (NA-24) Next Generation Safeguards Initiative (NGSI) and the nuclear industry have begun to develop approaches to identify and monitor uranium hexafluoride (UF6) cylinders. The NA-24 interest in a global monitoring system for UF6 cylinders relates to its interest in supporting the International Atomic Energy Agency (IAEA) in deterring and detecting diversion of UF6 (e.g., loss of cylinder in transit) and undeclared excess production at conversion and enrichment facilities. The industry interest in a global monitoring system for UF6 cylinders relates to the improvements in operational efficiencies that such a system would provide. This task is part of an effort to survey and assess technologies for a UF6 cylinder to identify candidate technologies for a proof-of-concept demonstration and evaluation for the Cylinder Identification System (CIS).

  8. Signatures and Methods for the Automated Nondestructive Assay of UF6 Cylinders at Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Smith, Leon E.; Mace, Emily K.; Misner, Alex C.; Shaver, Mark W.

    2010-08-08

    International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders taken to be representative of the facility’s entire cylinder inventory. These measurements are time-consuming, expensive, and assay only a small fraction of the total cylinder volume. An automated nondestructive assay system capable of providing enrichment measurements over the full volume of the cylinder could improve upon current verification practices in terms of manpower and assay accuracy. Such a station would use sensors that can be operated in an unattended mode at an industrial facility: medium-resolution scintillators for gamma-ray spectroscopy (e.g., NaI(Tl)) and moderated He-3 neutron detectors. This sensor combination allows the exploitation of additional, more-penetrating signatures beyond the traditional 185-keV emission from U-235: neutrons produced from F-19(?,n) reactions (spawned primarily from U 234 alpha emission) and high-energy gamma rays (extending up to 8 MeV) induced by neutrons interacting in the steel cylinder. This paper describes a study of these non-traditional signatures for the purposes of cylinder enrichment verification. The signatures and the radiation sensors designed to collect them are described, as are proof-of-principle cylinder measurements and analyses. Key sources of systematic uncertainty in the non-traditional signatures are discussed, and the potential benefits of utilizing these non-traditional signatures, in concert with an automated form of the traditional 185-keV-based assay, are discussed.

  9. MODEL AND ALGORITHM EVALUATION FOR THE HYBRID UF6 CONTAINER INSPECTION SYSTEM

    SciTech Connect (OSTI)

    McDonald, Benjamin S.; Jordan, David V.; Orton, Christopher R.; Mace, Emily K.; Smith, Leon E.; Wittman, Richard S.

    2011-06-14

    ABSTRACT Pacific Northwest National Laboratory (PNNL) is developing an automated UF6 cylinder verification station concept based on the combined collection of traditional enrichment-meter (186 keV photons from U-235) data and non-traditional, neutron-induced, high-energy gamma-signatures (3-8.5 MeV) with an array of collimated, medium-resolution scintillators. Previous (2010) work at PNNL demonstrated proof-of-principle that this hybrid method yields accurate, full-volume assay of the cylinder enrichment, reduces systematic errors when compared to several other enrichment assay methods, and provides simplified instrumentation and algorithms suitable for long-term unattended operations. We used Monte Carlo modeling with MCNP5 to support system design (e.g., number and configuration of detector arrays, and design of iron/poly collimators for enhanced (n,?) conversion) and enrichment algorithm development. We developed a first-generation modeling framework in 2010. These tools have since been expanded, refined and benchmarked against field measurements with a prototype system of a 30B cylinder population (0.2 to 4.95 weight % U-235). The MCNP5 model decomposes the radiation transport problem into a linear superposition of “basis spectra” representing contributions from the different uranium isotopes and gamma-ray generation mechanisms (e.g. neutron capture). This scheme accommodates fast generation of “virtual assay signatures” for arbitrary enrichment, material age, and fill variations. Ongoing (FY-2011) refinements to the physics model include accounting for generation of bremsstrahlung photons, arising primarily from the beta decay of Pa-234m, a U-238 daughter. We are using the refined model to optimize collimator design for the hybrid method. The traditional assay method benefits from a high degree of collimation (to isolate each detector’s field-of-view) and relatively small detector area, while the non-traditional method benefits from a wide field-of-view, i.e. less collimation and larger detectors. We implement the enrichment-meter method by applying a square-wave digital filter to a raw spectrum and extracting the 186-keV peak area directly from the convolute spectrum. Ongoing enhancements to this approach include mitigating a systematic peak-area measurement deficit arising from curvature in the spectrum continuum shape. An optimized system prototype based on model results is utilized in a new set of 2011 field measurements, and model and measurement enrichment assay uncertainties are compared.

  10. An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System

    SciTech Connect (OSTI)

    Martyn, Rose; Fitzgerald, Peter; Stehle, Nicholas D; Rowe, Nathan C; Younkin, James R

    2011-01-01

    An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control & Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

  11. Ultra-low field NMR for detection and characterization of 235 UF6

    SciTech Connect (OSTI)

    Espy, Michelle A; Magnelind, Per E; Matlashov, Andrei N; Urbaitis, Algis V; Volegov, Petr L

    2009-01-01

    We have demonstrated the first ultra-low field (ULF) nuclear magnetic resonance measurements of uranium hexafluoride (UF{sub 6}), both depleted and 70% enriched, which is used in the uranium enrichment process. A sensitive non-invasive detection system would have an important role in non-proliferation surveillance. A two-frequency technique was employed to remove the transients induced by rapidly switching off the 50 mT pre-polarization field. A mean transverse relaxation time T{sub 2} of 24 ms was estimated for the un-enriched UF{sub 6} sample measured at a mean temperature of 80 C. Nuclear magnetic resonance at ULF has several advantages including the ability to measure through metal, such as pipes, and simple magnetic field generation hardware. We present here recent data and discuss the potential for non-proliferation monitoring of enrichment and flow velocity.

  12. Results of Continuous Load Cell Monitoring Field Trial for UF6 Withdrawals at an Operating Industrial Plant

    SciTech Connect (OSTI)

    Krichinsky, Alan M; Bell, Lisa S; Conchewski, Curtis A; Peters, Benjamin R; Pickett, Chris A; Richardson, Dave; Rowe, Nathan C; Younkin, James R

    2010-01-01

    Continuous load cell monitoring (CLCM) has been implemented and tested for use as a safeguards tool during a 2009 field trial in an operating UF6 transfer facility. The transfer facility is part of the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio, operated by the United States Enrichment Corporation. During the field trial, two process scales for UF{sub 6} cylinders were continuously monitored for a 6-month period as cylinders were being filled. The collected CLCM data were used in testing an event processor serving as a filter for highlighting measurements representing significant operational activities that are important in verifying declared operations. The collection of CLCM data, coupled with rules-based event processing, can provide inspectors with knowledge of a facility's feed and withdrawal activities occurring between site visits. Such process knowledge promises to enhance the effectiveness of safeguards by enabling inspectors to quantitatively compare declared activities directly with process measurements. Selected results of the field trial and event processing will be presented in the context of their value to an independent inspector and a facility operator.

  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.

    2009-11-01

    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. A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants

    SciTech Connect (OSTI)

    Krichinsky, Alan M; Bates, Bruce E; Chesser, Joel B; Koo, Sinsze; Whitaker, J Michael

    2009-12-01

    This report describes an engineering-scale, mock UF6 feed and withdrawal (F&W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F&W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F&W system description. Continuous monitoring components on the mock F&W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF{sub 6} F&W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF{sub 6}. The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under plant operating conditions. The ultimate use of technologies tested on the engineering-scale test bed is to work with safeguards agencies to install them in operating plants (e.g., enrichment and fuel processing plants), thereby promoting new safeguards measures with minimal impact to operating plants. In addition, this system is useful in identifying features for new plants that can be incorporated as part of 'safeguards by design,' in which load cells and other monitoring technologies are specified to provide outputs for automated monitoring and inspector evaluation.

  15. Mail Services | The Ames Laboratory

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

    Mail Services General Information: Mail Services provides U.S. Postal Service (USPS) and ISU campus mail receiving, sorting and outbound service. This service is available for all Ames Laboratory official business. Quick Links to Schedules: Hours Pickup Delivery Stamped mail -outbound Mail to be posted/metered Campus mail to Ames Lab destinations Campus mail to Non-Ames Lab destinations Campus mail - inbound USPS mail - inbound Hours (back) The mail room in 153 Spedding is accessible to pick up

  16. Electronic Mail Analysis Capability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-01-08

    Establishes the pilot program to test the Department of Energy (DOE) Electronic Mail Analysis Capability (EMAC), which will be used to monitor and analyze outgoing and incoming electronic mail (e-mail) from the National Nuclear Security Administration (NNSA) and DOE laboratories that are engaged in nuclear weapons design or work involving special nuclear material. No cancellation.

  17. Mail Services User's Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-07-12

    This Manual provides detailed information on using the Department of Energy (DOE) mail services. Canceled by DOE G 573.1-1.

  18. mail_paycheck_111609

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

    Updated:
11/16/09
 P.O Box 1663 Los Alamos, New Mexico 87544 MAIL PAYCHECK FORM TO: CRAFT PAYROLL DEPARTMENT - P238 FROM: (Please Print) Z# ORG CODE PLEASE MAIL MY PAYCHECK, TO THE ADDRESS ON FILE WITH PAYROLL, FOR THE PAY PERIOD BEGINNING: EMPLOYEE SIGNATURE Z# DATE SUPERVISOR SIGNATURE Z# DATE

  19. Request Repository Mailing List

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

    Policies User Surveys NERSC Users Group User Announcements Help Staff Blogs Request Repository Mailing List Operations for: Passwords & Off-Hours Status 1-800-66-NERSC, option 1 or 510-486-6821 Account Support https://nim.nersc.gov accounts@nersc.gov 1-800-66-NERSC, option 2 or 510-486-8612 Consulting http://help.nersc.gov consult@nersc.gov 1-800-66-NERSC, option 3 or 510-486-8611 Home » For Users » Request Repository Mailing List Request Repository Mailing List Use this form to request a

  20. Mail and Distribution | Department of Energy

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

    Mail and Distribution Mail and Distribution The DOE Mail Center provides a variety of mail services for all official and other authorized mail for the Department of Energy and its employees. The services provided include the processing of all incoming postal mail, outgoing official mail, internal mail processing, accountable mail processing, pouch mail, a variety of overnight express mail services, directory services, and pick-up and delivery services. The Mail Management Memorandum (pdf)

  1. By Certified Mail May

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

    By Certified Mail May 4,2012 Dorothy Riehle FOIA Office U.S. Department of Energy P. O. Box 550 Richland, WA 99352 Re: FOIA RequestLand Transfer Dear Ms. Riehle: Pursuant to the...

  2. By E-Mail

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

    By E-Mail May 29, 2012 Dorothy Riehle FOIA Office U.S. Department of Energy P. O. Box 550 Richland, WA 99352 Re: FOIA RequestTank Inventories Dear Ms. Riehle: Pursuant to the...

  3. PDSF Mailing Lists

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

    Mailing Lists PDSF Mailing Lists pdsf-status@nersc.gov This is voluntary. You have to subscribe to it. This list can be chatty, since major and minor problems are sent to this list. Also multiple status updates will be sent for extended outages. Subscribe: Send email to pdsf-status-request@nersc.gov with subscribe in the subject of the message. Unsubscribe: Send email to pdsf-status-request@nersc.gov with unsubscribe in the subject of the message. pdsf-users@nersc.gov Users are subscribed to

  4. Mailing List Subscription

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

    Jefferson Lab Jefferson Lab Home Search Contact JLab Mailing List Subscription ---------------------- Please visit Jefferson Lab Computing for further information on managing your mailing lists. Subscribe Unsubscribe Your email address: You may subscribe/unsubscribe to these lists: cctest-alert clas_drift_chambers clas_offline clas_slow_control clas_strangep clas_tof credit-card csc_all cuga cugapost cugw dbgen dc_pwr dccc diam dnpprog e1_run e2_run earthwatch eedesign eg1_run egn_calcom

  5. Assessment of UF6 Equation of State

    SciTech Connect (OSTI)

    Brady, P; Chand, K; Warren, D; Vandersall, J

    2009-02-11

    A common assumption in the mathematical analysis of flows of compressible fluids is to treat the fluid as a perfect gas. This is an approximation, as no real fluid obeys the perfect gas relationships over all temperature and pressure conditions. An assessment of the validity of treating the UF{sub 6} gas flow field within a gas centrifuge with perfect gas relationships has been conducted. The definition of a perfect gas is commonly stated in two parts: (1) the gas obeys the thermal equation of state, p = {rho}RT (thermally perfect), and, (2) the gas specific heats are constant (calorically perfect). Analysis indicates the thermally perfect assumption is valid for all flow conditions within the gas centrifuge, including shock fields. The low operating gas pressure is the primary factor in the suitability of the thermally perfect equation of state for gas centrifuge computations. UF{sub 6} is not calorically perfect, as the specific heats vary as a function of temperature. This effect is insignificant within the bulk of the centrifuge gas field, as gas temperatures vary over a narrow range. The exception is in the vicinity of shock fields, where temperature, pressure, and density gradients are large, and the variation of specific heats with temperature should be included in the technically detailed analyses. Results from a normal shock analysis incorporating variable specific heats is included herein, presented in the conventional form of shock parameters as a function of inlet Mach Number. The error introduced by assuming constant specific heats is small for a nominal UF{sub 6} shock field, such that calorically perfect shock relationships can be used for scaling and initial analyses. The more rigorous imperfect gas analysis should be used for detailed analyses.

  6. Mail Services User's Guide

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-10-03

    This Guide provides information on using Department of Energy (DOE) mail services in accordance with U.S. Postal Service, General Services Administration (GSA), and DOE regulations. Cancels DOE M 573.1-1. Canceled by DOE N 251.89.

  7. Mailing List Subscription

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

    Mailing List Subscription Jefferson Lab Home Search Contact JLab Descriptions A - C autocad: No description available briefs: On-Target Briefs cctest-alert: No description available clas_drift_chambers: Hall B Drift Chambers Group clas_offline: Discussion group for CLAS RECSIS group clas_slow_control: CLAS slow control working group clas_strangep: Hall B Strange Particles using CLAS discussion group clas_tof: CLAS Time of Flight Collaboration credit-card: List of JLab Credit Card buyers csc_all:

  8. Printing and Mail Managers Exchange Forum Teleconference

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

    May 16, 2013 Mail discussion Joe Whitford opened the meeting by introducing Al Majors to talk about mail related items. 1) Update on the USPS mail name changes. If approved by the Postal Regulatory Commission the following name changes will go into effective July 28, 2013: a. Express Mail will be called Priority Mail Express b. Express Mail International will be Priority Mail International c. Express Mail Corporate Account will become USPS Express Corporate Account Only the names of these

  9. Printing and Mail Managers Exchange Forum Teleconference

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

    Mail Managers discussion Joe Whitford opened the meeting by introducing Al Majors to talk about mail related items. 1) Mr. Majors introduced Derek Milner, Policy Advisor from...

  10. Printing and Mail Managers Exchange Forum Teleconference

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

    Mail Managers discussion Joe Whitford opened the meeting by introducing Tony Nellums to talk about mail related items. 1) Mr. Nellums introduced Derek Milner, Policy Advisor from...

  11. LLNL E-Mail Utilities

    Energy Science and Technology Software Center (OSTI)

    2005-10-31

    The LLNL E-mail Utilities software library is a Java API that simplifies the creation and delivery of email in Java business applications. It consists of a database-driven template engine, various strategies for composing, queuing, dispatching email and a Java Swing GUI for creating and editing email templates.

  12. Minutes from the Print and Mail Managers Exchange Forum Teleconference...

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

    Minutes from the Print and Mail Managers Exchange Forum Teleconferences Minutes from the Print and Mail Managers Exchange Forum Teleconferences Minutes from the Print and Mail...

  13. Mail Management Memorandum, July 2, 2010 | Department of Energy

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

    Mail Management Memorandum, July 2, 2010 Mail Management Memorandum, July 2, 2010 Mail Management Memorandum prescribing policy and requirements for the effective, economical, and...

  14. Field Facilities Contacts for Printing and Mail

    Energy Savers [EERE]

    Field Facilities Contacts for Printing and Mail Print and Mail Contacts Site Printing Contact Mail Contact NNSA, Albuquerque Deborah Miller (505) 845-6049 Thomas H. Clinkenbeard NNSA Service Center PO Box 5400 Albuquerque, NM 87185-5400 (505) 845-4602 tclinkenbeard@doeal.gov (mailto:tclinkenbeard@doeal.gov) Argonne National Laboratory Doreen Schoening Argonne National Laboratory U.S. Department of Energy 9700 South Cass Avenue Blvd 340 Lemonmt, IL 60439 (630) 840-6399 dschoening@anl.gov

  15. Supplemental Systems for Unattended UF6 Cylinder Monitoring

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2010-08-11

    Cylinder assay and mass measurements, the mainstay of enrichment plant verification efforts have historically been performed by International Atomic Energy Agency (IAEA) inspectors using portable equipment. For the sake of efficiency, accuracy, and timeliness, such equipment is being supplanted by unattended measurement stations. Ancillary systems must be employed with such stations to ensure that measured parameters are properly recorded, cylinders are positively identified, operations occur according to procedure, and no tampering takes place in the inspectors’ absence. Depending on the facility, it may prove feasible to track cylinders from the measurement vicinity to their storage locations using surveillance. This paper will provide a cursory description of the various subsystems associated with Pacific Northwest National Laboratory’s Integrated Cylinder Verification Station and how inattention to the requirements of such systems could seriously diminish the capability of the integrated whole.

  16. Materials Data on UF6 (SG:62) by Materials Project

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

    Kristin Persson

    2014-11-02

    Computed materials data using density functional theory calculations. These calculations determine the electronic structure of bulk materials by solving approximations to the Schrodinger equation. For more information, see https://materialsproject.org/docs/calculations

  17. Enhanced Algorithm for Traceability Measurements in UF6 Flow Pipe

    SciTech Connect (OSTI)

    Copinger, Thomas E; March-Leuba, Jose A; Upadhyaya, Belle R

    2007-01-01

    The Blend Down Monitoring System (BDMS) is used to continually assess the mixing and downblending of highly enriched uranium (HEU) with low-enriched uranium (LEU). This is accomplished by measuring the enrichment and the fissile mass flow rate of the UF{sub 6} gas located in each process pipe of the system by inducing the fission of the {sup 235}U contained in the gas. Measurements are taken along this process route to trace the HEU content all the way to the product stream, ensuring that HEU was down blended. A problem associated with the current traceability measuring algorithm is that it does not account for the time-varying background that is introduced to the system by the movement of the shutter located at the HEU leg of the process. The current way of dealing with that problem is to discard the data for periods when the HEU shutter is open (50% of overall data) because it correlates with the same timeframe in which the direct contribution to background from the HEU shutter was seen. The advanced algorithm presented in this paper allows for continuous measurement of traceability (100%) by accurately accounting for the varying background during the shutter-movement cycle. This algorithm utilizes advanced processing techniques that identify and discriminate the different sources of background radiation, instead of grouping them into one background group for the whole measurement cycle. By using this additional information, the traceability measurement statistics can achieve a greater number of values, thus improving the overall usefulness of these measurements in the BDMS. The effectiveness of the new algorithm was determined by modeling it in a simulation and ensuring that it retained its integrity through a large number of runs, including various shutter-failure conditions. Each run was performed with varying amounts of background radiation from each individual source and with varying traceability counts. The simulations documented in this paper prove that the algorithm can stand up to various transients introduced into the system, such as failure of shutter movement.

  18. UF6 overfilling prevention at Eurodif production Georges Besse plant

    SciTech Connect (OSTI)

    Reneaud, J.M.

    1991-12-31

    Risk of overfilling exists on different equipments of Georges BESSE Plant: cylinders, desublimers and intermediate tanks. The preventive measures are composed of technical devices: desublimers weighing, load monitoring alarms, automatic controls ... and procedures, training, safety organization. In thirteen years of operation, some incidents have occurred but none of them has caused any personal injuries. They are related and discussed. The main factors involved in the Sequoyah fuel facility accident on 1/4/1986 have been analyzed and taken into account.

  19. Benefits of an International Database for UF6 Cylinders

    SciTech Connect (OSTI)

    Babcock, R A; Whitaker, J M; Murphy, J; Oakberg, J

    2008-06-30

    A reasonable expectation regarding the nuclear energy renaissance is that the location of fuel cycle nuclear materials throughout the world will be known. We ask--would an international system for uranium hexafluoride (UF{sub 6}) cylinders provide the effective assurances expected for international fuel supply and of the international fuel centers? This paper introduces the question and discusses the potential benefits of tracking UF{sub 6} cylinders through the development of an international database. The nonproliferation benefits of an international database for UF{sub 6} cylinders being used in the fuel cycle include an enhanced capability to reconcile nuclear material imports and exports. Currently, import and export declarations only require the reporting of total 'rolled up' quantities of nuclear materials contained in all items--not the quantities of materials in individual items like individual UF{sub 6} cylinders. The database could provide supplier countries with more assurance on the location of the UF{sub 6} cylinders they export. Additionally, a comprehensive database on all declared cylinders would be a valuable resource in detecting and recognizing undeclared cylinders. The database could potentially be administered by the IAEA and be accessible to authorized countries around the world. During the nuclear renaissance, the general public, as well as the participants will expect transparency and quality information about movement of nuclear fuel cycle nuclear materials. We will discuss the potential benefits of such a database for the suppliers, inspectorates, and general public.

  20. Read Your E-mail | Argonne National Laboratory

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

    Read Your E-mail All Argonne employees can read their e-mail through the web. Argonne E-Mail service is a robust, reliable electronic communication solution for supporting...

  1. Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Dubrin, J.W.; Rosen, R.S.; Zoller, J.N.; Harri, J.W.; Schwertz, N.L.

    1995-12-01

    The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered, is presented. The long-term management strategy alternatives fall into three broad categories: use, storage, or disposal. Conversion of the depleted UF6 to another form such as oxide or metal is needed to implement most of these alternatives. Likewise, transportation of materials is an integral part of constructing the complete pathway between the current storage condition and ultimate disposition. The analysis of options includes development of pre-conceptual designs; estimates of effluents, wastes, and emissions; specification of resource requirements; and preliminary hazards assessments. The results of this analysis will assist DOE in selecting a strategy by providing the engineering information necessary to evaluate the environmental impacts and costs of implementing the management strategy alternatives.

  2. Field Facilities Contacts for Printing and Mail | Department of Energy

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

    Field Facilities Contacts for Printing and Mail Field Facilities Contacts for Printing and Mail This is the list of DOE field facilities contacts for Printing and Mail as of April 27, 2011. Go to Mail Services Go to Printing Services PDF icon Field_Facilities_Contacts_Print-Mail.pdf More Documents & Publications Director's Perspective by George Miller Tenant Education and Training Fact Sheet: Collaboration of Oak Ridge, Argonne, and Livermore (CORAL

  3. T-618: Debian update for exim4: Mail Transport Agent

    Broader source: Energy.gov [DOE]

    It was discovered that Exim, the default mail transport agent in Debian, uses DKIM data obtain from DNS directly in a format string, potentially allowing malicious mail senders to execute arbitrary code.

  4. Depleted uranium management alternatives

    SciTech Connect (OSTI)

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

    1994-08-01

    This report evaluates two management alternatives for Department of Energy depleted uranium: continued storage as uranium hexafluoride, and conversion to uranium metal and fabrication to shielding for spent nuclear fuel containers. The results will be used to compare the costs with other alternatives, such as disposal. Cost estimates for the continued storage alternative are based on a life-cycle of 27 years through the year 2020. Cost estimates for the recycle alternative are based on existing conversion process costs and Capital costs for fabricating the containers. Additionally, the recycle alternative accounts for costs associated with intermediate product resale and secondary waste disposal for materials generated during the conversion process.

  5. Minutes from the Print and Mail Managers Exchange Forum Teleconferences |

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

    Department of Energy Minutes from the Print and Mail Managers Exchange Forum Teleconferences Minutes from the Print and Mail Managers Exchange Forum Teleconferences Minutes from the Print and Mail Managers Exchange Forum Teleconferences. Contact the Office of Administrative Management and Support at (202) 586-4318 with any questions. Last updated 01/30/14 PDF icon Minutes from the November 21, 2013 Printing and Mail Teleconference PDF icon Minutes from the September 19, 2013 Printing and

  6. Minutes from the January 19, 2011 Printing and Mail Teleconference

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

    January 2010 Printing and Mail Managers Exchange Forum Teleconference Twenty-one individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors Comments/Additions to last Months Minutes No comments. Printing Agenda Items......... Update on the Department-wide FY-2010 Three-Year Plan Dallas Woodruff, Headquarters in formed the group that the Department-wide Printing and Publishing Activities is currently in the concurrence

  7. Minutes from the January 20, 2010 Printing and Mail Teleconference

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

    , 2010 Printing and Mail Managers Exchange Forum Teleconference Twenty-one individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors. Comments/Additions to last Months Minutes Dallas Woodruff, Headquarters opened the meeting by thanking everyone for participating in the today's teleconference. Printing Agenda Items... Update on the Department-wide Printing and Publishing Activities Report Three-Year Plan. Dallas Woodruff,

  8. Minutes from the July 21, 2010 Printing and Mail Teleconference

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

    July 21, 2010 Printing and Mail Managers Exchange Forum Teleconference Twenty-one individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors. Comments/Additions to last Months Minutes Dallas Woodruff, Headquarters opened the meeting by thanking everyone for participating in the today's teleconference. Printing Agenda Items... Update on the Government Printing Office revisions to the Standard Form one (SF!), Twenty-five

  9. Minutes from the March 17, 2010 Printing and Mail Teleconference

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

    March 17, 2010 Printing and Mail Managers Exchange Forum Teleconference Twenty-eight individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors. Comments/Additions to last Months Minutes Dallas Woodruff, Headquarters opened the meeting by thanking everyone for participating in the today's teleconference. Printing Agenda Items... Upcoming Congressional Joint Committee on Printing Commercial Printing Report "JCP Form

  10. Minutes from the May 26, 2010 Printing and Mail Teleconference

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

    26, 2010 Printing and Mail Managers Exchange Forum Teleconference Seventeen individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors. Comments/Additions to last Months Minutes Dallas Woodruff, Headquarters opened the meeting by thanking everyone for participating in the today's teleconference. Printing Agenda Items... Update on the FY 2010, Congressional Joint Committee on Printing Commercial Printing Report "JCP

  11. Minutes from the September 15, 2010 Printing and Mail Teleconference

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

    September 15, 2010 Printing and Mail Managers Exchange Forum Teleconference Twenty-four individuals participated in the Printing and Mail Managers Exchange Forum, which included Printing and Mail Managers and Contractors. Comments/Additions to last Months Minutes Dallas Woodruff, Headquarters opened the meeting by thanking everyone for participating in the today's teleconference. Printing Agenda Items... Upcoming FY 2010 Department-wide Three-Year Plan Dallas Woodruff, Headquarters informed the

  12. Headquarters Program & Staff Office Mailing Addresses | Department of

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

    Energy Headquarters Program & Staff Office Mailing Addresses Headquarters Program & Staff Office Mailing Addresses The following addresses are for delivery of regular mail and small packages: Delivery to the Headquarters buildings in Washington, DC: Name of Individual Title Routing Symbol/Forrestal Building U.S. Department of Energy 1000 Independence Ave., S.W. Washington, DC 20585 Name of Individual Title Routing Symbol/L'Enfant Plaza Building U.S. Department of Energy 1000

  13. Minutes from the May 3, 2012 Printing and Mail Teleconference

    Energy Savers [EERE]

    3, 2012 Printing and Mail Managers Exchange Forum Teleconference Al Majors opened the meeting by introducing Derrick Milner, Program Manager from the General Services...

  14. Data-Driven Mailing Helps Heat Up Untapped Seattle Market

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

    Focus Series Data-Driven Mailing Helps Heat Up Untapped Seattle Market Recognizing owners of oil-heated homes in Seattle, Washington, as a long-untapped market, Community Power Works engaged them through a direct mail campaign in April 2012. Not only did the mailing generate hundreds of sign-ups, but the number of oil-heated homes initiating upgrades increased to 50% in the six months after the mailing. In the interview below, Community Power Works Project Manager Ruth Bell and Program/System

  15. Fully depleted back illuminated CCD

    DOE Patents [OSTI]

    Holland, Stephen Edward (Hercules, CA)

    2001-01-01

    A backside illuminated charge coupled device (CCD) is formed of a relatively thick high resistivity photon sensitive silicon substrate, with frontside electronic circuitry, and an optically transparent backside ohmic contact for applying a backside voltage which is at least sufficient to substantially fully deplete the substrate. A greater bias voltage which overdepletes the substrate may also be applied. One way of applying the bias voltage to the substrate is by physically connecting the voltage source to the ohmic contact. An alternate way of applying the bias voltage to the substrate is to physically connect the voltage source to the frontside of the substrate, at a point outside the depletion region. Thus both frontside and backside contacts can be used for backside biasing to fully deplete the substrate. Also, high resistivity gaps around the CCD channels and electrically floating channel stop regions can be provided in the CCD array around the CCD channels. The CCD array forms an imaging sensor useful in astronomy.

  16. Public Comments Submitted by E-mail | Department of Energy

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

    Public Comments Submitted by E-mail Public Comments Submitted by E-mail In order to gather information and recommendations for the Quadrennial Energy Review, EPSA solicited comments from stakeholders and the general public. The public comments are located on this page and can be sorted by heading, searched by topic using the tags below, or by entering search terms in the search field. Tags EPSA QER Downloads Page Title Name of Organization Name of Submitter Tags

  17. The Future of Electric Vehicles and Arizona State University's MAIL

    Energy Savers [EERE]

    Battery | Department of Energy The Future of Electric Vehicles and Arizona State University's MAIL Battery The Future of Electric Vehicles and Arizona State University's MAIL Battery August 11, 2010 - 4:26pm Addthis Cody Friesen and his team at Arizona State University | Photo Credit Arizona State University Cody Friesen and his team at Arizona State University | Photo Credit Arizona State University Andy Oare Andy Oare Former New Media Strategist, Office of Public Affairs What does this

  18. Mailing Addresses and Information Numbers for Operations, Field, and Site

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

    Offices | Department of Energy About Energy.gov » Mailing Addresses and Information Numbers for Operations, Field, and Site Offices Mailing Addresses and Information Numbers for Operations, Field, and Site Offices Name Telephone Number U.S. Department of Energy Ames Site Office 111 TASF, Iowa State University Ames, Iowa 50011 515-294-9557 U.S. Department of Energy Argonne Site Office 9800 S. Cass Avenue Argonne, IL 60439 630-252-2000 U.S. Department of Energy Berkeley Site Office Berkeley

  19. Mailing Addresses for National Laboratories and Technology Centers |

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

    Department of Energy Mailing Addresses for National Laboratories and Technology Centers Mailing Addresses for National Laboratories and Technology Centers Name Telephone Number U.S. Department of Energy Albany Research Center 1450 Queen Ave. SW Albany, OR 97321-2198 541-967-5892 U.S. Department of Energy Ames Laboratory #311 TASF, Iowa State University Ames, Iowa 50011 515-294-2680 U.S. Department of Energy Argonne National Laboratory (East) 9700 S. Cass Avenue Argonne, IL 60439 630-252-2000

  20. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site

    SciTech Connect (OSTI)

    N /A

    2003-11-28

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Portsmouth site in Ohio (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Portsmouth to a more stable chemical form suitable for use or disposal. The facility would also convert the DUF{sub 6} from the East Tennessee Technology Park (ETTP) site near Oak Ridge, Tennessee. In a Notice of Intent (NOI) published in the Federal Register on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (United States Code, Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (Code of Federal Regulations, Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a Federal Register Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Portsmouth site; from the transportation of all ETTP cylinders (DUF{sub 6}, low-enriched UF6 [LEU-UF{sub 6}], and empty) to Portsmouth; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). An option of shipping the ETTP cylinders to Paducah is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Portsmouth and ETTP sites. A separate EIS (DOE/EIS-0359) evaluates potential environmental impacts for the proposed Paducah conversion facility.

  1. E-mail et Web : pour une navigation sans risque

    ScienceCinema (OSTI)

    None

    2011-10-06

    Présentation orale en français, support visuel en anglais. À travers des exemples concrets, vous consoliderez vos connaissances et pourrez ainsi réajuster vos habitudes concernant l?utilisation sécurisée de votre boîte e-mail et de votre navigateur Web.

  2. Accident Conditions versus Regulatory Test for NRC-Approved UF6 Packages

    SciTech Connect (OSTI)

    MILLS, G. SCOTT; AMMERMAN, DOUGLAS J.; LOPEZ, CARLOS

    2003-01-01

    The Nuclear Regulatory Commission (NRC) approves new package designs for shipping fissile quantities of UF{sub 6}. Currently there are three packages approved by the NRC for domestic shipments of fissile quantities of UF{sub 6}: NCI-21PF-1; UX-30; and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident conditions as described in 10 CFR Part 71. The primary objective of this project was to relate the conditions experienced by these packages in the tests described in 10 CFR Part 71 to conditions potentially encountered in actual accidents and to estimate the probabilities of such accidents. Comparison of the effects of actual accident conditions to 10 CFR Part 71 tests was achieved by means of computer modeling of structural effects on the packages due to impacts with actual surfaces, and thermal effects resulting from test and other fire scenarios. In addition, the likelihood of encountering bodies of water or sufficient rainfall to cause complete or partial immersion during transport over representative truck routes was assessed. Modeled effects, and their associated probabilities, were combined with existing event-tree data, plus accident rates and other characteristics gathered from representative routes, to derive generalized probabilities of encountering accident conditions comparable to the 10 CFR Part 71 conditions. This analysis suggests that the regulatory conditions are unlikely to be exceeded in real accidents, i.e. the likelihood of UF{sub 6} being dispersed as a result of accident impact or fire is small. Moreover, given that an accident has occurred, exposure to water by fire-fighting, heavy rain or submersion in a body of water is even less probable by factors ranging from 0.5 to 8E-6.

  3. High temperature experiments on a 4 tons UF6 container TENERIFE program

    SciTech Connect (OSTI)

    Casselman, C.; Duret, B.; Seiler, J.M.; Ringot, C.; Warniez, P.

    1991-12-31

    The paper presents an experimental program (called TENERIFE) whose aim is to investigate the behaviour of a cylinder containing UF{sub 6} when exposed to a high temperature fire for model validation. Taking into account the experiments performed in the past, the modelization needs further information in order to be able to predict the behaviour of a real size cylinder when engulfed in a 800{degrees}C fire, as specified in the regulation. The main unknowns are related to (1) the UF{sub 6} behaviour beyond the critical point, (2) the relationship between temperature field and internal pressure and (3) the equivalent conductivity of the solid UF{sub 6}. In order to investigate these phenomena in a representative way it is foreseen to perform experiments with a cylinder of real diameter, but reduced length, containing 4 tons of UF{sub 6}. This cylinder will be placed in an electrically heated furnace. A confinement vessel prevents any dispersion of UF{sub 6}. The heat flux delivered by the furnace will be calibrated by specific tests. The cylinder will be changed for each test.

  4. Field Trial of LANL On-Line Advanced Enrichment Monitor for UF6 GCEP

    SciTech Connect (OSTI)

    Ianakiev, Kiril D.; Lombardi, Marcie; MacArthur, Duncan W.; Parker, Robert F.; Smith, Morag K.; Keller, Clifford; Friend, Peter; Dunford, Andrew

    2012-07-13

    The outline of this presentation is: (1) Technology basis of on-line enrichment monitoring; (2) Timescale of trial; (3) Description of installed equipment; (4) Photographs; (5) Results; (6) Possible further development; and (7) Conclusions. Summary of the good things about the Advanced Enrichment Monitor (AEM) performance is: (1) High accuracy - normally better than 1% relative, (2) Active system as accurate as passive system, (3) Fast and accurate detection of enrichment changes, (4) Physics is well understood, (5) Elegant method for capturing pressure signal, and (6) Data capture is automatic, low cost and fast. A couple of negative things are: (1) Some jumps in measured passive enrichment - of around +2% relative (due to clock errors?); and (2) Data handling and evaluation is off-line, expensive and very slow. Conclusions are: (1) LANL AEM is being tested on E23 plant at Capenhurst; (2) The trial is going very well; (3) AEM could detect production of HEU at potentially much lower cost than existing CEMO; (4) AEM can measure {sup 235}U assay accurately; (5) Active system using X-Ray source would avoid need for pressure measurement; (6) Substantial work lies ahead to go from current prototype to a production instrument.

  5. Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program

    SciTech Connect (OSTI)

    Boyer, Brian D; Whitaker, J. Michael; White-Horton, Jessica L.; Durbin, Karyn R.

    2012-07-12

    Thousands of cylinders containing uranium hexafluoride (UF{sub 6}) move around the world from conversion plants to enrichment plants to fuel fabrication plants, and their contents could be very useful to a country intent on diverting uranium for clandestine use. Each of these large cylinders can contain close to a significant quantity of natural uranium (48Y cylinder) or low-enriched uranium (LEU) (30B cylinder) defined as 75 kg {sup 235}U which can be further clandestinely enriched to produce 1.5 to 2 significant quantities of high enriched uranium (HEU) within weeks or months depending on the scale of the clandestine facility. The National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) kicked off a 5-year plan in April 2011 to investigate the concept of a unique identification system for UF{sub 6} cylinders and potentially to develop a cylinder tracking system that could be used by facility operators and the International Atomic Energy Agency (IAEA). The goal is to design an integrated solution beneficial to both industry and inspectorates that would improve cylinder operations at the facilities and provide enhanced capabilities to deter and detect both diversion of low-enriched uranium and undeclared enriched uranium production. The 5-year plan consists of six separate incremental tasks: (1) define the problem and establish the requirements for a unique identification (UID) and monitoring system; (2) develop a concept of operations for the identification and monitoring system; (3) determine cylinder monitoring devices and technology; (4) develop a registry database to support proof-of-concept demonstration; (5) integrate that system for the demonstration; and (6) demonstrate proof-of-concept. Throughout NNSA's performance of the tasks outlined in this program, the multi-laboratory team emphasizes that extensive engagement with industry stakeholders, regulatory authorities and inspectorates is essential to its success.

  6. Status Report on the Passive Neutron Enrichment Meter (PNEM) for UF6 Cylinder Assay

    SciTech Connect (OSTI)

    Miller, Karen A.; Swinhoe, Martyn T.; Menlove, Howard O.; Marlow, Johnna B.

    2012-05-02

    The Passive Neutron Enrichment Meter (PNEM) is a nondestructive assay (NDA) system being developed at Los Alamos National Laboratory (LANL). It was designed to determine {sup 235}U mass and enrichment of uranium hexafluoride (UF{sub 6}) in product, feed, and tails cylinders (i.e., 30B and 48Y cylinders). These cylinders are found in the nuclear fuel cycle at uranium conversion, enrichment, and fuel fabrication facilities. The PNEM is a {sup 3}He-based neutron detection system that consists of two briefcase-sized detector pods. A photograph of the system during characterization at LANL is shown in Fig. 1. Several signatures are currently being studied to determine the most effective measurement and data reduction technique for unfolding {sup 235}U mass and enrichment. The system collects total neutron and coincidence data for both bare and cadmium-covered detector pods. The measurement concept grew out of the success of the Uranium Cylinder Assay System (UCAS), which is an operator system at Rokkasho Enrichment Plant (REP) that uses total neutron counting to determine {sup 235}U mass in UF{sub 6} cylinders. The PNEM system was designed with higher efficiency than the UCAS in order to add coincidence counting functionality for the enrichment determination. A photograph of the UCAS with a 48Y cylinder at REP is shown in Fig. 2, and the calibration measurement data for 30B product and 48Y feed and tails cylinders is shown in Fig. 3. The data was collected in a low-background environment, meaning there is very little scatter in the data. The PNEM measurement concept was first presented at the 2010 Institute of Nuclear Materials Management (INMM) Annual Meeting. The physics design and uncertainty analysis were presented at the 2010 International Atomic Energy Agency (IAEA) Safeguards Symposium, and the mechanical and electrical designs and characterization measurements were published in the ESARDA Bulletin in 2011.

  7. Depleted uranium disposal options evaluation

    SciTech Connect (OSTI)

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

    1994-05-01

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

  8. V-147: IBM Lotus Notes Mail Client Lets Remote Users Execute...

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

    7: IBM Lotus Notes Mail Client Lets Remote Users Execute Java Applets V-147: IBM Lotus Notes Mail Client Lets Remote Users Execute Java Applets May 2, 2013 - 6:00am Addthis...

  9. Beneficial Uses of Depleted Uranium

    SciTech Connect (OSTI)

    Brown, C.; Croff, A.G.; Haire, M. J.

    1997-08-01

    Naturally occurring uranium contains 0.71 wt% {sup 235}U. In order for the uranium to be useful in most fission reactors, it must be enriched the concentration of the fissile isotope {sup 235}U must be increased. Depleted uranium (DU) is a co-product of the processing of natural uranium to produce enriched uranium, and DU has a {sup 235}U concentration of less than 0.71 wt%. In the United States, essentially all of the DU inventory is in the chemical form of uranium hexafluoride (UF{sub 6}) and is stored in large cylinders above ground. If this co-product material were to be declared surplus, converted to a stable oxide form, and disposed, the costs are estimated to be several billion dollars. Only small amounts of DU have at this time been beneficially reused. The U.S. Department of Energy (DOE) has begun the Beneficial Uses of DU Project to identify large-scale uses of DU and encourage its reuse for the primary purpose of potentially reducing the cost and expediting the disposition of the DU inventory. This paper discusses the inventory of DU and its rate of increase; DU disposition options; beneficial use options; a preliminary cost analysis; and major technical, institutional, and regulatory issues to be resolved.

  10. Minutes from the February 23, 2012 Printing and Mail Teleconference

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

    Printing and Mail Managers Exchange Forum Teleconference February 23, 2012 Participants: Headquarters (5) National Energy Technology Laboratory, PA National Security Complex Y-12 (2) Oak Ridge National Laboratory Y-12 Site Office (2) Hanford Site Office Oak Ridge Association University Oak Ridge Operations Office BWXT Pantex Site Office JanTec Corporation, Richland, Washington Los Alamos National Laboratory Chicago Office Bettis Atomic Power Laboratory National Security Technology C1, Las Vegas

  11. Minutes from the October 26, 2011 Printing and Mail Teleconference

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

    October 26, 2011 Printing and Mail Managers Exchange Forum Teleconference Comments/Additions to last Months Minutes No comments. Please note the teleconference minutes were not electronically recorded as in the past. The minutes only consist of information provided to the group by Alvan Majors and Dallas Woodruff of Headquarters on topics listed in the agenda and not any follow-up questions. Printing Agenda Items......... Printing and Publishing Activities Report "Three-Year Plan: Dallas

  12. Mail-Order Metal-Organic Frameworks (MOFs) | Center for Gas

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

    SeparationsRelevant to Clean Energy Technologies | Blandine Jerome Mail-Order Metal-Organic Frameworks (MOFs)

  13. Depleted uranium: A DOE management guide

    SciTech Connect (OSTI)

    1995-10-01

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

  14. EIA - Natural Gas Pipeline Network - Depleted Reservoir Storage

    Gasoline and Diesel Fuel Update (EIA)

    Configuration Depleted Reservoir Storage Configuration About U.S. Natural Gas Pipelines - Transporting Natural Gas based on data through 2007/2008 with selected updates Depleted Production Reservoir Underground Natural Gas Storage Well Configuration Depleted Production Reservoir Storage

  15. DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6...

    Office of Environmental Management (EM)

    Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at Ohio and Kentucky Facilities DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at...

  16. DOE Extends Contract to Operate Depleted Uranium Hexafluoride...

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

    Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants December 24, 2015 -...

  17. Enterprise Assessments Targeted Review of the Paducah Depleted...

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

    Review of the Paducah Depleted Uranium Hexafluoride Conversion Facility Fire Protection Program - September 2015 Enterprise Assessments Targeted Review of the Paducah Depleted...

  18. EIA - Natural Gas Pipeline Network - Depleted Reservoir Storage...

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

    Gas based on data through 20072008 with selected updates Depleted Production Reservoir Underground Natural Gas Storage Well Configuration Depleted Production Reservoir Storage

  19. Clustering and Mechanics in Dense Depletion and Thermal Gels...

    Office of Scientific and Technical Information (OSTI)

    Clustering and Mechanics in Dense Depletion and Thermal Gels Citation Details In-Document Search Title: Clustering and Mechanics in Dense Depletion and Thermal Gels Authors: ...

  20. Data-Driven Mailing Helps Heat Up Untapped Seattle Market | Department...

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

    Mailing Helps Heat Up Untapped Seattle Market Abridged transcript of an interview with Community Power Works Project Manager Ruth Bell and ProgramSystem Analyst Vince Schueler...

  1. U.S. DEPARTMENT OF ENERGY RECEIPT FOR CONTROLLED MAIL PARCEL SERVICE

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

    HQ F 1410.2 (06-93) U.S. DEPARTMENT OF ENERGY RECEIPT FOR CONTROLLED MAIL PARCEL SERVICE (Receipt No.) MAIL STATION: DATE: TO: NAME: ROUTING SYMBOL: FROM: DOE Mail Facility, Office of Administration Services 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. ITEM NO. ITEM NO. ITEM NO. SIGN AND RETURN WITHIN 24 HOURS TO AVOID TRACER ACTION TO DOE MAIL FACILITY (Stamp Location) RECEIVED BY: DATE: Printed with soy ink on recycled paper

  2. U-157: Ruby Mail Gem Directory Traversal and Shell Command Injection Vulnerabilities

    Broader source: Energy.gov [DOE]

    Some vulnerabilities have been reported in the Mail gem for Ruby, which can be exploited by malicious people to manipulate certain data and compromise a vulnerable system.

  3. Neutral depletion and the helicon density limit

    SciTech Connect (OSTI)

    Magee, R. M.; Galante, M. E.; Carr, J. Jr.; Lusk, G.; McCarren, D. W.; Scime, E. E.

    2013-12-15

    It is straightforward to create fully ionized plasmas with modest rf power in a helicon. It is difficult, however, to create plasmas with density >10{sup 20} m{sup ?3}, because neutral depletion leads to a lack of fuel. In order to address this density limit, we present fast (1 MHz), time-resolved measurements of the neutral density at and downstream from the rf antenna in krypton helicon plasmas. At the start of the discharge, the neutral density underneath the antenna is reduced to 1% of its initial value in 15 ?s. The ionization rate inferred from these data implies that the electron temperature near the antenna is much higher than the electron temperature measured downstream. Neutral density measurements made downstream from the antenna show much slower depletion, requiring 14 ms to decrease by a factor of 1/e. Furthermore, the downstream depletion appears to be due to neutral pumping rather than ionization.

  4. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

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

    2000-06-01

    The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

  5. The ultimate disposition of depleted uranium

    SciTech Connect (OSTI)

    Lemons, T.R.

    1991-12-31

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

  6. Carbon sequestration in depleted oil shale deposits

    DOE Patents [OSTI]

    Burnham, Alan K; Carroll, Susan A

    2014-12-02

    A method and apparatus are described for sequestering carbon dioxide underground by mineralizing the carbon dioxide with coinjected fluids and minerals remaining from the extraction shale oil. In one embodiment, the oil shale of an illite-rich oil shale is heated to pyrolyze the shale underground, and carbon dioxide is provided to the remaining depleted oil shale while at an elevated temperature. Conditions are sufficient to mineralize the carbon dioxide.

  7. Mario Molina, Chlorofluorocarbons (CFCs), and Ozone Depletion

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

    Mario Molina, Chlorofluorocarbons (CFCs), and Ozone Depletion Resources with Additional Information In 1973 Mario Molina ... was a postdoctoral researcher working in the laboratory of F. Sherwood Rowland at the University of California at Irvine ... when he made an unsettling discovery. He had been investigating a class of compounds called chlorofluorocarbons, or CFCs. CFCs were used as refrigerants, aerosol sprays, and in making plastic foams. Molina wondered what happened to them once they

  8. U.S. Postal Service General Mail Facility, San Diego, California |

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

    Department of Energy Postal Service General Mail Facility, San Diego, California U.S. Postal Service General Mail Facility, San Diego, California Overview The U.S. Postal Service (USPS) was the first Federal agency to award a shared energy savings (SES) contract (now known as energy savings performance contracts). The contract was awarded to the Co-Energy Group in December 1987 for a lighting retrofit at the USPS General Mail Facility in San Diego, California. The local utility, San Diego

  9. Disposition of DOE Excess Depleted Uranium, Natural Uranium, and

    Office of Environmental Management (EM)

    Low-Enriched Uranium | Department of Energy Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium The U.S. Department of Energy (DOE) owns and manages an inventory of depleted uranium (DU), natural uranium (NU), and low-enriched uranium (LEU) that is currently stored in large cylinders as depleted uranium hexafluoride (DUF6), natural uranium hexafluoride (NUF6), and

  10. Sign Up for E-mail Updates | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Sign Up for E-mail Updates Materials Sciences and Engineering (MSE) Division MSE Home About Staff What's New Research Areas Reports and Activities Science Highlights Principal Investigators' Meetings BES Home What's New Sign Up for E-mail Updates Print Text Size: A A A FeedbackShare Page The Division has a "Dear Colleague" email list, which is used to circulate general information such as funding opportunity announcements and administrative information such as position openings. To

  11. Legal and policy issues associated with monitoring employee E-mail

    SciTech Connect (OSTI)

    Segura, M.A.; Rither, A.C.

    1997-01-01

    This paper examines the legal issues involved with employer monitoring of employee e-mail. In addition to identifying pertinent legal issues, the paper provides guidelines that will help the Pacific Northwest National Laboratory (PNNL) establish a program for monitoring outgoing e-mail to insure compliance with company policies, particularly those regarding protection of trade secrets and proprietary information, and to comply with the Department of Energy`s (DOE) procedures for protecting Export Controlled Information (ECI). Electronic communication has allowed companies to enhance efficiency, responsiveness and effectiveness. E-mail allows employees to transmit all types of data to other individuals inside and outside of their companies. The ease with which information can be transmitted by e-mail has placed trade secrets, proprietary information, and other sensitive data at risk from inadvertent disclosure by employees. As employers attempt to protect their interests through measures such as monitoring e-mail, they may expose themselves to liability under federal and state laws for violating employee privacy. Business use of e-mail has proliferated so rapidly that the federal and state legal systems have not been able to adequately address the issues arising out of its use in the workplace.

  12. Evaluation of a RF-Based Approach for Tracking UF6 Cylinders at a Uranium Enrichment Plant

    SciTech Connect (OSTI)

    Pickett, Chris A; Younkin, James R; Kovacic, Donald N; Laughter, Mark D; Hines, Jairus B; Boyer, Brian; Martinez, B.

    2008-01-01

    Approved industry-standard cylinders are used globally to handle and store uranium hexafluoride (UF{sub 6}) feed, product, tails, and samples at uranium enrichment plants. The International Atomic Energy Agency (IAEA) relies on time-consuming physical inspections to verify operator declarations and detect possible diversion of UF{sub 6}. Development of a reliable, automated, and tamper-resistant system for near real-time tracking and monitoring UF{sub 6} cylinders (as they move within an enrichment facility) would greatly improve the inspector function. This type of system can reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a proof-of-concept approach that was designed to evaluate the feasibility of using radio frequency (RF)-based technologies to track individual UF{sub 6} cylinders throughout a portion of their life cycle, and thus demonstrate the potential for improved domestic accountability of materials, and a more effective and efficient method for application of site-level IAEA safeguards. The evaluation system incorporates RF-based identification devices (RFID) which provide a foundation for establishing a reliable, automated, and near real-time tracking system that can be set up to utilize site-specific, rules-based detection algorithms. This paper will report results from a proof-of-concept demonstration at a real enrichment facility that is specifically designed to evaluate both the feasibility of using RF to track cylinders and the durability of the RF equipment to survive the rigors of operational processing and handling. The paper also discusses methods for securely attaching RF devices and describes how the technology can effectively be layered with other safeguard systems and approaches to build a robust system for detecting cylinder diversion. Additionally, concepts for off-site tracking of cylinders are described.

  13. Enterprise Assessments Targeted Review of the Paducah Depleted Uranium

    Office of Environmental Management (EM)

    Hexafluoride Conversion Facility Fire Protection Program - September 2015 | Department of Energy Review of the Paducah Depleted Uranium Hexafluoride Conversion Facility Fire Protection Program - September 2015 Enterprise Assessments Targeted Review of the Paducah Depleted Uranium Hexafluoride Conversion Facility Fire Protection Program - September 2015 September 2015 Targeted Review of the Fire Protection Program at the Paducah Depleted Uranium Hexafluoride Conversion Facility The U.S.

  14. DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion

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

    Plants | Department of Energy Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants December 24, 2015 - 11:06am Addthis LEXINGTON, Ky. (Dec. 24, 2015) - The U.S. Department of Energy's Office of Environmental Management (EM) today announced it is extending its contract for Operations of Depleted Uranium Hexafluoride (DUF6) Conversion Facilities at Paducah, Kentucky and Portsmouth, Ohio for a

  15. DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion

    Office of Environmental Management (EM)

    Plants | Department of Energy Contract to Operate Depleted Uranium Hexafluoride Conversion Plants DOE Extends Contract to Operate Depleted Uranium Hexafluoride Conversion Plants December 24, 2015 - 10:00am Addthis Media Contact Brad Mitzelfelt, 859-219-4035 brad.mitzelfelt@lex.doe.gov LEXINGTON, Ky. - The U.S. Department of Energy's Office of Environmental Management (EM) today announced it is extending its contract for Operations of Depleted Uranium Hexafluoride (DUF6) Conversion Facilities

  16. University of Michigan adds Depletion Capability to MPACT

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

    of Michigan researchers Ben Collins, Ang Zhu, Brendan Kochunas, and Tom Downar. The numerical methods to implement nuclide point depletion and integrate a time dependent...

  17. Gas generation matrix depletion quality assurance project plan

    SciTech Connect (OSTI)

    NONE

    1998-05-01

    The Los Alamos National Laboratory (LANL) is to provide the necessary expertise, experience, equipment and instrumentation, and management structure to: Conduct the matrix depletion experiments using simulated waste for quantifying matrix depletion effects; and Conduct experiments on 60 cylinders containing simulated TRU waste to determine the effects of matrix depletion on gas generation for transportation. All work for the Gas Generation Matrix Depletion (GGMD) experiment is performed according to the quality objectives established in the test plan and under this Quality Assurance Project Plan (QAPjP).

  18. Recovery of Depleted Uranium Fragments from Soil

    SciTech Connect (OSTI)

    Farr, C.P.; Alecksen, T.J.; Heronimus, R.S.; Simonds, M.H.; Farrar, D.R.; Baker, K.R.; Miller, M.L.

    2008-07-01

    A cost-effective method was demonstrated for recovering depleted uranium (DU) fragments from soil. A compacted clean soil pad was prepared adjacent to a pile of soil containing DU fragments. Soil from the contaminated pile was placed on the pad in three-inch lifts using conventional construction equipment. Each lift was scanned with an automatic scanning system consisting of an array of radiation detectors coupled to a detector positioning system. The data were downloaded into ArcGIS for data presentation. Areas of the pad exhibiting scaler counts above the decision level were identified as likely locations of DU fragments. The coordinates of these locations were downloaded into a PDA that was wirelessly connected to the positioning system. The PDA guided technicians to the locations where hand-held trowels and shovels were used to remove the fragments. After DU removal, the affected areas were re-scanned and the new data patched into the data base to replace the original data. This new data set along with soil sample results served as final status survey data. (authors)

  19. DOE Selects Contractor for Depleted Hexafluoride Conversion Project...

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

    DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati ...

  20. Hyperspectral stimulated emission depletion microscopy and methods of use thereof

    DOE Patents [OSTI]

    Timlin, Jerilyn A; Aaron, Jesse S

    2014-04-01

    A hyperspectral stimulated emission depletion ("STED") microscope system for high-resolution imaging of samples labeled with multiple fluorophores (e.g., two to ten fluorophores). The hyperspectral STED microscope includes a light source, optical systems configured for generating an excitation light beam and a depletion light beam, optical systems configured for focusing the excitation and depletion light beams on a sample, and systems for collecting and processing data generated by interaction of the excitation and depletion light beams with the sample. Hyperspectral STED data may be analyzed using multivariate curve resolution analysis techniques to deconvolute emission from the multiple fluorophores. The hyperspectral STED microscope described herein can be used for multi-color, subdiffraction imaging of samples (e.g., materials and biological materials) and for analyzing a tissue by Forster Resonance Energy Transfer ("FRET").

  1. Stimulation Emission Depletion (STED) microscopy | The Ames Laboratory

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

    Stimulation Emission Depletion (STED) microscopy What is STED? Stimulation Emission Depletion (STED) microscopy is a super resolution microscopy tool that captures super resolution images on a nanometer scale. A donut-shaped red light switches off surrounding molecules, allowing only those in the center to fluoresce. At the nanoscale, light microscopes cannot tell features apart. Because light moves as waves and the particles of light are so close together, the lens used cannot focus all of the

  2. Retrieval of buried depleted uranium from the T-1 trench

    SciTech Connect (OSTI)

    Burmeister, M.; Castaneda, N.; Greengard, T. |; Hull, C.; Barbour, D.; Quapp, W.J.

    1998-07-01

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

  3. DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support

    Office of Environmental Management (EM)

    | Department of Energy Contractor for Depleted Hexafluoride Conversion Project Support DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support March 25, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) today awarded a competitive small business task order to Navarro Research and Engineering Inc. of Oak Ridge, Tennessee. The award is a $22 million, time and materials task order with a

  4. Depleted Uranium Hexafluoride (DUF6) Fully Operational at the Portsmouth

    Office of Environmental Management (EM)

    and Paducah Gaseous Diffusion Sites | Department of Energy Depleted Uranium Hexafluoride (DUF6) Fully Operational at the Portsmouth and Paducah Gaseous Diffusion Sites Depleted Uranium Hexafluoride (DUF6) Fully Operational at the Portsmouth and Paducah Gaseous Diffusion Sites October 20, 2011 - 9:16am Addthis When Babcock & Wilcox Conversion Services took over the DUF6 Project on March 29 of this year, the company had one thing in mind: Bring all seven conversion lines at both plants to

  5. Via E-Mail Michael Li Electricity Policy Specialist U.S. Department of Energy

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

    November 1, 2010 Via E-Mail Michael Li Electricity Policy Specialist U.S. Department of Energy Office of Electricity Delivery and Energy Reliability 1000 Independence Avenue, SW Washington, DC 20585 smartgridpolicy@hq.doe.gov Re: Smart Grid RFI: Addressing Policy And Logistical Challenges Dear Mr. Li: On behalf of the Association of Home Appliance Manufacturers (AHAM), I would like to provide our comments on the Smart Grid RFI: Addressing Policy and Logistical Challenges, 75 Fed. Reg. 57,006

  6. By E-Mail Daniel Cohen Assistant General Counsel for Legislation, Regulation, and Energy Efficiency

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

    June 19, 2012 By E-Mail Daniel Cohen Assistant General Counsel for Legislation, Regulation, and Energy Efficiency U.S. Department of Energy Office of the General Counsel 1000 Independence Ave., SW Washington, D.C. 20585 Regulatory.Review@hq.doe.gov Re: Regulatory Burden RFI Dear Mr. Cohen: The Association of Home Appliance Manufacturers (AHAM) respectfully submits the following comments to the Department of Energy (DOE) on its Regulatory Burden RFI, 77 Fed. Reg. 28518 (May 15, 2012). AHAM

  7. By E-Mail Daniel Cohen Assistant General Counsel for Legislation, Regulation, and Energy Efficiency

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

    21, 2011 By E-Mail Daniel Cohen Assistant General Counsel for Legislation, Regulation, and Energy Efficiency U.S. Department of Energy Office of the General Counsel 1000 Independence Ave., SW Room 6A245 Washington, D.C. 20585 Regulatory.Review@hq.doe.gov Re: Regulatory Burden RFI Dear Mr. Cohen: The Association of Home Appliance Manufacturers (AHAM) respectfully submits the following comments to the Department of Energy (DOE) on its Request for Information on reducing regulatory burden, 76 Fed.

  8. CERTIFIED MAIL RETURN RECEIPT REQUESTED Dr. Chi-Chang Kao Laboratory Director

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

    , 2014 CERTIFIED MAIL RETURN RECEIPT REQUESTED Dr. Chi-Chang Kao Laboratory Director SLAC National Accelerator Laboratory Stanford University 2575 Sand Hill Road Menlo Park, California 94025-7015 WEA-2014-05 Dear Dr. Kao: This letter refers to the Department of Energy's (DOE) investigation into the facts and circumstances associated with the implementation of worker safety and health program requirements related to laser and electron beam equipment at SLAC National Accelerator Laboratory (SLAC)

  9. Depleted uranium as a backfill for nuclear fuel waste package

    DOE Patents [OSTI]

    Forsberg, Charles W.

    1998-01-01

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

  10. Depleted uranium as a backfill for nuclear fuel waste package

    DOE Patents [OSTI]

    Forsberg, C.W.

    1998-11-03

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

  11. Effect of Shim Arm Depletion in the NBSR

    SciTech Connect (OSTI)

    Hanson A. H.; Brown N.; Diamond, D.J.

    2013-02-22

    The cadmium shim arms in the NBSR undergo burnup during reactor operation and hence, require periodic replacement. Presently, the shim arms are replaced after every 25 cycles to guarantee they can maintain sufficient shutdown margin. Two prior reports document the expected change in the 113Cd distribution because of the shim arm depletion. One set of calculations was for the present high-enriched uranium fuel and the other for the low-enriched uranium fuel when it was in the COMP7 configuration (7 inch fuel length vs. the present 11 inch length). The depleted 113Cd distributions calculated for these cores were applied to the current design for an equilibrium low-enriched uranium core. This report details the predicted effects, if any, of shim arm depletion on the shim arm worth, the shutdown margin, power distributions and kinetics parameters.

  12. 2575 Sand Hill Road * Mail Stop 103 * Menlo Park, CA 94025-7015

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

    575 Sand Hill Road * Mail Stop 103 * Menlo Park, CA 94025-7015 650-926-2288 * Fax 650-926-4695 SLAC is operated by Stanford University for the U.S. Department of Energy SLAC National Accelerator Laboratory LCLS Users' Newsletter, Issue 1, April 8, 2009 Dear Colleagues: We would like to present to you the first issue of the LCLS Users' Newsletter. We are pleased to report that we have recruited Henia Kamil as the LCLS User Research Administrator Manager. Please join me in welcoming Henia and feel

  13. Report Period: EIA ID NUMBER: Appendix A: Mailing Address: Appendix B:

    Gasoline and Diesel Fuel Update (EIA)

    Report Period: EIA ID NUMBER: Appendix A: Mailing Address: Appendix B: Zip Code - Secure File Transfer option available at: - - - - Email form to: OOG.SURVEYS@eia.doe.gov Fax form to: (202) 586-9772 Email address: Oil & Gas Survey U.S. Department of Energy Ben Franklin Station PO Box 279 Washington, DC 20044-0279 Questions? Call toll free: 1-800-638-8812 1. Total Acquisitions (Enter the total volume of foreign crude oil acquired during the report month for importation into the United States.

  14. Mail-Order Metal-Organic Frameworks (MOFs): Designing Isoreticular MOF-5

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

    Analogues Comprising Commercially Available Organic Molecules | Center for Gas SeparationsRelevant to Clean Energy Technologies | Blandine Jerome Mail-Order Metal-Organic Frameworks (MOFs): Designing Isoreticular MOF-5 Analogues Comprising Commercially Available Organic Molecules Previous Next List R. L. Martin, L.-C. Lin, K. Jariwala, B. Smit, and M. Haranczyk, J Phys Chem C, 117, 12159-12167 (2013) DOI: 10.1021/jp401920y jp-2013-01920y_0010 Abstract Metal-organic frameworks (MOFs), a class

  15. EIS-0269: Long-Term Management of Depleted Uranium Hexaflouride

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) prepared this programmatic environmental impact statement to assess the potential impacts of alternative management strategies for depleted uranium hexafluoride currently stored at three DOE sites: Paducah site near Paducah, Kentucky; Portsmouth site near Portsmouth, Ohio; and K-25 site on the Oak Ridge Reservation in Oak Ridge, Tennessee.

  16. CRDIAC: Coupled Reactor Depletion Instrument with Automated Control

    SciTech Connect (OSTI)

    Steven K. Logan

    2012-08-01

    When modeling the behavior of a nuclear reactor over time, it is important to understand how the isotopes in the reactor will change, or transmute, over that time. This is especially important in the reactor fuel itself. Many nuclear physics modeling codes model how particles interact in the system, but do not model this over time. Thus, another code is used in conjunction with the nuclear physics code to accomplish this. In our code, Monte Carlo N-Particle (MCNP) codes and the Multi Reactor Transmutation Analysis Utility (MRTAU) were chosen as the codes to use. In this way, MCNP would produce the reaction rates in the different isotopes present and MRTAU would use cross sections generated from these reaction rates to determine how the mass of each isotope is lost or gained. Between these two codes, the information must be altered and edited for use. For this, a Python 2.7 script was developed to aid the user in getting the information in the correct forms. This newly developed methodology was called the Coupled Reactor Depletion Instrument with Automated Controls (CRDIAC). As is the case in any newly developed methodology for modeling of physical phenomena, CRDIAC needed to be verified against similar methodology and validated against data taken from an experiment, in our case AFIP-3. AFIP-3 was a reduced enrichment plate type fuel tested in the ATR. We verified our methodology against the MCNP Coupled with ORIGEN2 (MCWO) method and validated our work against the Post Irradiation Examination (PIE) data. When compared to MCWO, the difference in concentration of U-235 throughout Cycle 144A was about 1%. When compared to the PIE data, the average bias for end of life U-235 concentration was about 2%. These results from CRDIAC therefore agree with the MCWO and PIE data, validating and verifying CRDIAC. CRDIAC provides an alternative to using ORIGEN-based methodology, which is useful because CRDIAC's depletion code, MRTAU, uses every available isotope in its depletion, unlike ORIGEN, which only depletes the isotopes specified by the user. This means that depletions done by MRTAU more accurately reflect reality. MRTAU also allows the user to build new isotope data sets, which means any isotope with nuclear data could be depleted, something that would help predict the outcomes of nuclear reaction testing in materials other than fuel, like beryllium or gold.

  17. 1,2,3-D Diffusion Depletion Multi-Group

    Energy Science and Technology Software Center (OSTI)

    1992-04-20

    CITATION is designed to solve problems using the finite difference representation of neutron diffusion theory, treating up to three space dimensions with arbitrary group to group scattering. X-y-z, theta-r-z, hexagonal z, and triagonal z geometries may be treated. Depletion problems may be solved and fuel managed for multi-cycle analysis. Extensive first order perturbation results may be obtained given microscopic data and nuclide concentrations. Statics problems may be solved and perturbation results obtained with microscopic data.

  18. High-voltage compatible, full-depleted CCD

    DOE Patents [OSTI]

    Holland, Stephen Edward (Hercules, CA)

    2007-09-18

    A charge coupled device for detecting electromagnetic and particle radiation is described. The device includes a high-resistivity semiconductor substrate, buried channel regions, gate electrode circuitry, and amplifier circuitry. For good spatial resolution and high performance, especially when operated at high voltages with full or nearly full depletion of the substrate, the device can also include a guard ring positioned near channel regions, a biased channel stop, and a biased polysilicon electrode over the channel stop.

  19. Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions

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

    Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions At the direction of Energy Secretary Steven Chu, over many months, the Energy Department (DOE) has been working closely with Energy Northwest (ENW), the Tennessee Valley Authority (TVA), and USEC Inc. (USEC) to develop a plan to address the challenges at USEC's Paducah Gaseous Diffusion Plant (GDP) that advances America's national security interests, protects taxpayers, and provides benefits for TVA and the Bonneville

  20. Accounting for Depletion of Oil and Gas Resources in Malaysia

    SciTech Connect (OSTI)

    Othman, Jamal Jafari, Yaghoob

    2012-12-15

    Since oil and gas are non-renewable resources, it is important to identify the extent to which they have been depleted. Such information will contribute to the formulation and evaluation of appropriate sustainable development policies. This paper provides an assessment of the changes in the availability of oil and gas resources in Malaysia by first compiling the physical balance sheet for the period 2000-2007, and then assessing the monetary balance sheets for the said resource by using the Net Present Value method. Our findings show serious reduction in the value of oil reserves from 2001 to 2005, due to changes in crude oil prices, and thereafter the depletion rates decreased. In the context of sustainable development planning, albeit in the weak sustainability sense, it will be important to ascertain if sufficient reinvestments of the estimated resource rents in related or alternative capitals are being attempted by Malaysia. For the study period, the cumulative resource rents were to the tune of RM61 billion. Through a depletion or resource rents policy, the estimated quantum may guide the identification of a reinvestment threshold (after considering needed capital investment for future development of the industry) in light of ensuring the future productive capacity of the economy at the time when the resource is exhausted.

  1. Next Generations Safeguards Initiative: The Life of a Cylinder

    SciTech Connect (OSTI)

    Morgan, James B; White-Horton, Jessica L

    2012-01-01

    The U.S. Department of Energy/National Nuclear Security Administration Office of Nonproliferation and International Security's Next Generation Safeguards Initiative (NGSI) has begun a program based on a five-year plan to investigate the concept of a global monitoring scheme that uniquely identifies uranium hexafluoride (UF6) cylinders and their locations throughout the life cycle. A key initial activity in the NGSI program is to understand and document the 'life of a UF6 cylinder' from cradle to grave. This document describes the life of a UF6 cylinder and includes cylinder manufacture and procurement processes as well as cylinder-handling and operational practices at conversion, enrichment, fuel fabrication, and depleted UF6 conversion facilities. The NGSI multiple-laboratory team is using this document as a building block for subsequent tasks in the five-year plan, including development of the functional requirements for cylinder-tagging and tracking devices.

  2. Accelerated Depletion: Assessing Its Impacts on Domestic Oil and Natural Gas Prices and Production

    Reports and Publications (EIA)

    2000-01-01

    Analysis of the potential impacts of accelerated depletion on domestic oil and natural gas prices and production.

  3. Inhibition of lytic infection of pseudorabies virus by arginine depletion

    SciTech Connect (OSTI)

    Wang, H.-C. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Kao, Y.-C. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Chang, T-J. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Wong, M.-L. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China)]. E-mail: mlwong@dragon.nchu.edu.tw

    2005-08-26

    Pseudorabies virus (PRV) is a member of Alphahepesviruses; it is an enveloped virus with a double-stranded DNA genome. Polyamines (such as spermine and spermidine) are ubiquitous in animal cells and participate in cellular proliferation and differentiation. Previous results of our laboratory showed that the PRV can accomplish lytic infection either in the presence of exogenous spermine (or spermidine) or depletion of cellular polyamines. The amino acid arginine is a precursor of polyamine biosynthesis. In this work, we investigated the role of arginine in PRV infection. It was found that the plaque formation of PRV was inhibited by arginase (enzyme catalyzing the conversion of arginine into ornithine and urea) treatment whereas this inhibition can be reversed by exogenous arginine, suggesting that arginine is essential for PRV proliferation. Western blotting was conducted to study the effect of arginine depletion on the levels of structural proteins of PRV in virus-infected cells. Four PRV structural proteins (gB, gE, UL47, and UL48) were chosen for examination, and results revealed that the levels of viral proteins were obviously reduced in long time arginase treatment. However, the overall protein synthesis machinery was apparently not influenced by arginase treatment either in mock or PRV-infected cells. Analyzing with native gel, we found that arginase treatment affected the mobility of PRV structural proteins, suggesting the conformational change of viral proteins by arginine depletion. Heat shock proteins, acting as molecular chaperons, participate in protein folding and translocation. Our results demonstrated that long time arginase treatment could reduce the expression of cellular heat shock proteins 70 (hsc70 and hsp70), and transcriptional suppression of heat shock protein 70 gene promoter was one of the mechanisms involved in this reduced expression.

  4. Depleted uranium storage and disposal trade study: Summary report

    SciTech Connect (OSTI)

    Hightower, J.R.; Trabalka, J.R.

    2000-02-01

    The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

  5. A more accurate and penetrating method to measure the enrichment and mass of UF6 storage containers using passive neutron self-interrogation

    SciTech Connect (OSTI)

    Menlove, Howard O; Swinhoe, Martyn T; Miller, Karen A

    2010-01-01

    This paper describes an unattended mode neutron measurement that can provide the enrichment of the uranium in UF{sub 6} cylinders. The new passive neutron measurement provides better penetration into the uranium mass than prior gamma-ray enrichment measurement methods. The Passive Neutron Enrichment Monitor (PNEM) provides a new measurement technique that uses passive neutron totals and coincidence counting together with neutron self-interrogation to measure the enrichment in the cylinders. The measurement uses the neutron rates from two detector pods. One of the pods has a bare polyethylene surface next to the cylinder and the other polyethylene surface is covered with Cd to prevent thermal neutrons from returning to the cylinder. The primary neutron source from the enriched UF{sub 6} is the alpha-particle decay from the {sub 234}U that interacts with the fluorine to produce random neutrons. The singles neutron counting rate is dominated by the {sub 234}U neutrons with a minor contribution from the induced fissions in the {sub 235}U. However, the doubles counting rate comes primarily from the induced fissions (i.e., multiplication) in the {sub 235}U in enriched uranium. The PNEM concept makes use of the passive neutrons that are initially produced from the {sub 234}U reactions that track the {sub 235}U enrichment during the enrichment process. The induced fission reactions from the thermal-neutron albedo are all from the {sub 235}U and provide a measurement of the {sub 235}U. The Cd ratio has the desirable feature that all of the thermal-neutron-induced fissions in {sub 235}U are independent of the original neutron source. Thus, the ratio is independent of the uranium age, purity, and prior reactor history.

  6. Defining the needs for non-destructive assay of UF6 feed, product, and tails at gas centrifuge enrichment plants and possible next steps

    SciTech Connect (OSTI)

    Boyer, Brian D; Swinhoe, Martyn T; Moran, Bruce W; Lebrun, Alain

    2009-01-01

    Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to detect undeclared LEU production with adequate detection probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of UF{sub 6} bulk material used in the process of enrichment at GCEPS. The inspectors also take destructive assay (DA) samples for analysis off-site which provide accurate, on the order of 0.1 % to 0.5% uncertainty, data on the enrichment of the UF{sub 6} feed, tails, and product. However, DA sample taking is a much more labor intensive and resource intensive exercise for the operator and inspector. Furthermore, the operator must ship the samples off-site to the IAEA laboratory which delays the timeliness of the results and contains the possibility of the loss of the continuity of knowledge of the samples during the storage and transit of the material. Use of the IAEA's inspection sampling algorithm shows that while total sample size is fixed by the total population of potential samples and its intrinsic qualities, the split of the samples into NDA or DA samples is determined by the uncertainties in the NDA measurements. Therefore, the larger the uncertainties in the NDA methods, more of the sample taken must be DA samples. Since the DA sampling is arduous and costly, improvements in NDA methods would reduce the number of DA samples needed. Furthermore, if methods of on-site analysis of the samples could be developed that have uncertainties in the 1-2% range, a lot of the problems inherent in DA sampling could be removed. The use of an unattended system that could give an overview of the entire process giving complementary data on the enrichment process as well as accurate measures of enrichment and weights of the UF{sub 6} feed, tails, and product would be a major step in enhancing the ability of NDA beyond present attended systems. The possibility of monitoring the feed, tails, and product header pipes in such a way as to gain safeguards relevant flow and enrichment information without compromising the intellectual property of the operator including proprietary equipment and operational parameters would be a huge step forward. This paper contains an analysis of possible improvements in unattended and attended NDA systems including such process monitoring and possible on-site analysis of DA samples that could reduce the uncertainty of the inspector measurements reducing the difference between the operator's and inspector's measurements providing more effective and efficient IAEA GeEPs safeguards.

  7. Results from a "Proof-of-Concept" Demonstration of RF-Based Tracking of UF6 Cylinders during a Processing Operation at a Uranium Enrichment Plant

    SciTech Connect (OSTI)

    Pickett, Chris A; Kovacic, Donald N; Whitaker, J Michael; Younkin, James R; Hines, Jairus B; Laughter, Mark D; Morgan, Jim; Carrick, Bernie; Boyer, Brian; Whittle, K.

    2008-01-01

    Approved industry-standard cylinders are used globally for processing, storing, and transporting uranium hexafluoride (UF{sub 6}) at uranium enrichment plants. To ensure that cylinder movements at enrichment facilities occur as declared, the International Atomic Energy Agency (IAEA) must conduct time-consuming periodic physical inspections to validate facility records, cylinder identity, and containment. By using a robust system design that includes the capability for real-time unattended monitoring (of cylinder movements), site-specific rules-based event detection algorithms, and the capability to integrate with other types of monitoring technologies, one can build a system that will improve overall inspector effectiveness. This type of monitoring system can provide timely detection of safeguard events that could be used to ensure more timely and appropriate responses by the IAEA. It also could reduce reliance on facility records and have the additional benefit of enhancing domestic safeguards at the installed facilities. This paper will discuss the installation and evaluation of a radio-frequency- (RF-) based cylinder tracking system that was installed at a United States Enrichment Corporation Centrifuge Facility. This system was installed primarily to evaluate the feasibility of using RF technology at a site and the operational durability of the components under harsh processing conditions. The installation included a basic system that is designed to support layering with other safeguard system technologies and that applies fundamental rules-based event processing methodologies. This paper will discuss the fundamental elements of the system design, the results from this site installation, and future efforts needed to make this technology ready for IAEA consideration.

  8. Including environmental concerns in management strategies for depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Goldberg, M.; Avci, H.I.; Bradley, C.E.

    1995-12-31

    One of the major programs within the Office of Nuclear Energy, Science, and Technology of the US Department of Energy (DOE) is the depleted uranium hexafluoride (DUF{sub 6}) management program. The program is intended to find a long-term management strategy for the DUF{sub 6} that is currently stored in approximately 46,400 cylinders at Paducah, KY; Portsmouth, OH; and Oak Ridge, TN, USA. The program has four major components: technology assessment, engineering analysis, cost analysis, and the environmental impact statement (EIS). From the beginning of the program, the DOE has incorporated the environmental considerations into the process of strategy selection. Currently, the DOE has no preferred alternative. The results of the environmental impacts assessment from the EIS, as well as the results from the other components of the program, will be factored into the strategy selection process. In addition to the DOE`s current management plan, other alternatives continued storage, reuse, or disposal of depleted uranium, will be considered in the EIS. The EIS is expected to be completed and issued in its final form in the fall of 1997.

  9. Ozone-depleting-substance control and phase-out plan

    SciTech Connect (OSTI)

    Nickels, J.M.; Brown, M.J.

    1994-07-01

    Title VI of the Federal Clean Air Act Amendments of 1990 requires regulation of the use and disposal of ozone-depleting substances (ODSs) (e.g., Halon, Freon). Several important federal regulations have been promulgated that affect the use of such substances at the Hanford Site. On April 23, 1993, Executive Order (EO) 12843, Procurement Requirements and Policies for Federal Agencies for Ozone-Depleting Substances (EPA 1993) was issued for Federal facilities to conform to the new US Environmental Protection Agency (EPA) regulations implementing the Clean Air Act of 1963 (CAA), Section 613, as amended. To implement the requirements of Title VI the US Department of Energy, Richland Operations Office (RL), issued a directive to the Hanford Site contractors on May 25, 1994 (Wisness 1994). The directive assigns Westinghouse Hanford Company (WHC) the lead in coordinating the development of a sitewide comprehensive implementation plan to be drafted by July 29, 1994 and completed by September 30, 1994. The implementation plan will address several areas where immediate compliance action is required. It will identify all current uses of ODSs and inventories, document the remaining useful life of equipment that contains ODS chemicals, provide a phase-out schedule, and provide a strategy that will be implemented consistently by all the Hanford Site contractors. This plan also addresses the critical and required elements of Federal regulations, the EO, and US Department of Energy (DOE) guidance. This plan is intended to establish a sitewide management system to address the clean air requirements.

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

    National Nuclear Security Administration (NNSA)

    DRAFT SUPPLEMENT ANALYSIS FOR LOCATION(S) TO DISPOSE OF DEPLETED URANIUM OXIDE CONVERSION PRODUCT GENERATED FROM DOE'S INVENTORY OF DEPLETED URANIUM HEXAFLUORIDE (DOE/EIS-0359-SA1 AND DOE/EIS-0360-SA1) March 2007 March 2007 i CONTENTS NOTATION........................................................................................................................... iv 1 INTRODUCTION AND BACKGROUND ................................................................. 1 1.1 Why DOE Has Prepared This

  11. DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at

    Energy Savers [EERE]

    Ohio and Kentucky Facilities | Department of Energy Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at Ohio and Kentucky Facilities DOE Seeks Contractor for Depleted Uranium Hexafluoride (DUF6) Operations at Ohio and Kentucky Facilities April 1, 2015 - 3:30pm Addthis Media Contact: Lynette Chafin, 513-246-0461, Lynette.Chafin@emcbc.doe.gov Cincinnati -- The U.S. Department of Energy (DOE) today issued a Draft Request for Proposal (RFP) seeking a contractor to perform Depleted

  12. Improved Spatial Resolution in Thick, Fully-Depleted CCDs withEnhanced...

    Office of Scientific and Technical Information (OSTI)

    Improved Spatial Resolution in Thick, Fully-Depleted CCDs withEnhanced Red Sensitivity Citation Details In-Document Search Title: Improved Spatial Resolution in Thick,...

  13. EIS-0329: Proposed Construction, Operation, Decontamination/Decommissioning of Depleted Uranium Hexafluoride Conversion Facilities

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky.

  14. A ground state depleted laser in neodymium doped yttrium orthosilicate

    SciTech Connect (OSTI)

    Beach, R.; Albrecht, G.; Solarz, R.; Krupke, W.; Comaskey, B.; Mitchell, S.; Brandle, C.; Berkstresser, G.

    1990-01-16

    A ground state depleted (GSD){sup 1,2} laser has been demonstrated in the form of a Q-switched oscillator operating at 912 nm. Using Nd{sup 3+} as the active ion and Y{sub 2}SiO{sub 5} as the host material, the laser transition is from the lowest lying stark level of the Nd{sup 3t}F{sub 3/2} level to a stark level 355 cm{sup {minus}1} above the lowest lying one in the {sup 4}I{sub 9/2} manifold. The necessity of depleting the ground {sup 4}I{sub 9/2} manifold is evident for this level scheme as transparency requires a 10% inversion. To achieve the high excitation levels required for the efficient operation of this laser, bleach wave pumping using an alexandrite laser at 745 nm has been employed. The existence of a large absorption feature at 810 nm also allows for the possibility of AlGaAs laser diode pumping. Using KNbO{sub 3}, noncritical phase matching is possible at 140{degree}C using d{sub 32} and has been demonstrated. The results of Q-switched laser performance and harmonic generation in KNbO{sub 3} will be presented. Orthosilicate can be grown in large boules of excellent optical quality using a Czochralski technique. Because of the relatively small 912 nm emission cross section of 2-3 {times} 10{sup {minus}20} cm{sup 2} (orientation dependent) fluences of 10-20 J/cm{sup 2} must be circulated in the laser cavity for the efficient extraction of stored energy. This necessitates very aggressive laser damage thresholds. Results from the Reptile laser damage facility at Lawrence Livermore National Laboratory (LLNL) will be presented showing Y{sub 2}SiO{sub 5} bulk and AR sol-gel coated surface damage thresholds of greater than 40 J/cm{sup 2} for 10 nsec, 10 Hz, 1.06 {mu} pulses. 16 refs., 18 figs., 6 tabs.

  15. Neutronic and depletion analysis of the Pb-AHTR

    SciTech Connect (OSTI)

    Fratoni, Massimiliano; Greenspan, Ehud; Peterson, Per F.

    2007-07-01

    The PB-AHTR is a Pebble Bed Advanced High Temperature Reactor that is cooled with the liquid salt flibe (LiF-BeF{sub 2}) rather than helium. This study presents a preliminary neutronic and depletion analysis for the PBAHTR. The attainable burnup is determined as a function of uranium loading per pebble, power density and core dimensions. It is found that the optimal design for a 425 {mu}m UC{sub 0.5}O{sub 1.5} fuel kernel diameter, 10% enriched uranium, features a graphite-to-heavy metal ratio of {approx}360 and its reactivity coefficients are all negative. A comparison with the helium-cooled pebble-bed reactor and with a prismatic-fuel reactor that is cooled with either flibe or helium is also presented. It is found that the PB-AHTR offers similar discharge burnup as the other three designs. As compared to the gas-cooled pebble bed, the PB-AHTR uranium loading and energy generated per pebble are {approx}2.5 times higher. (authors)

  16. Investigation of breached depleted UF{sub 6} cylinders

    SciTech Connect (OSTI)

    DeVan, J.H.

    1991-12-31

    In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that occurred at the time that the cylinders had been placed in the storage yard. In both cylinders evidence pointed to the impact of a lifting lug of an adjacent cylinder near the front stiffening ring, where deflection of the cylinder could occur only by tearing the cylinder. The impacts appear to have punctured the cylinders and thereby set up corrosion processes that greatly extended the openings in the wall and obliterated the original crack. Fortunately, the reaction products formed by this process were relatively protective and prevented any large-scale loss of uranium. The main factors that precipitated the failures were inadequate spacing between cylinders and deviations in the orientations of lifting lugs from their intended horizontal position. After reviewing the causes and effects of the failures, the team`s principal recommendation for remedial action concerned improved cylinder handling and inspection procedures. Design modifications and supplementary mechanical tests were also recommended to improve the cylinder containment integrity during the stacking operation.

  17. Kr Ion Irradiation Study of the Depleted-Uranium Alloys

    SciTech Connect (OSTI)

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

    2010-12-01

    Fuel development for the Reduced Enrichment Research and Test Reactor program is tasked with the development of new low-enriched uranium nuclear fuels that can be employed to replace existing highly enriched uranium fuels currently used in some research reactors throughout the world. For dispersion-type fuels, radiation stability of the fuel/cladding interaction product has a strong impact on fuel performance. Three depleted uranium alloys are cast for the radiation stability studies of the fuel/cladding interaction product using Kr ion irradiation to investigate radiation damage from fission products. SEM analysis indicates the presence of the phases of interest: U(Si, Al)3, (U, Mo)(Si, Al)3, UMo2Al20, U6Mo4Al43, and UAl4. Irradiations of TEM disc samples were conducted with 500 keV Kr ions at 200ºC to ion doses up to 2.5 × 1015 ions/cm2 (~ 10 dpa) with an Kr ion flux of 1012 ions/cm2-sec (~ 4.0 × 10-3 dpa/sec). Microstructural evolution of the phases relevant to fuel-cladding interaction products was investigated using transmission electron microscopy.

  18. Manager Group Name","Location","Name","Title","Contact","E-mail

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

    Manager Group Name","Location","Name","Title","Contact","E-mail" "","","","","","Main: smothersd@osti.gov Alt: " "","","","","","Main: dan.doyle@netl.doe.gov Alt: " "Headquarters","Office of Science<br /> ","Laura Biven","Senior Science and Technology Advisor","(301)

  19. Site Office Contracting Officer E-mail address Ames Site Office Jackie York Jacquelyn.york@ch.doe.gov

    National Nuclear Security Administration (NNSA)

    Site Office Contracting Officer E-mail address Ames Site Office Jackie York Jacquelyn.york@ch.doe.gov Argonne Site Office Jacquelyn York Jacquelyn.york@ch.doe.gov Brookhaven Site Office Evelyn Landini Jennifer Hartmann elandini@bnl.gov jhartmann@bnl.gov Idaho Site Office Paul Allen allenph@id.doe.gov Kansas City Site Office Ralph Tennant rtennant@kcp.gov Lawrence Livermore Site Office Homer Williamson homer.williamson@nnsa.doe.gov Los Alamos Site Office Barbara Romero Robert M. Poole

  20. Microsoft Word - WD Proposed Plan D5 R8 MASTER 10-29-14 _final with reply mail_ rev 1

    Office of Environmental Management (EM)

    WD-PLN-0034, Rev. 8 1 DOE/PPPO/03-0312&D5 Aerial photo of the Portsmouth Gaseous Diffusion Plant showing the three large process buildings (center of photo) and other support facilities, facing southwest PUBLIC COMMENT PERIOD NOVEMBER 12, 2014 TO JANUARY 10, 2015 HOW YOU CAN PARTICIPATE Read this Proposed Plan and review related documents in the Administrative Record. Comment on this Proposed Plan by mail, email, or fax to: Ms. Kristi Wiehle Department of Energy P.O. Box 370 Piketon, Ohio

  1. Depleted uranium human health risk assessment, Jefferson Proving Ground, Indiana

    SciTech Connect (OSTI)

    Ebinger, M.H.; Hansen, W.R.

    1994-04-29

    The risk to human health from fragments of depleted uranium (DU) at Jefferson Proving Ground (JPG) was estimated using two types of ecosystem pathway models. A steady-state, model of the JPG area was developed to examine the effects of DU in soils, water, and vegetation on deer that were hunted and consumed by humans. The RESRAD code was also used to estimate the effects of farming the impact area and consuming the products derived from the farm. The steady-state model showed that minimal doses to humans are expected from consumption of deer that inhabit the impact area. Median values for doses to humans range from about 1 mrem ({plus_minus}2.4) to 0.04 mrem ({plus_minus}0.13) and translate to less than 1 {times} 10{sup {minus}6} detriments (excess cancers) in the population. Monte Carlo simulation of the steady-state model was used to derive the probability distributions from which the median values were drawn. Sensitivity analyses of the steady-state model showed that the amount of DU in airborne dust and, therefore, the amount of DU on the vegetation surface, controlled the amount of DU ingested by deer and by humans. Human doses from the RESRAD estimates ranged from less than 1 mrem/y to about 6.5 mrem/y in a hunting scenario and subsistence fanning scenario, respectively. The human doses exceeded the 100 mrem/y dose limit when drinking water for the farming scenario was obtained from the on-site aquifer that was presumably contaminated with DU. The two farming scenarios were unrealistic land uses because the additional risk to humans due to unexploded ordnance in the impact area was not figured into the risk estimate. The doses estimated with RESRAD translated to less than 1 {times} 10{sup {minus}6} detriments to about 1 {times} 10{sup {minus}3} detriments. The higher risks were associated only with the farming scenario in which drinking water was obtained on-site.

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

    DOE Patents [OSTI]

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

    2000-02-29

    The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

  3. Accelerated cellular senescence phenotype of GAPDH-depleted human lung carcinoma cells

    SciTech Connect (OSTI)

    Phadke, Manali; Krynetskaia, Natalia; Mishra, Anurag; Krynetskiy, Evgeny; Jayne Haines Center for Pharmacogenomics, Temple University School of Pharmacy, Philadelphia, PA 19140

    2011-07-29

    Highlights: {yields} We examined the effect of glyceraldehyde 3-phosphate (GAPDH) depletion on proliferation of human carcinoma A549 cells. {yields} GAPDH depletion induces accelerated senescence in tumor cells via AMPK network, in the absence of DNA damage. {yields} Metabolic and genetic rescue experiments indicate that GAPDH has regulatory functions linking energy metabolism and cell cycle. {yields} Induction of senescence in LKB1-deficient lung cancer cells via GAPDH depletion suggests a novel strategy to control tumor cell proliferation. -- Abstract: Glyceraldehyde 3-phosphate dehydrogenase (GAPDH) is a pivotal glycolytic enzyme, and a signaling molecule which acts at the interface between stress factors and the cellular apoptotic machinery. Earlier, we found that knockdown of GAPDH in human carcinoma cell lines resulted in cell proliferation arrest and chemoresistance to S phase-specific cytotoxic agents. To elucidate the mechanism by which GAPDH depletion arrests cell proliferation, we examined the effect of GAPDH knockdown on human carcinoma cells A549. Our results show that GAPDH-depleted cells establish senescence phenotype, as revealed by proliferation arrest, changes in morphology, SA-{beta}-galactosidase staining, and more than 2-fold up-regulation of senescence-associated genes DEC1 and GLB1. Accelerated senescence following GAPDH depletion results from compromised glycolysis and energy crisis leading to the sustained AMPK activation via phosphorylation of {alpha} subunit at Thr172. Our findings demonstrate that GAPDH depletion switches human tumor cells to senescent phenotype via AMPK network, in the absence of DNA damage. Rescue experiments using metabolic and genetic models confirmed that GAPDH has important regulatory functions linking the energy metabolism and the cell cycle networks. Induction of senescence in LKB1-deficient non-small cell lung cancer cells via GAPDH depletion suggests a novel strategy to control tumor cell proliferation.

  4. DOE Announces Transfer of Depleted Uranium to Advance the U.S. National

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

    Security Interests, Extend Operations at Paducah Gaseous Diffusion Plant | Department of Energy Transfer of Depleted Uranium to Advance the U.S. National Security Interests, Extend Operations at Paducah Gaseous Diffusion Plant DOE Announces Transfer of Depleted Uranium to Advance the U.S. National Security Interests, Extend Operations at Paducah Gaseous Diffusion Plant May 15, 2012 - 4:00pm Addthis News Media Contact (202) 386-4940 WASHINGTON - The Department of Energy - in collaboration

  5. Depletion Aggregation > Batteries & Fuel Cells > Research > The Energy

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

    Materials Center at Cornell Batteries & Fuel Cells In This Section Battery Anodes Battery Cathodes Depletion Aggregation Membranes Depletion Aggregation We are exploring a number of synthetic strategies to produce nanohybrids systems that carry great promise as structural materials in fuel cells and other electrochemical devices. To that end, we have prepared highly oriented arrays of several inorganic (silicate, graphene and graphitic) nanosheets well dispersed within the Nafion matrix

  6. Optimization of Depletion Modeling and Simulation for the High Flux Isotope Reactor

    SciTech Connect (OSTI)

    Betzler, Benjamin R; Ade, Brian J; Chandler, David; Ilas, Germina; Sunny, Eva E

    2015-01-01

    Monte Carlo based depletion tools used for the high-fidelity modeling and simulation of the High Flux Isotope Reactor (HFIR) come at a great computational cost; finding sufficient approximations is necessary to make the use of these tools feasible. The optimization of the neutronics and depletion model for the HFIR is based on two factors: (i) the explicit representation of the involute fuel plates with sets of polyhedra and (ii) the treatment of depletion mixtures and control element position during depletion calculations. A very fine representation (i.e., more polyhedra in the involute plate approximation) does not significantly improve simulation accuracy. The recommended representation closely represents the physical plates and ensures sufficient fidelity in regions with high flux gradients. Including the fissile targets in the central flux trap of the reactor as depletion mixtures has the greatest effect on the calculated cycle length, while localized effects (e.g., the burnup of specific isotopes or the power distribution evolution over the cycle) are more noticeable consequences of including a critical control element search or depleting burnable absorbers outside the fuel region.

  7. Depletion of cellular poly (A) binding protein prevents protein synthesis and leads to apoptosis in HeLa cells

    SciTech Connect (OSTI)

    Thangima Zannat, Mst.; Bhattacharjee, Rumpa B.; Bag, Jnanankur

    2011-05-13

    Highlights: {yields} Depletion of cellular PABP level arrests mRNA translation in HeLa cells. {yields} PABP knock down leads to apoptotic cell death. {yields} PABP depletion does not affect transcription. {yields} PABP depletion does not lead to nuclear accumulation of mRNA. -- Abstract: The cytoplasmic poly (A) binding protein (PABP) is important in mRNA translation and stability. In yeast, depletion of PABP leads to translation arrest. Similarly, the PABP gene in Drosophila is important for proper development. It is however uncertain, whether mammalian PABP is essential for mRNA translation. Here we showed the effect of PABP depletion on mRNA metabolism in HeLa cells by using a small interfering RNA. Our results suggest that depletion of PABP prevents protein synthesis and consequently leads to cell death through apoptosis. Interestingly, no detectable effect of PABP depletion on transcription, transport and stability of mRNA was observed.

  8. Stochastic interactions of two Brownian hard spheres in the presence of depletants

    SciTech Connect (OSTI)

    Karzar-Jeddi, Mehdi; Fan, Tai-Hsi; Tuinier, Remco; Taniguchi, Takashi

    2014-06-07

    A quantitative analysis is presented for the stochastic interactions of a pair of Brownian hard spheres in non-adsorbing polymer solutions. The hard spheres are hypothetically trapped by optical tweezers and allowed for random motion near the trapped positions. The investigation focuses on the long-time correlated Brownian motion. The mobility tensor altered by the polymer depletion effect is computed by the boundary integral method, and the corresponding random displacement is determined by the fluctuation-dissipation theorem. From our computations it follows that the presence of depletion layers around the hard spheres has a significant effect on the hydrodynamic interactions and particle dynamics as compared to pure solvent and uniform polymer solution cases. The probability distribution functions of random walks of the two interacting hard spheres that are trapped clearly shift due to the polymer depletion effect. The results show that the reduction of the viscosity in the depletion layers around the spheres and the entropic force due to the overlapping of depletion zones have a significant influence on the correlated Brownian interactions.

  9. Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1

    SciTech Connect (OSTI)

    Zoller, J.N.; Rosen, R.S.; Holliday, M.A.

    1995-06-30

    With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation. These Appendices contain the Federal Register Notice, comments on evaluation factors, independent technical reviewers resumes, independent technical reviewers manual, and technology information packages.

  10. Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2

    SciTech Connect (OSTI)

    Zoller, J.N.; Rosen, R.S.; Holliday, M.A.

    1995-06-30

    With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation.

  11. Transient effects and pump depletion in stimulated Raman scattering. [Para-hydrogen

    SciTech Connect (OSTI)

    Carlsten, J.L.; Wenzel, R.G.; Druehl, K.

    1983-01-01

    Stimulated rotational Raman scattering in a 300-K multipass cell filled with para-H/sub 2/ with a single-mode CO/sub 2/-pumped laser is studied using a frequency-narrowed optical parametric oscillator (OPO) as a probe laser at the Stokes frequency for the S/sub 0/(O) transition. Amplification and pump depletion are examined as a function of incident pump energy. The pump depletion shows clear evidence of transient behavior. A theoretical treatment of transient stimulated Raman scattering, including effects of both pump depletion and medium saturation is presented. In a first approximation, diffraction effects are neglected, and only plane-wave interactions are considered. The theoretical results are compared to the experimental pulse shapes.

  12. Monopolistic recycling of oil revenue and intertemporal bias in oil depletion and trade

    SciTech Connect (OSTI)

    Hillman, A.L.; Long, N.V.

    1985-08-01

    This paper investigates oil depletion and trade when monopolistic oil producers also exercise monopoly power in the capital market. A two-period model views collusively organized oil producers with an initial trade surplus and a subsequent deficit. When monopoly power in the capital market is applied to the disadvantage of borrowers, less oil is initially made available to oil importers than if the interest rate had been competitively determined. This depletion bias, however, is reversed if, because of incentives for capital accumulation, it is to the advantage of the oil producers to subsidize lending to the oil importers. In either case the bias in oil depletion due to monopolistic recycling of oil revenue is greater, the more vulnerable are oil importer's incomes to a curtailment of oil supplies. 25 references.

  13. Summary of the engineering analysis report for the long-term management of depleted uranium hexafluoride

    SciTech Connect (OSTI)

    Dubrin, J.W., Rahm-Crites, L.

    1997-09-01

    The Department of Energy (DOE) is reviewing ideas for the long-term management and use of its depleted uranium hexafluoride. DOE owns about 560,000 metric tons (over a billion pounds) of depleted uranium hexafluoride. This material is contained in steel cylinders located in storage yards near Paducah, Kentucky; Portsmouth, Ohio; and at the East Tennessee Technology Park (formerly the K-25 Site) in Oak Ridge, Tennessee. On November 10, 1994, DOE announced its new Depleted Uranium Hexafluoride Management Program by issuing a Request for Recommendations and an Advance Notice of Intent in the Federal Register (59 FR 56324 and 56325). The first part of this program consists of engineering, costs and environmental impact studies. Part one will conclude with the selection of a long-term management plan or strategy. Part two will carry out the selected strategy.

  14. 1,2 or 3-D Few-Group Diffusion Depletion

    Energy Science and Technology Software Center (OSTI)

    1982-12-01

    The PDQ series of programs is designed to solve the neutron diffusion-depletion problem in one, two or three dimensions. The three-dimensional spatial calculation may be either explicit or discontinuous trial function synthesis. Up to five lethargy groups are permitted. Adjoint, fixed source, one iteration, additive fixed source, eigenvalue, and boundary value calculations may be performed. The programs utilize the HARMONY system for time-dependent representation of cross section variation and generalized depletion chain solutions. Geometries availablemore » include rectangular, cylindrical, spherical, and hexagonal. All allow variable mesh in all dimensions. Various control searches as well as temperature and xenon feedback are provided.« less

  15. U.S. Natural Gas Number of Underground Storage Depleted Fields Capacity

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

    (Number of Elements) Depleted Fields Capacity (Number of Elements) U.S. Natural Gas Number of Underground Storage Depleted Fields Capacity (Number of Elements) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1990's 335 2000's 336 351 340 318 320 320 322 326 324 331 2010's 331 329 330 332 333 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 2/29/2016 Next Release Date:

  16. U.S. Working Natural Gas Underground Storage Depleted Fields Capacity

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

    (Million Cubic Feet) Depleted Fields Capacity (Million Cubic Feet) U.S. Working Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 2000's 3,583,786 3,659,968 2010's 3,733,993 3,769,113 3,720,980 3,839,852 3,844,927 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 2/29/2016 Next Release Date: 3/31/2016

  17. Electron depletion via cathode spot dispersion of dielectric powder into an overhead plasma

    SciTech Connect (OSTI)

    Gillman, Eric D. [Naval Research Laboratory, 4555 Overlook Ave SW, Washington, District of Columbia 20375 (United States)] [Naval Research Laboratory, 4555 Overlook Ave SW, Washington, District of Columbia 20375 (United States); Foster, John E. [Department of Nuclear Engineering and Radiological Sciences (NERS), University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, Michigan 48109 (United States)] [Department of Nuclear Engineering and Radiological Sciences (NERS), University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, Michigan 48109 (United States)

    2013-11-15

    The effectiveness of cathode spot delivered dielectric particles for the purpose of plasma depletion is investigated. Here, cathode spot flows kinetically entrain and accelerate dielectric particles originally at rest into a background plasma. The time variation of the background plasma density is tracked using a cylindrical Langmuir probe biased approximately at electron saturation. As inferred from changes in the electron saturation current, depletion fractions of up to 95% are observed. This method could be exploited as a means of communications blackout mitigation for manned and unmanned reentering spacecraft as well as any high speed vehicle enveloped by a dense plasma layer.

  18. Running Out Of and Into Oil. Analyzing Global Oil Depletion and Transition Through 2050

    SciTech Connect (OSTI)

    Greene, David L.; Hopson, Janet L.; Li, Jia

    2003-10-01

    This report presents a risk analysis of world conventional oil resource production, depletion, expansion, and a possible transition to unconventional oil resources such as oil sands, heavy oil and shale oil over the period 2000 to 2050. Risk analysis uses Monte Carlo simulation methods to produce a probability distribution of outcomes rather than a single value.

  19. DOE Issues Request for Quotations for Depleted Uranium Hexafluoride Conversion Technical Services

    Broader source: Energy.gov [DOE]

    Cincinnati – The U.S. Department of Energy (DOE) today issued a Request for Quotation (RFQ) for engineering and operations technical services to support the Portsmouth Paducah Project Office and the oversight of operations of the Depleted Uranium Hexafluoride (DUF6) Conversion Project located in Paducah KY, and Portsmouth OH.

  20. FORIG: a modification of the ORIGEN2 isotope-generation and depletion code for fusion problems

    SciTech Connect (OSTI)

    Blink, J.A.

    1982-03-03

    This report describes how to use the FORIG computer code to solve isotope-generation and depletion problems in fusion and fission reactors. FORIG is an adaptation of ORIGEN2 to run on a Cray-1 computer, and to accept more extensive activation cross sections.

  1. MailedForm.pptx

    National Nuclear Security Administration (NNSA)

    Sign Up For Services Provided By The Radiological Security Partnership. Businesses using high-activity radioactive sources (Cesium-137, Cobalt-60, Americium-241, and Iridium-192) may qualify for the federally funded Partnership. To apply, complete and submit the form below. Once your information has been transmitted and reviewed, a representative will contact you with further information. Business or Facility Name ______________________________________________ Salutation __________ First Name

  2. EIS-0269: Notice of Intent to Prepare a Programmatic Environmental Impact

    Office of Environmental Management (EM)

    Statement | Department of Energy Notice of Intent to Prepare a Programmatic Environmental Impact Statement EIS-0269: Notice of Intent to Prepare a Programmatic Environmental Impact Statement Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride, Paducah, Kentucky; Portsmouth, Ohio; and Oak Ridge, Tennessee This impact statement will support management decisions on depleted UF6 by evaluating the environmental impacts of a range of reasonable alternative

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

    Broader source: Energy.gov [DOE]

    This site-specific EIS analyzes the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three alternative locations within the Paducah site; transportation of all cylinders (DUF6, enriched, and empty) currently stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Portsmouth; construction of a new cylinder storage yard at Portsmouth (if required) for ETTP cylinders; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride (HF) produced as a conversion coproduct; and neutralization of HF to calcium fluoride and its sale or disposal in the event that the HF product is not sold.

  4. U.S. Natural Gas Underground Storage Depleted Fields Capacity (Million

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

    Cubic Feet) Depleted Fields Capacity (Million Cubic Feet) U.S. Natural Gas Underground Storage Depleted Fields Capacity (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1990's 6,780,700 2000's 6,788,130 6,768,622 6,747,108 6,733,983 6,776,894 6,667,222 6,711,656 6,801,291 6,805,490 6,917,547 2010's 7,074,773 7,104,948 7,038,245 7,074,916 7,085,773 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure

  5. An assessment of alternatives and technologies for replacing ozone- depleting substances at DOE facilities

    SciTech Connect (OSTI)

    Purcell, C.W.; Miller, K.B.; Friedman, J.R.; Rapoport, R.D.; Conover, D.R.; Hendrickson, P.L.; Koss, T.C.

    1992-10-01

    Title VI of the Clean Air Act, as amended, mandates a production phase-out for ozone-depleting substances (ODSs). These requirements will have a significant impact on US Department of Energy (DOE) facilities. Currently, DOE uses ODSs in three major activities: fire suppression (halon), refrigeration and cooling (chlorofluorocarbons [CFCs]), and cleaning that requires solvents (CFCs, methyl chloroform, and carbon tetrachloride). This report provides basic information on methods and strategies to phase out use of ODSs at DOE facilities.

  6. Potential hazards of compressed air energy storage in depleted natural gas reservoirs.

    SciTech Connect (OSTI)

    Cooper, Paul W.; Grubelich, Mark Charles; Bauer, Stephen J.

    2011-09-01

    This report is a preliminary assessment of the ignition and explosion potential in a depleted hydrocarbon reservoir from air cycling associated with compressed air energy storage (CAES) in geologic media. The study identifies issues associated with this phenomenon as well as possible mitigating measures that should be considered. Compressed air energy storage (CAES) in geologic media has been proposed to help supplement renewable energy sources (e.g., wind and solar) by providing a means to store energy when excess energy is available, and to provide an energy source during non-productive or low productivity renewable energy time periods. Presently, salt caverns represent the only proven underground storage used for CAES. Depleted natural gas reservoirs represent another potential underground storage vessel for CAES because they have demonstrated their container function and may have the requisite porosity and permeability; however reservoirs have yet to be demonstrated as a functional/operational storage media for compressed air. Specifically, air introduced into a depleted natural gas reservoir presents a situation where an ignition and explosion potential may exist. This report presents the results of an initial study identifying issues associated with this phenomena as well as possible mitigating measures that should be considered.

  7. Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations

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

    Fensin, M. L.; Galloway, J. D.; James, M. R.

    2015-04-11

    The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. With the merger of MCNPX and MCNP5, MCNP6 combined the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. The new MCNP6 depletion capability was first showcased at the International Congress for Advancements in Nuclear Power Plants (ICAPP) meeting in 2012. At that conference the new capabilities addressed included the combined distributive and shared memory parallel architecture for the burnup capability, improved memory management, physics enhancements, and newmore » predictability as compared to the H.B Robinson Benchmark. At Los Alamos National Laboratory, a special purpose cluster named “tebow,” was constructed such to maximize available RAM per CPU, as well as leveraging swap space with solid state hard drives, to allow larger scale depletion calculations (allowing for significantly more burnable regions than previously examined). As the MCNP6 burnup capability was scaled to larger numbers of burnable regions, a noticeable slowdown was realized.This paper details two specific computational performance strategies for improving calculation speedup: (1) retrieving cross sections during transport; and (2) tallying mechanisms specific to burnup in MCNP. To combat this slowdown new performance upgrades were developed and integrated into MCNP6 1.2.« less

  8. Micelle-induced depletion interaction and resultant structure in charged colloidal nanoparticle system

    SciTech Connect (OSTI)

    Ray, D.; Aswal, V. K.; Kohlbrecher, J.

    2015-04-28

    The evolution of the interaction and the resultant structure in the mixed system of anionic silica nanoparticles (Ludox LS30) and non-ionic surfactant decaethylene glycol monododecylether (C12E10), undergoing phase separation, have been studied using small-angle neutron scattering and dynamic light scattering. The measurements have been carried out for a fixed concentration of nanoparticle (1?wt.?%) with varying concentration of surfactant (0 to 1?wt.?%), in the absence and presence of an electrolyte. It is found that the micelles of non-ionic surfactant adsorb on the nanoparticle in the absence of electrolyte (form stable system), whereas these micelles become non-adsorbing in the presence of electrolyte (show phase separation). The phase separation arises because of C12E10 micelles, causing depletion interaction between nanoparticles and leading to their aggregation. The interaction is modeled by double Yukawa potential accounting for attractive depletion as well as repulsive electrostatic forces. Both the interactions (attraction and repulsion) are found to be of long-range. The nanoparticle aggregation (phase separation) is governed by the increase in the magnitude and the range of the depletion attraction with the increase in the surfactant concentration. The nanoparticle aggregates formed are quite large in size (order of micron) and are characterized by the surface fractal having simple cubic packing of nanoparticles within the aggregates.

  9. Semiconductor-based photoelectrochemical water splitting at the limit of very wide depletion region

    SciTech Connect (OSTI)

    Liu, Mingzhao; Lyons, John L.; Yan, Danhua H.; Hybertsen, Mark S.

    2015-11-23

    In semiconductor-based photoelectrochemical (PEC) water splitting, carrier separation and delivery largely relies on the depletion region formed at the semiconductor/water interface. As a Schottky junction device, the trade-off between photon collection and minority carrier delivery remains a persistent obstacle for maximizing the performance of a water splitting photoelectrode. Here, it is demonstrated that the PEC water splitting efficiency for an n-SrTiO3 (n-STO) photoanode is improved very significantly despite its weak indirect band gap optical absorption (α < 10⁴ cm⁻¹), by widening the depletion region through engineering its doping density and profile. Graded doped n-SrTiO3 photoanodes are fabricated with their bulk heavily doped with oxygen vacancies but their surface lightly doped over a tunable depth of a few hundred nanometers, through a simple low temperature re-oxidation technique. The graded doping profile widens the depletion region to over 500 nm, thus leading to very efficient charge carrier separation and high quantum efficiency (>70%) for the weak indirect transition. As a result, this simultaneous optimization of the light absorption, minority carrier (hole) delivery, and majority carrier (electron) transport by means of a graded doping architecture may be useful for other indirect band gap photocatalysts that suffer from a similar problem of weak optical absorption.

  10. Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.

    SciTech Connect (OSTI)

    Wilson, E.H.; Horelik, N.E.; Dunn, F.E.; Newton, T.H., Jr.; Hu, L.; Stevens, J.G.

    2012-04-04

    The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context, most research and test reactors both domestic and international have started a program of conversion to the use of Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (UMo) is expected to allow the conversion of U.S. domestic high performance reactors like the MITR-II reactor. Toward this goal, core geometry and power distributions are presented. Distributions of power are calculated for LEU cores depleted with MCODE using an MCNP5 Monte Carlo model. The MCNP5 HEU and LEU MITR models were previously compared to experimental benchmark data for the MITR-II. This same model was used with a finer spatial depletion in order to generate power distributions for the LEU cores. The objective of this work is to generate and characterize a series of fresh and depleted core peak power distributions, and provide a thermal hydraulic evaluation of the geometry which should be considered for subsequent thermal hydraulic safety analyses.

  11. Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations

    SciTech Connect (OSTI)

    Fensin, M. L.; Galloway, J. D.; James, M. R.

    2015-04-11

    The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. With the merger of MCNPX and MCNP5, MCNP6 combined the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. The new MCNP6 depletion capability was first showcased at the International Congress for Advancements in Nuclear Power Plants (ICAPP) meeting in 2012. At that conference the new capabilities addressed included the combined distributive and shared memory parallel architecture for the burnup capability, improved memory management, physics enhancements, and new predictability as compared to the H.B Robinson Benchmark. At Los Alamos National Laboratory, a special purpose cluster named “tebow,” was constructed such to maximize available RAM per CPU, as well as leveraging swap space with solid state hard drives, to allow larger scale depletion calculations (allowing for significantly more burnable regions than previously examined). As the MCNP6 burnup capability was scaled to larger numbers of burnable regions, a noticeable slowdown was realized.This paper details two specific computational performance strategies for improving calculation speedup: (1) retrieving cross sections during transport; and (2) tallying mechanisms specific to burnup in MCNP. To combat this slowdown new performance upgrades were developed and integrated into MCNP6 1.2.

  12. Semiconductor-based photoelectrochemical water splitting at the limit of very wide depletion region

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

    Liu, Mingzhao; Lyons, John L.; Yan, Danhua H.; Hybertsen, Mark S.

    2015-11-23

    In semiconductor-based photoelectrochemical (PEC) water splitting, carrier separation and delivery largely relies on the depletion region formed at the semiconductor/water interface. As a Schottky junction device, the trade-off between photon collection and minority carrier delivery remains a persistent obstacle for maximizing the performance of a water splitting photoelectrode. Here, it is demonstrated that the PEC water splitting efficiency for an n-SrTiO3 (n-STO) photoanode is improved very significantly despite its weak indirect band gap optical absorption (α < 10⁴ cm⁻¹), by widening the depletion region through engineering its doping density and profile. Graded doped n-SrTiO3 photoanodes are fabricated with their bulkmore » heavily doped with oxygen vacancies but their surface lightly doped over a tunable depth of a few hundred nanometers, through a simple low temperature re-oxidation technique. The graded doping profile widens the depletion region to over 500 nm, thus leading to very efficient charge carrier separation and high quantum efficiency (>70%) for the weak indirect transition. As a result, this simultaneous optimization of the light absorption, minority carrier (hole) delivery, and majority carrier (electron) transport by means of a graded doping architecture may be useful for other indirect band gap photocatalysts that suffer from a similar problem of weak optical absorption.« less

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

    SciTech Connect (OSTI)

    Schneider, Erich; Scopatza, Anthony; Deinert, Mark

    2007-07-01

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

  14. Second Generation Monolithic Full-depletion Radiation Sensor with Integrated CMOS Circuitry

    SciTech Connect (OSTI)

    Segal, J.D.; Kenney, C.J.; Parker, S.I.; Aw, C.H.; Snoeys, W.J.; Wooley, B.; Plummer, J.D.; /Stanford U., Elect. Eng. Dept.

    2011-05-20

    A second-generation monolithic silicon radiation sensor has been built and characterized. This pixel detector has CMOS circuitry fabricated directly in the high-resistivity floatzone substrate. The bulk is fully depleted from bias applied to the backside diode. Within the array, PMOS pixel circuitry forms the first stage amplifiers. Full CMOS circuitry implementing further amplification as well as column and row logic is located in the periphery of the pixel array. This allows a sparse-field readout scheme where only pixels with signals above a certain threshold are readout. We describe the fabrication process, circuit design, system performance, and results of gamma-ray radiation tests.

  15. Interdisciplinary Investigation of CO2 Sequestration in Depleted Shale Gas Formations

    SciTech Connect (OSTI)

    Zoback, Mark; Kovscek, Anthony; Wilcox, Jennifer

    2013-09-30

    This project investigates the feasibility of geologic sequestration of CO2 in depleted shale gas reservoirs from an interdisciplinary viewpoint. It is anticipated that over the next two decades, tens of thousands of wells will be drilled in the 23 states in which organic-rich shale gas deposits are found. This research investigates the feasibility of using these formations for sequestration. If feasible, the number of sites where CO2 can be sequestered increases dramatically. The research embraces a broad array of length scales ranging from the ~10 nanometer scale of the pores in the shale formations to reservoir scale through a series of integrated laboratory and theoretical studies.

  16. Postmidnight depletion of the high-energy tail of the quiet plasmasphere

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

    Sarno-Smith, Lois K.; Liemohn, Michael W.; Katus, Roxanne M.; Skoug, Ruth M.; Larsen, Brian A.; Thomsen, Michelle F.; Wygant, John R.; Moldwin, Mark B.

    2015-03-06

    The Van Allen Probes Helium Oxygen Proton Electron (HOPE) instrument measures the high energy tail of the thermal plasmasphere allowing study of topside ionosphere and inner magnetosphere coupling. We statistically analyze a 22 month period of HOPE data, looking at quiet times with a Kp index of less than 3. We investigate the high energy range of the plasmasphere, which consists of ions at energies between 1-10 eV and contains approximately 5% of total plasmaspheric density. Both the fluxes and partial plasma densities over this energy range show H+ is depleted the most in the post-midnight sector (1-4 MLT), followedmore » by O+ and then He+. The relative depletion of each species across the post-midnight sector is not ordered by mass, which reveals ionospheric influence. We compare our results with keV energy electron data from HOPE and the Van Allen Probes Electric Fields and Waves (EFW) instrument spacecraft potential to rule out spacecraft charging. Our conclusion is that the post-midnight ion disappearance is due to diurnal ionospheric temperature variation and charge exchange processes« less

  17. Postmidnight depletion of the high-energy tail of the quiet plasmasphere

    SciTech Connect (OSTI)

    Sarno-Smith, Lois K.; Liemohn, Michael W.; Katus, Roxanne M.; Skoug, Ruth M.; Larsen, Brian A.; Thomsen, Michelle F.; Wygant, John R.; Moldwin, Mark B.

    2015-03-06

    The Van Allen Probes Helium Oxygen Proton Electron (HOPE) instrument measures the high energy tail of the thermal plasmasphere allowing study of topside ionosphere and inner magnetosphere coupling. We statistically analyze a 22 month period of HOPE data, looking at quiet times with a Kp index of less than 3. We investigate the high energy range of the plasmasphere, which consists of ions at energies between 1-10 eV and contains approximately 5% of total plasmaspheric density. Both the fluxes and partial plasma densities over this energy range show H+ is depleted the most in the post-midnight sector (1-4 MLT), followed by O+ and then He+. The relative depletion of each species across the post-midnight sector is not ordered by mass, which reveals ionospheric influence. We compare our results with keV energy electron data from HOPE and the Van Allen Probes Electric Fields and Waves (EFW) instrument spacecraft potential to rule out spacecraft charging. Our conclusion is that the post-midnight ion disappearance is due to diurnal ionospheric temperature variation and charge exchange processes

  18. Effects of Bismuth on Wide-Depletion-Width GaInNAs Solar Cells

    SciTech Connect (OSTI)

    Ptak, A. J.; France, R.; Jiang, C.-S.; Reedy, R. C.

    2008-05-01

    GaInNAs solar cells could be useful in next-generation multijunction solar cells if issues surrounding low photocurrents and photovoltages are surmounted. Wide-depletion-width devices generate significant photocurrent using a p-i-n structure grown by molecular beam epitaxy, but these depletion widths are only realized in a region of parameter space that leads to rough surface morphologies. Here, bismuth is explored as a surfactant for the growth of GaInNAs solar cells. Very low fluxes of Bi are effective at maintaining smooth surfaces, even at high growth temperatures and In contents. However, Bi also increases the net donor concentration in these materials, manifested in our n-on-p device structures as a pn-junction that moves deeper into the base layer with increasing Bi fluxes. Quantum efficiency modeling and scanning kelvin probe microscopy measurements confirm the type conversion of the base layer from p type to n type. Bi incorporation in GaAsBi samples shows signs of surface segregation, leading to a finite buildup time, and this effect may lead to slow changes in the electrical properties of the GaInNAs(Bi) devices. Bi also appears to create a defect level, although this defect level is not deleterious enough to increase the dark current in the devices.

  19. Depleted uranium oxides and silicates as spent nuclear fuel waste package fill materials

    SciTech Connect (OSTI)

    Forsberg, C.W.

    1996-09-10

    A new repository waste package (WP) concept for spent nuclear fuel (SNF) is being investigated that uses depleted uranium (DU) to improve performance and reduce the uncertainties of geological disposal of SNF. The WP would be filled with SNF and then filled with depleted uranium (DU) ({approximately}0.2 wt % {sup 235}U) dioxide (UO{sub 2}) or DU silicate-glass beads. Fission products and actinides can not escape the SNF UO{sub 2} crystals until the UO{sub 2} dissolves or is transformed into other chemical species. After WP failure, the DU fill material slows dissolution by three mechanisms: (1) saturation of AT groundwater with DU and suppression of SNF dissolution, (2) maintenance of chemically reducing conditions in the WP that minimize SNF solubility by sacrificial oxidation of DU from the +4 valence state, and (3) evolution of DU to lower-density hydrated uranium silicates. The fill expansion seals the WP from water flow. The DU also isotopically exchanges with SNF uranium as the SNF degrades to reduce long-term nuclear-criticality concerns.

  20. The depletion of Interleukin-8 causes cell cycle arrest and increases the efficacy of docetaxel in breast cancer cells

    SciTech Connect (OSTI)

    Shao, Nan; Chen, Liu-Hua; Ye, Run-Yi; Lin, Ying; Wang, Shen-Ming

    2013-02-15

    Highlights: ? IL-8 depletion affects cell cycle distribution. ? Intrinsic IL-8 mediates breast cancer cell migration and invasion. ? IL-8 siRNA down regulates key factors that control survival and metastatic pathway. ? IL-8 depletion reduces integrin ?3 expression. ? IL-8 depletion increases the chemosensitivity to docetaxel. -- Abstract: IL-8 is a multi-functional pro-inflammatory chemokine, which is highly expressed in cancers, such as ER-negative breast cancer. The present study demonstrates the pervasive role of IL-8 in the malignant progression of ER-negative breast cancer. IL-8 siRNA inhibited proliferation and delayed the G1 to S cell cycle progression in MDA-MB-231 and BT549 cells. IL-8 silencing resulted in the upregulation of the CDK inhibitor p27, the downregulation of cyclin D1, and the reduction of phosphorylated-Akt and NF-?B activities. IL-8 depletion also increased the chemosensitivity to docetaxel. These results indicate a role for IL-8 in promoting tumor cell survival and resistance to docetaxel and highlight the potential therapeutic significance of IL-8 depletion in ER-negative breast cancer patients.

  1. Manufacturing Process Development to Produce Depleted Uranium Wire for EBAM Feedstock

    SciTech Connect (OSTI)

    Alexander, David John; Clarke, Kester Diederik; Coughlin, Daniel Robert; Scott, Jeffrey E.

    2015-06-30

    Wire produced from depleted uranium (DU) is needed as feedstock for the Electron-Beam Additive Manufacturing (EBAM) process. The goal is to produce long lengths of DU wire with round or rectangular cross section, nominally 1.5 mm (0.060 inches). It was found that rolling methods, rather than swaging or drawing, are preferable for production of intermediate quantities of DU wire. Trials with grooveless rolling have shown that it is suitable for initial reductions of large stock. Initial trials with grooved rolling have been successful, for certain materials. Modified square grooves (square round-bottom vee grooves) with 12.5 % reduction of area per pass have been selected for the reduction process.

  2. Multi-images deconvolution improves signal-to-noise ratio on gated stimulated emission depletion microscopy

    SciTech Connect (OSTI)

    Castello, Marco; Diaspro, Alberto; Vicidomini, Giuseppe

    2014-12-08

    Time-gated detection, namely, only collecting the fluorescence photons after a time-delay from the excitation events, reduces complexity, cost, and illumination intensity of a stimulated emission depletion (STED) microscope. In the gated continuous-wave- (CW-) STED implementation, the spatial resolution improves with increased time-delay, but the signal-to-noise ratio (SNR) reduces. Thus, in sub-optimal conditions, such as a low photon-budget regime, the SNR reduction can cancel-out the expected gain in resolution. Here, we propose a method which does not discard photons, but instead collects all the photons in different time-gates and recombines them through a multi-image deconvolution. Our results, obtained on simulated and experimental data, show that the SNR of the restored image improves relative to the gated image, thereby improving the effective resolution.

  3. Theophylline prevents NAD{sup +} depletion via PARP-1 inhibition in human pulmonary epithelial cells

    SciTech Connect (OSTI)

    Moonen, Harald J.J. . E-mail: h.moonen@grat.unimaas.nl; Geraets, Liesbeth; Vaarhorst, Anika; Bast, Aalt; Wouters, Emiel F.M.; Hageman, Geja J.

    2005-12-30

    Oxidative DNA damage, as occurs during exacerbations in chronic obstructive pulmonary disease (COPD), highly activates the nuclear enzyme poly(ADP-ribose)polymerase-1 (PARP-1). This can lead to cellular depletion of its substrate NAD{sup +}, resulting in an energy crisis and ultimately in cell death. Inhibition of PARP-1 results in preservation of the intracellular NAD{sup +} pool, and of NAD{sup +}-dependent cellular processes. In this study, PARP-1 activation by hydrogen peroxide decreased intracellular NAD{sup +} levels in human pulmonary epithelial cells, which was found to be prevented in a dose-dependent manner by theophylline, a widely used compound in the treatment of COPD. This enzyme inhibition by theophylline was confirmed in an ELISA using purified human PARP-1 and was found to be competitive by nature. These findings provide new mechanistic insights into the therapeutic effect of theophylline in oxidative stress-induced lung pathologies.

  4. Revenue ruling 73-538: the service's assault on percentage depletion for ''D'' miners

    SciTech Connect (OSTI)

    Barnes, D.A.

    1983-01-01

    In this article, the author examines the Internal Revenue Service's ruling that storage and loading for shipment at the mine site are nonmining processes for ores and minerals described in section 613(c)(4)(D) of the Internal Revenue Code. He explains the tax consequences of the ruling and discusses the correctness of the position taken by the Internal Revenue Service in light of the relevant case law and the language and legislative history of the statute. The effect of the ruling is to reduce the percentage depletion deduction available to many miners of ores and minerals described in section 613(c)(4)(D), including miners of lead, zinc, copper, gold, silver, uranium, fluorspar, potash, soda ash, garnet and tungsten. (JMT)

  5. Strategy for Characterizing Transuranics and Technetium Contamination in Depleted UF{sub 6} Cylinders

    SciTech Connect (OSTI)

    Hightower, J.R.

    2000-10-26

    This report summarizes results of a study performed to develop a strategy for characterization of low levels of radioactive contaminants [plutonium (Pu), neptunium (Np), americium (Am), and technetium (Tc)] in depleted uranium hexafluoride (DUF{sub 6}) cylinders at the gaseous diffusion plants in Oak Ridge, Tennessee; Paducah, Kentucky; and Piketon, Ohio. In these gaseous diffusion plants, this radioactivity came from enriching recycled uranium (the so-called ''reactor returns'') from Savannah River, South Carolina, and Hanford, Washington, reactors. Results of this study will be used to support a request for proposals to design, build, and operate facilities to convert the DUF{sub 6} to more chemically stable forms. These facilities would need to be designed to handle any transuranic contaminants that might be present in order to (1) protect the workers' health and safety and (2) protect the public and the environment.

  6. Cadmium Depletion Impacts on Hardening Neutron6 Spectrum for Advanced Fuel Testing in ATR

    SciTech Connect (OSTI)

    Gray S. Chang

    2011-05-01

    For transmuting long-lived isotopes contained in spent nuclear fuel into shorter-lived fission products effectively is in a fast neutron spectrum reactor. In the absence of a fast spectrum test reactor in the United States of America (USA), initial irradiation testing of candidate fuels can be performed in a thermal test reactor that has been modified to produce a test region with a hardened neutron spectrum. A test region is achieved with a Cadmium (Cd) filter which can harden the neutron spectrum to a spectrum similar (although still somewhat softer) to that of the liquid metal fast breeder reactor (LMFBR). A fuel test loop with a Cd-filter has been installed within the East Flux Trap (EFT) of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). A detailed comparison analyses between the cadmium (Cd) filter hardened neutron spectrum in the ATR and the LMFBR fast neutron spectrum have been performed using MCWO. MCWO is a set of scripting tools that are used to couple the Monte Carlo transport code MCNP with the isotope depletion and buildup code ORIGEN-2.2. The MCWO-calculated results indicate that the Cd-filter can effectively flatten the Rim-Effect and reduce the linear heat rate (LHGR) to meet the advanced fuel testing project requirements at the beginning of irradiation (BOI). However, the filtering characteristics of Cd as a strong absorber quickly depletes over time, and the Cd-filter must be replaced for every two typical operating cycles within the EFT of the ATR. The designed Cd-filter can effectively depress the LHGR in experimental fuels and harden the neutron spectrum enough to adequately flatten the Rim Effect in the test region.

  7. Environmental acceptability of high-performance alternatives for depleted uranium penetrators

    SciTech Connect (OSTI)

    Kerley, C.R.; Easterly, C.E.; Eckerman, K.F.

    1996-08-01

    The Army`s environmental strategy for investigating material substitution and management is to measure system environmental gains/losses in all phases of the material management life cycle from cradle to grave. This study is the first in a series of new investigations, applying material life cycle concepts, to evaluate whether there are environmental benefits from increasing the use of tungsten as an alternative to depleted uranium (DU) in Kinetic Energy Penetrators (KEPs). Current military armor penetrators use DU and tungsten as base materials. Although DU alloys have provided the highest performance of any high-density alloy deployed against enemy heavy armor, its low-level radioactivity poses a number of environmental risks. These risks include exposures to the military and civilian population from inhalation, ingestion, and injection of particles. Depleted uranium is well known to be chemically toxic (kidney toxicity), and workplace exposure levels are based on its renal toxicity. Waste materials containing DU fragments are classified as low-level radioactive waste and are regulated by the Nuclear Regulatory Commission. These characteristics of DU do not preclude its use in KEPs. However, long-term management challenges associated with KEP deployment and improved public perceptions about environmental risks from military activities might be well served by a serious effort to identify, develop, and substitute alternative materials that meet performance objectives and involve fewer environmental risks. Tungsten, a leading candidate base material for KEPS, is potentially such a material because it is not radioactive. Tungsten is less well studied, however, with respect to health impacts and other environmental risks. The present study is designed to contribute to the understanding of the environmental behavior of tungsten by synthesizing available information that is relevant to its potential use as a penetrator.

  8. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-29

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  9. CRC DEPLETION CALCULATIONS FOR THE RODDED ASSEMBLIES IN BATCHES 1, 2, 3, AND 1X OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-09-03

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies from batches 1, 2, 3, and 1X of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its irradiation history. The objective of this analysis is to provide SAS2H calculated isotopic compositions of depleted fuel and depleted burnable poison for each fuel assembly to be used in subsequent CRC reactivity calculations containing the fuel assemblies.

  10. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 4 AND 5 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-30

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 4 and 5 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  11. Enterprise Assessments Targeted Review of the Paducah Depleted Uranium Hexafluoride Conversion Facility Fire Protection Program … September 2015

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

    Targeted Review of the Paducah Depleted Uranium Hexafluoride Conversion Facility Fire Protection Program September 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms ..................................................................................................................................................... ii Executive Summary

  12. DOE Issues Final Request for Proposal for the Operation of Depleted Uranium Hexafluoride (DUF6) Conversion Facilities

    Broader source: Energy.gov [DOE]

    Cincinnati -- The U.S. Department of Energy (DOE) today issued a Final Request for Proposal (RFP), for the Operation of Depleted Uranium Hexafluoride (DUF6) Conversion Facilities at Paducah, Kentucky and Portsmouth, Ohio. A cost-plus award fee and firm-fixed-price contract line item contract will be awarded from this Final RFP.

  13. Top-gate organic depletion and inversion transistors with doped channel and injection contact

    SciTech Connect (OSTI)

    Liu, Xuhai; Kasemann, Daniel Leo, Karl

    2015-03-09

    Organic field-effect transistors constitute a vibrant research field and open application perspectives in flexible electronics. For a commercial breakthrough, however, significant performance improvements are still needed, e.g., stable and high charge carrier mobility and on-off ratio, tunable threshold voltage, as well as integrability criteria such as n- and p-channel operation and top-gate architecture. Here, we show pentacene-based top-gate organic transistors operated in depletion and inversion regimes, realized by doping source and drain contacts as well as a thin layer of the transistor channel. By varying the doping concentration and the thickness of the doped channel, we control the position of the threshold voltage without degrading on-off ratio or mobility. Capacitance-voltage measurements show that an inversion channel can indeed be formed, e.g., an n-doped channel can be inverted to a p-type inversion channel with highly p-doped contacts. The Cytop polymer dielectric minimizes hysteresis, and the transistors can be biased for prolonged cycles without a shift of threshold voltage, indicating excellent operation stability.

  14. DEPLETION OF MOLECULAR GAS BY AN ACCRETION OUTBURST IN A PROTOPLANETARY DISK

    SciTech Connect (OSTI)

    Banzatti, A.; Pontoppidan, K. M.; Muzerolle, J. [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States); Bruderer, S. [Max-Planck-Institut für Extraterrestrische Physik, Giessenbachstr. 1, D-85748 Garching bei München (Germany); Meyer, M. R., E-mail: banzatti@stsci.edu [ETH Zürich, Institut für Astronomie, Wolfgang-Pauli-Strasse 27, CH-8093 Zürich (Switzerland)

    2015-01-01

    We investigate new and archival 3-5 ?m high-resolution (?3 km s{sup –1}) spectroscopy of molecular gas in the inner disk of the young solar-mass star EX Lupi, taken during and after the strong accretion outburst of 2008. The data were obtained using the CRIRES spectrometer at the European Southern Observatory Very Large Telescope in 2008 and 2014. In 2008, emission lines from CO, H{sub 2}O, and OH were detected with broad profiles tracing gas near and within the corotation radius (0.02-0.3 AU). In 2014, the spectra display marked differences. The CO lines, while still detected, are much weaker, and the H{sub 2}O and OH lines have disappeared altogether. At 3 ?m a veiled stellar photospheric spectrum is observed. Our analysis finds that the molecular gas mass in the inner disk has decreased by an order of magnitude since the outburst, matching a similar decrease in the accretion rate onto the star. We discuss these findings in the context of a rapid depletion of material accumulated beyond the disk corotation radius during quiescent periods, as proposed by models of episodic accretion in EXor-type young stars.

  15. Modulated Tool-Path Chip Breaking For Depleted Uranium Machining Operations

    SciTech Connect (OSTI)

    Barkman, W. E.; Babelay Jr., E. F.; Smith, K. S.; Assaid T. S.; McFarland, J. T.; Tursky, D. A.

    2010-04-15

    Turning operations involving depleted uranium frequently generate long, stringy chips that present a hazard to both the machinist and the machine tool. While a variety of chip-breaking techniques are available, they generally depend on a mechanism that increases the bending of the chip or the introduction of a one dimensional vibration that produces an interrupted cutting pattern. Unfortunately, neither of these approaches is particularly effective when making a 'light depth-of-cut' on a contoured workpiece. The historical solution to this problem has been for the machinist to use long-handled tweezers to 'pull the chip' and try to keep it submerged in the chip pan; however, this approach is not practical for all machining operations. This paper discusses a research project involving the Y-12 National Security Complex and the University of North Carolina at Charlotte in which unique, oscillatory part programs are used to continuously create an interrupted cut that generates pre-defined, user-selectable chip lengths.

  16. Proceedings of a workshop on uses of depleted uranium in storage, transportation and repository facilities

    SciTech Connect (OSTI)

    1997-12-31

    A workshop on the potential uses of depleted uranium (DU) in the repository was organized to coordinate the planning of future activities. The attendees, the original workshop objective and the agenda are provided in Appendices A, B and C. After some opening remarks and discussions, the objectives of the workshop were revised to: (1) exchange information and views on the status of the Department of Energy (DOE) activities related to repository design and planning; (2) exchange information on DU management and planning; (3) identify potential uses of DU in the storage, transportation, and disposal of high-level waste and spent fuel; and (4) define the future activities that would be needed if potential uses were to be further evaluated and developed. This summary of the workshop is intended to be an integrated resource for planning of any future work related to DU use in the repository. The synopsis of the first day`s presentations is provided in Appendix D. Copies of slides from each presenter are presented in Appendix E.

  17. Imaging the Solar Cell P-N Junction and Depletion Region Using Secondary Electron Contrast

    SciTech Connect (OSTI)

    Heath, J. T.; Jiang, C. S.; Al-Jassim, M. M.

    2011-01-01

    We report on secondary electron (SE) images of cross-sectioned multicrystalline Si and GaAs/GaInP solar cell devices, focusing on quantifying the relationship between the apparent n{sup +}-p contrast and characteristic electronic features of the device. These samples allow us to compare the SE signal from devices which have very different physical characteristics: differing materials, diffused junction versus abrupt junction, heterojunction versus homojunction. Despite these differences, we find that the SE image contrast for both types of sample, and as a function of reverse bias across the diode, closely agrees with PC1D simulations of the bulk electrostatic potential in the device, accurately yielding the depletion edge and width. A spatial derivative of the SE data shows a local maximum at the metallurgical junction. Such data are valuable, for example, in studying the conformity of a diffused junction to the textured surface topography. These data also extend our understanding of the origin of the SE contrast.

  18. Running Out of and Into Oil: Analyzing Global Oil Depletion and Transition Through 2050

    SciTech Connect (OSTI)

    Greene, D.L.

    2003-11-14

    This report presents a risk analysis of world conventional oil resource production, depletion, expansion, and a possible transition to unconventional oil resources such as oil sands, heavy oil and shale oil over the period 2000 to 2050. Risk analysis uses Monte Carlo simulation methods to produce a probability distribution of outcomes rather than a single value. Probability distributions are produced for the year in which conventional oil production peaks for the world as a whole and the year of peak production from regions outside the Middle East. Recent estimates of world oil resources by the United States Geological Survey (USGS), the International Institute of Applied Systems Analysis (IIASA), the World Energy Council (WEC) and Dr. C. Campbell provide alternative views of the extent of ultimate world oil resources. A model of oil resource depletion and expansion for twelve world regions is combined with a market equilibrium model of conventional and unconventional oil supply and demand to create a World Energy Scenarios Model (WESM). The model does not make use of Hubbert curves but instead relies on target reserve-to-production ratios to determine when regional output will begin to decline. The authors believe that their analysis has a bias toward optimism about oil resource availability because it does not attempt to incorporate political or environmental constraints on production, nor does it explicitly include geologic constraints on production rates. Global energy scenarios created by IIASA and WEC provide the context for the risk analysis. Key variables such as the quantity of undiscovered oil and rates of technological progress are treated as probability distributions, rather than constants. Analyses based on the USGS and IIASA resource assessments indicate that conventional oil production outside the Middle East is likely to peak sometime between 2010 and 2030. The most important determinants of the date are the quantity of undiscovered oil, the rate at which unconventional oil production can be expanded, and the rate of growth of reserves and enhanced recovery. Analysis based on data produced by Campbell indicates that the peak of non-Middle East production will occur before 2010. For total world conventional oil production, the results indicate a peak somewhere between 2020 and 2050. Key determinants of the peak in world oil production are the rate at which the Middle East region expands its output and the minimum reserves-to-production ratios producers will tolerate. Once world conventional oil production peaks, first oil sands and heavy oil from Canada, Venezuela and Russia, and later some other source such as shale oil from the United States must expand if total world oil consumption is to continue to increase. Alternative sources of liquid hydrocarbon fuels, such as coal or natural gas are also possible resources but not considered in this analysis nor is the possibility of transition to a hydrogen economy. These limitations were adopted to simplify the transition analysis. Inspection of the paths of conventional oil production indicates that even if world oil production does not peak before 2020, output of conventional oil is likely to increase at a substantially slower rate after that date. The implication is that there will have to be increased production of unconventional oil after that date if world petroleum consumption is to grow.

  19. Ozone depletion, developing countries, and human rights: Seeking better ground on which to fight for protection of the ozone layer

    SciTech Connect (OSTI)

    Williams, V.

    1995-12-31

    I urge you not to take a complacent view of the situation. The state of depletion of the ozone layer continues to be alarming... In February, 1993, the ozone levels over North America and most of Europe were 20 percent below normal... Even now, millions of tons of CFC [chlorofluorocarbon] products are en route to their fatal stratospheric rendezvous... This exponential increase calls for increased reflection on the state of the ozone layer and calls for bold decisions.

  20. FORIG: a computer code for calculating radionuclide generation and depletion in fusion and fission reactors. User's manual

    SciTech Connect (OSTI)

    Blink, J.A.

    1985-03-01

    In this manual we describe the use of the FORIG computer code to solve isotope-generation and depletion problems in fusion and fission reactors. FORIG runs on a Cray-1 computer and accepts more extensive activation cross sections than ORIGEN2 from which it was adapted. This report is an updated and a combined version of the previous ORIGEN2 and FORIG manuals. 7 refs., 15 figs., 13 tabs.

  1. Diffraction barrier breakthrough in coherent anti-Stokes Raman scattering microscopy by additional probe-beam-induced phonon depletion

    SciTech Connect (OSTI)

    Liu Wei; Niu Hanben

    2011-02-15

    We provide an approach to significantly break the diffraction limit in coherent anti-Stokes Raman scattering (CARS) microscopy via an additional probe-beam-induced photon depletion (APIPD). The additional probe beam, whose profile is doughnut shaped and whose wavelength is different from the Gaussian probe beam, depletes the phonons to yield an unwanted anti-Stokes signal within a certain bandwidth at the rim of the diffraction-limited spot. When the Gaussian probe beam that follows immediately arrives, no anti-Stokes signal is generated in this region, resembling stimulated emission depletion (STED) microscopy, and the spot-generating useful anti-Stokes signals by this beam are substantially suppressed to a much smaller dimension. Scanning the spot renders three-dimensional, label-free, and chemically selective CARS images with subdiffraction resolution. Also, resolution-enhanced images of the molecule, specified by its broadband even-total CARS spectral signals not only by one anti-Stokes signal for its special chemical bond, can be obtained by employing a supercontinuum source.

  2. Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages

    SciTech Connect (OSTI)

    Forsberg, C.W.

    1996-01-20

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

  3. Refurbishment of uranium hexafluoride cylinder storage yards C-745-K, L, M, N, and P and construction of a new uranium hexafluoride cylinder storage yard (C-745-T) at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    SciTech Connect (OSTI)

    1996-07-01

    The Paducah Gaseous Diffusion Plant (PGDP) is a uranium enrichment facility owned by the US Department of Energy (DOE). A residual of the uranium enrichment process is depleted uranium hexafluoride (UF6). Depleted UF6, a solid at ambient temperature, is stored in 32,200 steel cylinders that hold a maximum of 14 tons each. Storage conditions are suboptimal and have resulted in accelerated corrosion of cylinders, increasing the potential for a release of hazardous substances. Consequently, the DOE is proposing refurbishment of certain existing yards and construction of a new storage yard. This environmental assessment (EA) evaluates the impacts of the proposed action and no action and considers alternate sites for the proposed new storage yard. The proposed action includes (1) renovating five existing cylinder yards; (2) constructing a new UF6 storage yard; handling and onsite transport of cylinders among existing yards to accommodate construction; and (4) after refurbishment and construction, restacking of cylinders to meet spacing and inspection requirements. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major Federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969. Therefore, DOE is issuing a Finding of No Significant Impact. Additionally, it is reported in this EA that the loss of less than one acre of wetlands at the proposed project site would not be a significant adverse impact.

  4. H. R. 4670: a bill to amend the Internal Revenue Code of 1954 to increase the depletion allowance for oil and natural gas, and to allow percentage depletion for stripper well production of integrated producers. Introduced in the House of Representatives, Ninety-Ninth Congress, Second Session, April 23, 1986

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    An amendment to the Internal Revenue Code of 1954 increases the depletion allowance for oil and natural gas and allows percentage depletion for stripper well production of integrated producers. The bill was referred to the House Committee on Ways and Means after its introduction.

  5. ZPR-3 Assembly 11 : A cylindrical sssembly of highly enriched uranium and depleted uranium with an average {sup 235}U enrichment of 12 atom % and a depleted uranium reflector.

    SciTech Connect (OSTI)

    Lell, R. M.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; National Security; Inst. of Physics and Power Engineering

    2010-09-30

    Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 11 (ZPR-3/11) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 12 at.% and a depleted uranium reflector. Approximately 79.7% of the total fissions in this assembly occur above 100 keV, approximately 20.3% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 8 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specificationsa and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 11 began in early January 1958, and the Assembly 11 program ended in late January 1958. The core consisted of highly enriched uranium (HEU) plates and depleted uranium plates loaded into stainless steel drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, six columns of 0.125 in.-wide (3.175 mm) depleted uranium plates and one column of 1.0 in.-wide (25.4 mm) depleted uranium plates. The length of each column was 10 in. (254.0 mm) in each half of the core. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the depleted uranium radial blanket was approximately 14 in. (355.6 mm), and the length of the radial blanket in each half of the matrix was 22 in. (558.8 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/11, the reference critical configuration was loading 10 which was critical on January 21, 1958. Subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/11 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. A very accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/11 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must do this without increasing the total uncertain

  6. Grain boundary depletion and migration during selective oxidation of Cr in a Ni-5Cr binary alloy exposed to high-temperature hydrogenated water

    SciTech Connect (OSTI)

    Schreiber, Daniel K.; Olszta, Matthew J.; Bruemmer, Stephen M.

    2014-10-01

    High-resolution microscopy of a high-purity Ni-5Cr alloy exposed to 360°C hydrogenated water reveals intergranular selective oxidation of Cr accompanied by local Cr depletion and diffusion-induced grain boundary migration (DIGM). The corrosion-product oxide consists of a porous, interconnected network of Cr2O3 platelets with no further O ingress into the metal ahead. Extensive grain boundary depletion of Cr (to <0.05at.%) is observed typically 20–100 nm wide as a result of DIGM and reaching depths of many micrometers beyond the oxidation front.

  7. HIGHLY DEPLETED ETHANE AND MILDLY DEPLETED METHANOL IN COMET 21P/GIACOBINI-ZINNER: APPLICATION OF A NEW EMPIRICAL {nu}{sub 2}-BAND MODEL FOR CH{sub 3}OH NEAR 50 K

    SciTech Connect (OSTI)

    DiSanti, M. A.; Bonev, B. P.; Villanueva, G. L.; Mumma, M. J.

    2013-01-20

    We obtained infrared spectra of Comet 21P/Giacobini-Zinner (hereafter 21P/GZ) using NIRSPEC at Keck II on UT 2005 June 3, approximately one month before perihelion, that simultaneously sampled H{sub 2}O, C{sub 2}H{sub 6}, and CH{sub 3}OH. Our production rate for H{sub 2}O (3.885 {+-} 0.074 Multiplication-Sign 10{sup 28} molecules s{sup -1}) was consistent with that measured during other apparitions of 21P/GZ as retrieved from optical, infrared, and radio observations. Our analysis also provided values for rotational temperature (T {sub rot} = 51 {+-} 3 K) and the abundance ratio of ortho and para spin populations for water (OPR = 2.99 {+-} 0.23, implying a spin temperature exceeding 50 K). Six Q-branches in the {nu}{sub 7} band of C{sub 2}H{sub 6} provided a production rate (5.27 {+-} 0.90 Multiplication-Sign 10{sup 25} s{sup -1}) that corresponded to an abundance ratio of 0.136 {+-} 0.023 Multiplication-Sign 10{sup -2} relative to H{sub 2}O, confirming the previously reported strong depletion of C{sub 2}H{sub 6} from IR observations during the 1998 apparition, and in qualitative agreement with the depletion of C{sub 2} known from optical studies of 21P/GZ. For CH{sub 3}OH, we applied our recently published quantum model for the {nu}{sub 3} band to obtain a rotational temperature (48{sup +10}/{sub -7} K) consistent with that obtained for H{sub 2}O. In addition, we developed a new empirical model for the CH{sub 3}OH {nu}{sub 2} band, based on observations of Comet 8P/Tuttle with NIRSPEC. The application of our {nu}{sub 2} model to 21P/GZ yielded a production rate in agreement with that obtained from the {nu}{sub 3} band. Combining results from both {nu}{sub 2} and {nu}{sub 3} bands provided a production rate (47.5 {+-} 4.4 Multiplication-Sign 10{sup 25} s{sup -1}) that corresponded to an abundance ratio of 1.22 {+-} 0.11 Multiplication-Sign 10{sup -2} relative to H{sub 2}O in 21P/GZ, indicating mild depletion of CH{sub 3}OH. Together with observations of 21P/GZ in 1998, our study provides a measure of primary volatile production rates for this Jupiter family comet over multiple apparitions using high-resolution IR spectroscopy.

  8. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

    SciTech Connect (OSTI)

    N /A

    2003-11-28

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). Although not part of the proposed action, an option of shipping all cylinders (DUF{sub 6}, low-enriched UF{sub 6} [LEU-UF{sub 6}], and empty) stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Paducah rather than to Portsmouth is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Paducah site. A separate EIS (DOE/EIS-0360) evaluates the potential environmental impacts for the proposed Portsmouth conversion facility.

  9. Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants, May 2012

    Office of Environmental Management (EM)

    Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants May 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background

  10. Design and Implementation of a C02 Flood Utilizing Advanced Reservoir Characterization and Horizontal Injection Wells in a Shallow Shelf Carbonate Approaching Waterflood Depletion

    SciTech Connect (OSTI)

    1997-08-01

    The objective is to utilize reservoir characteristics and advanced technologies to optimize the design of a carbon dioxide (CO2) project for the South Cowden Unit (SCU) located in Ector County, Texas. The SCU is a mature, relatively small, shallow shelf carbonate unit nearing waterflood depletion. Also the project seeks to demonstrate the performance and economic viability of the project in the field.

  11. Preliminary formation analysis for compressed air energy storage in depleted natural gas reservoirs : a study for the DOE Energy Storage Systems Program.

    SciTech Connect (OSTI)

    Gardner, William Payton

    2013-06-01

    The purpose of this study is to develop an engineering and operational understanding of CAES performance for a depleted natural gas reservoir by evaluation of relative permeability effects of air, water and natural gas in depleted natural gas reservoirs as a reservoir is initially depleted, an air bubble is created, and as air is initially cycled. The composition of produced gases will be evaluated as the three phase flow of methane, nitrogen and brine are modeled. The effects of a methane gas phase on the relative permeability of air in a formation are investigated and the composition of the produced fluid, which consists primarily of the amount of natural gas in the produced air are determined. Simulations of compressed air energy storage (CAES) in depleted natural gas reservoirs were carried out to assess the effect of formation permeability on the design of a simple CAES system. The injection of N2 (as a proxy to air), and the extraction of the resulting gas mixture in a depleted natural gas reservoir were modeled using the TOUGH2 reservoir simulator with the EOS7c equation of state. The optimal borehole spacing was determined as a function of the formation scale intrinsic permeability. Natural gas reservoir results are similar to those for an aquifer. Borehole spacing is dependent upon the intrinsic permeability of the formation. Higher permeability allows increased injection and extraction rates which is equivalent to more power per borehole for a given screen length. The number of boreholes per 100 MW for a given intrinsic permeability in a depleted natural gas reservoir is essentially identical to that determined for a simple aquifer of identical properties. During bubble formation methane is displaced and a sharp N2methane boundary is formed with an almost pure N2 gas phase in the bubble near the borehole. During cycling mixing of methane and air occurs along the boundary as the air bubble boundary moves. The extracted gas mixture changes as a function of time and proximity of the bubble boundary to the well. For all simulations reported here, with a formation radius above 50 m the maximum methane composition in the produced gas phase was less than 0.5%. This report provides an initial investigation of CAES in a depleted natural gas reservoir, and the results will provide useful guidance in CAES system investigation and design in the future.

  12. Three dimensional dust-acoustic solitary waves in an electron depleted dusty plasma with two-superthermal ion-temperature

    SciTech Connect (OSTI)

    Borhanian, J.; Shahmansouri, M.

    2013-01-15

    A theoretical investigation is carried out to study the existence and characteristics of propagation of dust-acoustic (DA) waves in an electron-depleted dusty plasma with two-temperature ions, which are modeled by kappa distribution functions. A three-dimensional cylindrical Kadomtsev-Petviashvili equation governing evolution of small but finite amplitude DA waves is derived by means of a reductive perturbation method. The influence of physical parameters on solitary wave structure is examined. Furthermore, the energy integral equation is used to study the existence domains of the localized structures. It is found that the present model can be employed to describe the existence of positive as well as negative polarity DA solitary waves by selecting special values for parameters of the system, e.g., superthermal index of cold and/or hot ions, cold to hot ion density ratio, and hot to cold ion temperature ratio. This model may be useful to understand the excitation of nonlinear DA waves in astrophysical objects.

  13. Benchmark of SCALE (SAS2H) isotopic predictions of depletion analyses for San Onofre PWR MOX fuel

    SciTech Connect (OSTI)

    Hermann, O.W.

    2000-02-01

    The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, after discharge from reactors is of significant interest to the Fissile Materials Disposition Program. The validation of the SCALE (SAS2H) depletion code for use in the prediction of isotopic compositions of MOX fuel, similar to previous validation studies on uranium-only fueled reactors, has corresponding significance. The EEI-Westinghouse Plutonium Recycle Demonstration Program examined the use of MOX fuel in the San Onofre PWR, Unit 1, during cycles 2 and 3. Isotopic analyses of the MOX spent fuel were conducted on 13 actinides and {sup 148}Nd by either mass or alpha spectrometry. Six fuel pellet samples were taken from four different fuel pins of an irradiated MOX assembly. The measured actinide inventories from those samples has been used to benchmark SAS2H for MOX fuel applications. The average percentage differences in the code results compared with the measurement were {minus}0.9% for {sup 235}U and 5.2% for {sup 239}Pu. The differences for most of the isotopes were significantly larger than in the cases for uranium-only fueled reactors. In general, comparisons of code results with alpha spectrometer data had extreme differences, although the differences in the calculations compared with mass spectrometer analyses were not extremely larger than that of uranium-only fueled reactors. This benchmark study should be useful in estimating uncertainties of inventory, criticality and dose calculations of MOX spent fuel.

  14. Influence of hydraulic and geomorphologic components of a semi-arid watershed on depleted-uranium transport

    SciTech Connect (OSTI)

    Becker, N.M.

    1991-01-01

    Investigations were undertaken to determine the fate and transport of depleted uranium away from high explosive firing sites at Los Alamos National Laboratory in north-central New Mexico. Investigations concentrated on a small, semi-arid watershed which drains 5 firing sites. Sampling for uranium in spring/summer/fall runoff, snowmelt runoff, in fallout, and in soil and in sediments revealed that surface water is the main transport mechanism. Although the watershed is less than 8 km{sup 2}, flow discontinuity was observed between the divide and the outlet; flow discontinuity occurs in semi-arid and arid watersheds, but was unexpected at this scale. This region, termed a discharge sink, is an area where all flow infiltrates and all sediment, including uranium, deposits during nearly all flow events; it is estimated that the discharge sink has provided the locale for uranium detention during the last 23 years. Mass balance calculations indicate that over 90% of uranium expended still remains at or nearby the firing sites. Leaching experiments determined that uranium can rapidly dissolve from the solid phase. It is postulated that precipitation and runoff which percolate vertically through uranium-contaminated soil and sediment are capable of transporting uranium in the dissolved phase to deeper strata. This may be the key transport mechanism which moves uranium out of the watershed.

  15. revealing H{sub 2}D{sup +} depletion and compact structure in starless and protostellar cores with ALMA

    SciTech Connect (OSTI)

    Friesen, R. K.; Di Francesco, J.; Bourke, T. L.; Caselli, P.; Jørgensen, J. K.; Pineda, J. E.; Wong, M.

    2014-12-10

    We present Atacama Large Millimeter/submillimeter Array (ALMA) observations of the submillimeter dust continuum and H{sub 2}D{sup +} 1{sub 10}-1{sub 11} emission toward two evolved, potentially protostellar cores within the Ophiuchus molecular cloud, Oph A SM1 and SM1N. The data reveal small-scale condensations within both cores, with mass upper limits of M ? 0.02 M {sub ?} (?20 M {sub Jup}). The SM1 condensation is consistent with a nearly symmetric Gaussian source with a width of only 37 AU. The SM1N condensation is elongated and extends 500 AU along its major axis. No evidence for substructure is seen in either source. A Jeans analysis indicates that these sources are unlikely to fragment, suggesting that both will form single stars. H{sub 2}D{sup +} is only detected toward SM1N, offset from the continuum peak by ?150-200 AU. This offset may be due to either heating from an undetected, young, low-luminosity protostellar source or first hydrostatic core, or HD (and consequently H{sub 2}D{sup +}) depletion in the cold center of the condensation. We propose that SM1 is protostellar and that the condensation detected by ALMA is a warm (T ? 30-50 K) accretion disk. The less concentrated emission of the SM1N condensation suggests that it is still starless, but we cannot rule out the presence of a low-luminosity source, perhaps surrounded by a pseudodisk. These data observationally reveal the earliest stages of the formation of circumstellar accretion regions and agree with theoretical predictions that disk formation can occur very early in the star formation process, coeval with or just after the formation of a first hydrostatic core or protostar.

  16. Assessment of Reusing 14-ton, Thin-Wall, Depleted UF{sub 6} Cylinders as LLW Disposal Containers

    SciTech Connect (OSTI)

    O'Connor, D.G.

    2000-11-30

    Approximately 700,000 MT of DUF{sub 6} is stored, or will be produced under a current agreement with the USEC, at the Paducah site in Kentucky, Portsmouth site in Ohio, and ETTP site in Tennessee. On July 21, 1998, the 105th Congress approved Public Law 105-204 (Ref; 1), which directed that facilities be built at the Kentucky and Ohio sites to convert DUF{sub 6} to a stable form for disposition. On July 6, 1999, the Department of Energy (DOE) issued the ''Final Plan for the Conversion of Depleted Uranium Hexafluoride as Required by Public Law 105-204 (Ref. 2), in which DOE committed to develop a Depleted Uranium Hexafluoride Materials Use Roadmap''. On September 1, 2000, DOE issued the Draft Depleted Uranium Hexafluoride Materials Use Roadmap (Ref. 3) (Roadmap), which provides alternate paths for the long-term storage, beneficial use, and eventual disposition of each product form and material that will result from the DUF{sub 6} conversion activity. One of the paths being considered for DUF{sub 6} cylinders is to reuse the empty cylinders as containers to transport and dispose of LLW, including the converted DU. The Roadmap provides results of the many alternate uses and disposal paths for conversion products and the empty DUF{sub 6} storage cylinders. As a part of the Roadmap, evaluations were conducted of cost savings, technical maturity, barriers to implementation, and other impacts. Results of these evaluations indicate that using the DUF{sub 6} storage cylinders as LLW disposal containers could provide moderate cost savings due to the avoided cost of purchasing LLW packages and the avoided cost of disposing of the cylinders. No significant technical or institutional issues were identified that would make using cylinders as LLW packages less effective than other disposition paths. Over 58,000 cylinders have been used, or will be used, to store DUF{sub 6}. Over 51,000 of those cylinders are 14TTW cylinders with a nominal wall thickness of 5/16-m (0.79 cm). These- 14TTW cylinders, which have a nominal diameter of 48 inches and nominally contain 14 tons (12.7 MT) of DUF{sub 6}, were originally designed and fabricated for temporary storage of DUF{sub 6}. They were fabricated from pressure-vessel-grade steels according to the provisions of the ASME Boiler and Pressure Vessel Code (Ref. 4). Cylinders are stored in open yards at the three sites and, due to historical storage techniques, were subject to corrosion. Roughly 10,000 of the 14TTW cylinders are considered substandard (Ref. 5) due to corrosion and other structural anomalies caused by mishandling. This means that approximately 40,000 14TTW cylinders could be made available as containers for LLW disposal In order to demonstrate the use of 14TTW cylinders as LLW disposal containers, several qualifying tasks need to be performed. Two demonstrations are being considered using 14TTW cylinders--one demonstration using contaminated soil and one demonstration using U{sub 3}O{sub 8}. The objective of this report are to determine how much information is known that could be used to support the demonstrations, and how much additional work will need to be done in order to conduct the demonstrations. Information associated with the following four qualifying tasks are evaluated in this report. (1) Perform a review of structural assessments that have been conducted for 14TTW. (2) Develop a procedure for filling 14TTW cylinders with LLW that have been previously washed. (3) Evaluate the transportation requirements for shipping 14TTW cylinders containing LLW. (4) Evaluate the WAC that will be imposed by the NTS. Two assumptions are made to facilitate this evaluation of using DUF{sub 6} cylinders as LLW disposal containers. (1) Only 14TTW cylinders will be considered for use as LLW containers, and (2) The NTS will be the LLW disposal site.

  17. Design and Implementation of a CO(2) Flood Utilizing Advanced Reservoir Characterization and Horizontal Injection Wells in Shallow Shelf Carbonate Approaching Waterflood Depletion

    SciTech Connect (OSTI)

    Harpole, K.J.; Dollens, K.B.; Durrett, E.G.; Bles, J.S

    1997-10-31

    The first objective is to utilize reservoir characterization and advanced technologies to optimize the design of a carbon dioxide (CO) project for the South Cowden Unit (SCU) located in Ector County, Texas. The SCU is a mature, relatively small, shallow shelf carbonate unit nearing waterflood depletion. The second objective is to demonstrate the performance and economic viability of the project in the field. All work this quarter falls within the demonstration project.

  18. IDENTIFICATION OF AN {sup 84}Sr-DEPLETED CARRIER IN PRIMITIVE METEORITES AND IMPLICATIONS FOR THERMAL PROCESSING IN THE SOLAR PROTOPLANETARY DISK

    SciTech Connect (OSTI)

    Paton, Chad; Schiller, Martin; Bizzarro, Martin E-mail: schiller@snm.ku.dk

    2013-02-01

    The existence of correlated nucleosynthetic heterogeneities in solar system reservoirs is now well demonstrated for numerous nuclides. However, it has proven difficult to discriminate between the two disparate processes that can explain such correlated variability: incomplete mixing of presolar material or secondary processing of a well-mixed disk. Using stepwise acid-leaching of the Ivuna CI-chondrite, we show that unlike other nuclides such as {sup 54}Cr and {sup 50}Ti, Sr-isotope variability is the result of a carrier depleted in {sup 84}Sr. The carrier is most likely presolar SiC, which is known to have both high Sr-concentrations relative to solar abundances and extremely depleted {sup 84}Sr compositions. Thus, variability in {sup 84}Sr in meteorites and their components can be attributed to varying contributions from presolar SiC. The observed {sup 84}Sr excesses in calcium-aluminum refractory inclusions (CAIs) suggest their formation from an SiC-free gaseous reservoir, whereas the {sup 84}Sr depletions present in differentiated meteorites require their formation from material with an increased concentration of SiC relative to CI chondrites. The presence of a positive correlation between {sup 84}Sr and {sup 54}Cr, despite being hosted in carriers of negative and positive anomalies, respectively, is not compatible with incomplete mixing of presolar material but instead suggests that the solar system's nucleosynthetic heterogeneity reflects selective thermal processing of dust. Based on vaporization experiments of SiC under nebular conditions, the lack of SiC material in the CAI-forming gas inferred from our data requires that the duration of thermal processing of dust resulting in the vaporization of CAI precursors was extremely short-lived, possibly lasting only hours to days.

  19. Widget:MailChimp | Open Energy Information

    Open Energy Info (EERE)

    source History View New Pages Recent Changes All Special Pages Semantic SearchQuerying Get Involved Help Apps Datasets Community Login | Sign Up Search Widget Edit History...

  20. NAME ORGANIZATION E-MAIL PHONE

    Energy Savers [EERE]

    Bush, Andy Oak Ridge Nat'l Laboratory buschac@ornl.gov (865) 574-2105 (Alternate) Miller, Ruth Oak Ridge Nat'l Laboratory millerra@ornl.gov (865) 576-0393 Kirsch, Greg Sandia...

  1. Mail Management Memorandum, July 2, 2010

    Energy Savers [EERE]

  2. 2014 Uranium Marketing Annual Report

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

    1 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 Deliveries Uranium concentrate Natural UF 6 Enriched UF 6 Total Purchases 2,004 1,312 ...

  3. ZPR-3 Assembly 6F : A spherical assembly of highly enriched uranium, depleted uranium, aluminum and steel with an average {sup 235}U enrichment of 47 atom %.

    SciTech Connect (OSTI)

    Lell, R. M.; McKnight, R. D; Schaefer, R. W.; Nuclear Engineering Division

    2010-09-30

    Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 6 consisted of six phases, A through F. In each phase a critical configuration was constructed to simulate a very simple shape such as a slab, cylinder or sphere that could be analyzed with the limited analytical tools available in the 1950s. In each case the configuration consisted of a core region of metal plates surrounded by a thick depleted uranium metal reflector. The average compositions of the core configurations were essentially identical in phases A - F. ZPR-3 Assembly 6F (ZPR-3/6F), the final phase of the Assembly 6 program, simulated a spherical core with a thick depleted uranium reflector. ZPR-3/6F was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 47 at.%. Approximately 81.4% of the total fissions in this assembly occur above 100 keV, approximately 18.6% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 7 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3/6F began in late December 1956, and the experimental measurements were performed in January 1957. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates, perforated aluminum plates and stainless steel plates loaded into aluminum drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of three columns of 0.125 in.-wide (3.175 mm) HEU plates, three columns of 0.125 in.-wide depleted uranium plates, nine columns of 0.125 in.-wide perforated aluminum plates and one column of stainless steel plates. The maximum length of each column of core material in a drawer was 9 in. (228.6 mm). Because of the goal to produce an approximately spherical core, core fuel and diluent column lengths generally varied between adjacent drawers and frequently within an individual drawer. The axial reflector consisted of depleted uranium plates and blocks loaded in the available space in the front (core) drawers, with the remainder loaded into back drawers behind the front drawers. The radial reflector consisted of blocks of depleted uranium loaded directly into the matrix tubes. The assembly geometry approximated a reflected sphere as closely as the square matrix tubes, the drawers and the shapes of fuel and diluent plates allowed. According to the logbook and loading records for ZPR-3/6F

  4. Carrier transport and collection in fully depleted semiconductors by a combined action of the space charge field and the field due to electrode voltages

    DOE Patents [OSTI]

    Rehak, Pavel (Patchogue, NY); Gatti, Emilio (Lesmo, IT)

    1987-01-01

    A semiconductor charge transport device and method for making same, characterized by providing a thin semiconductor wafer having rectifying junctions on its opposing major surfaces and including a small capacitance ohmic contact, in combination with bias voltage means and associated circuit means for applying a predetermined voltage to effectively deplete the wafer in regions thereof between the rectifying junctions and the ohmic contact. A charge transport device of the invention is usable as a drift chamber, a low capacitance detector, or a charge coupled device each constructed according to the methods of the invention for making such devices. Detectors constructed according to the principles of the invention are characterized by having significantly higher particle position indicating resolution than is attainable with prior art detectors, while at the same time requiring substantially fewer readout channels to realize such high resolution.

  5. Steady State Sputtering Yields and Surface Compositions of Depleted Uranium and Uranium Carbide bombarded by 30 keV Gallium or 16 keV Cesium Ions.

    SciTech Connect (OSTI)

    Siekhaus, W. J.; Teslich, N. E.; Weber, P. K.

    2014-10-23

    Depleted uranium that included carbide inclusions was sputtered with 30-keV gallium ions or 16-kev cesium ions to depths much greater than the ions’ range, i.e. using steady-state sputtering. The recession of both the uranium’s and uranium carbide’s surfaces and the ion corresponding fluences were used to determine the steady-state target sputtering yields of both uranium and uranium carbide, i.e. 6.3 atoms of uranium and 2.4 units of uranium carbide eroded per gallium ion, and 9.9 uranium atoms and 3.65 units of uranium carbide eroded by cesium ions. The steady state surface composition resulting from the simultaneous gallium or cesium implantation and sputter-erosion of uranium and uranium carbide were calculated to be U??Ga??, (UC)??Ga?? and U??Cs?, (UC)??Cs??, respectively.

  6. Streamlined approach for environmental restoration plan for corrective action unit 430, buried depleted uranium artillery round No. 1, Tonopah test range

    SciTech Connect (OSTI)

    NONE

    1996-09-01

    This plan addresses actions necessary for the restoration and closure of Corrective Action Unit (CAU) No. 430, Buried Depleted Uranium (DU) Artillery Round No. 1 (Corrective Action Site No. TA-55-003-0960), a buried and unexploded W-79 Joint Test Assembly (JTA) artillery test projectile with high explosives (HE), at the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Tonopah Test Range (TTR) in south-central Nevada. It describes activities that will occur at the site as well as the steps that will be taken to gather adequate data to obtain a notice of completion from Nevada Division of Environmental Protection (NDEP). This plan was prepared under the Streamlined Approach for Environmental Restoration (SAFER) concept, and it will be implemented in accordance with the Federal Facility Agreement and Consent Order (FFACO) and the Resource Conservation and Recovery Act (RCRA) Industrial Sites Quality Assurance Project Plan.

  7. Carrier transport and collection in fully depleted semiconductors by a combined action of the space charge field and the field due to electrode voltages

    DOE Patents [OSTI]

    Rehak, P.; Gatti, E.

    1987-08-18

    A semiconductor charge transport device and method for making same are disclosed, characterized by providing a thin semiconductor wafer having rectifying junctions on its opposing major surfaces and including a small capacitance ohmic contact, in combination with bias voltage means and associated circuit means for applying a predetermined voltage to effectively deplete the wafer in regions thereof between the rectifying junctions and the ohmic contact. A charge transport device of the invention is usable as a drift chamber, a low capacitance detector, or a charge coupled device each constructed according to the methods of the invention for making such devices. Detectors constructed according to the principles of the invention are characterized by having significantly higher particle position indicating resolution than is attainable with prior art detectors, while at the same time requiring substantially fewer readout channels to realize such high resolution. 16 figs.

  8. Carrier transport and collection in fully depleted semiconductors by a combined action of the space charge field and the field due to electrode voltages

    DOE Patents [OSTI]

    Rehak, P.; Gatti, E.

    1984-02-24

    A semiconductor charge transport device and method for making same, characterized by providing a thin semiconductor wafer having rectifying functions on its opposing major surfaces and including a small capacitance ohmic contact, in combination with bias voltage means and associated circuit means for applying a predetermined voltage to effectively deplete the wafer in regions thereof between the rectifying junctions and the ohmic contact. A charge transport device of the invention is usable as a drift chamber, a low capacitance detector, or a charge coupled device each constructed according to the methods of the invention for making such devices. Detectors constructed according to the principles of the invention are characterized by having significantly higher particle position indicating resolution than is attainable with prior art detectors, while at the same time requiring substantially fewer readout channels to realize such high resolution.

  9. Hydrologic transport of depleted uranium associated with open air dynamic range testing at Los Alamos National Laboratory, New Mexico, and Eglin Air Force Base, Florida

    SciTech Connect (OSTI)

    Becker, N.M.; Vanta, E.B.

    1995-05-01

    Hydrologic investigations on depleted uranium fate and transport associated with dynamic testing activities were instituted in the 1980`s at Los Alamos National Laboratory and Eglin Air Force Base. At Los Alamos, extensive field watershed investigations of soil, sediment, and especially runoff water were conducted. Eglin conducted field investigations and runoff studies similar to those at Los Alamos at former and active test ranges. Laboratory experiments complemented the field investigations at both installations. Mass balance calculations were performed to quantify the mass of expended uranium which had transported away from firing sites. At Los Alamos, it is estimated that more than 90 percent of the uranium still remains in close proximity to firing sites, which has been corroborated by independent calculations. At Eglin, we estimate that 90 to 95 percent of the uranium remains at test ranges. These data demonstrate that uranium moves slowly via surface water, in both semi-arid (Los Alamos) and humid (Eglin) environments.

  10. Commercial considerations in conversion and UF{sub 6} transactions

    SciTech Connect (OSTI)

    1994-02-01

    This article addresses various commercial considerations that result from the conversion of U3O8 into UF6 and the associated physical characteristics of natural UF6. Handling, transport, conversion, and enrichment of UF6 are discussed. Avenues of acquisition, including nation of origin, are also noted.

  11. Source Term Modeling for Evaluating the Potential Impacts to Groundwater of Fluids Escaping from a Depleted Oil Reservoir Used for Carbon Sequestration

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Brown, Christopher F.

    2014-06-13

    In recent years depleted oil reservoirs have received special interest as carbon storage reservoirs because of their potential to offset costs through collaboration with enhanced oil recovery projects. Modeling is currently being conducted to evaluate potential risks to groundwater associated with leakage of fluids from depleted oil reservoirs used for storage of CO2. Modeling results reported here focused on understanding how toxic organic compounds found in oil will distribute between the various phases within a storage reservoir after introduction of CO2, understanding the migration potential of these compounds, and assessing potential groundwater impacts should leakage occur. Two model scenarios were conducted to evaluate how organic components in oil will distribute among the phases of interest (oil, CO2, and brine). The first case consisted of 50 wt.% oil and 50 wt.% water; the second case was 90 wt.% CO2 and 10 wt.% oil. Several key organic compounds were selected for special attention in this study based upon their occurrence in oil at significant concentrations, relative toxicity, or because they can serve as surrogate compounds for other more highly toxic compounds for which required input data are not available. The organic contaminants of interest (COI) selected for this study were benzene, toluene, naphthalene, phenanthrene, and anthracene. Partitioning of organic compounds between crude oil and supercritical CO2 was modeled using the Peng-Robinson equation of state over temperature and pressure conditions that represent the entire subsurface system (from those relevant to deep geologic carbon storage environments to near surface conditions). Results indicate that for a typical set of oil reservoir conditions (75°C, and 21,520 kPa) negligible amounts of the COI dissolve into the aqueous phase. When CO2 is introduced into the reservoir such that the final composition of the reservoir is 90 wt.% CO2 and 10 wt.% oil, a significant fraction of the oil dissolves into the vapor phase. As the vapor phase moves up through the stratigraphic column, pressures and temperatures decrease, resulting in significant condensation of oil components. The heaviest organic components condense early in this process (at higher pressures and temperatures), while the lighter components tend to remain in the vapor phase until much lower pressures and temperatures are reached. Based on the model assumptions, the final concentrations of COI to reach an aquifer at 1,520 kPa and 25°C were quite significant for benzene and toluene, whereas the concentrations of polynuclear aromatic hydrocarbons that reach the aquifer were very small. This work demonstrates a methodology that can provide COI source term concentrations in CO2 leaking from a reservoir and entering an overlying aquifer for use in risk assessments.

  12. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    ... "BP AMOCO PRODUCTION COMPANY","9094 Other","District of Columbia" "CAMERON LNG",,"Delaware" "CAROLINA GAS TRANSMISSION CORP",,"Florida" "CENTANA ...

  13. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    ... GAS COMPANY","9087 Blast Furnace Gas","California","CA" "BP AMOCO PRODUCTION ... PIPELINE COMPANY",,"Nigeria" "NORTH BAJA PIPELINE COMPANY",,"Malaysia" "NORTH ...

  14. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    ... "NORTENO PIPELINE COMPANY",,"Japan" "NORTH BAJA PIPELINE COMPANY",,"Mexico" "NORTH COUNTRY ... WATER,GAS AND ELECTRIC" "SOUTHERN CALIFORNIA GAS COMPANY" "SOUTHERN LNG ...

  15. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    over the web using secure, encrypted processes. (It is the same method that commercial companies communicate with customers when transacting business on the web.) To use this ...

  16. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    over the web using secure, encrypted processes. (It is the same method that commercial companies use to communicate with customers when transacting business on the web.) To use ...

  17. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    business on the web.) To use this service, we recommend the use of Microsoft Internet Explorer 5.5 or later or Netscape 4.77 or later. Send your surveys using this secure...

  18. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    "REPORT YEAR 2011" "This report is mandatory under Public Law 93-275. Failure to comply may result in criminal fines, civil penalties and other sanctions as provided by law. ...

  19. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    under the Federal Energy Administration Act of 1974 (Public Law 93-275). Failure to comply may result in criminal fines, civil penalties and other sanctions as provided by law. ...

  20. This form may be submitted to the EIA by mail, fax, e-mail, or...

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

    ,,," Version No: 2014.001" "ANNUAL REPORT OF THE ORIGIN OF NATURAL GAS LIQUIDS PRODUCTION" "FORM EIA-64A" "REPORT YEAR 2014" "This report is...

  1. 4-Methylumbelliferone inhibits hyaluronan synthesis by depletion of cellular UDP-glucuronic acid and downregulation of hyaluronan synthase 2 and 3

    SciTech Connect (OSTI)

    Kultti, Anne; Pasonen-Seppaenen, Sanna; Jauhiainen, Marjo; Rilla, Kirsi J.; Kaernae, Riikka; Pyoeriae, Emma; Tammi, Raija H.; Tammi, Markku I.

    2009-07-01

    Hyaluronan accumulation on cancer cells and their surrounding stroma predicts an unfavourable disease outcome, suggesting that hyaluronan enhances tumor growth and spreading. 4-Methylumbelliferone (4-MU) inhibits hyaluronan synthesis and retards cancer spreading in experimental animals through mechanisms not fully understood. These mechanisms were studied in A2058 melanoma cells, MCF-7 and MDA-MB-361 breast, SKOV-3 ovarian and UT-SCC118 squamous carcinoma cells by analysing hyaluronan synthesis, UDP-glucuronic acid (UDP-GlcUA) content, and hyaluronan synthase (HAS) mRNA levels. The maximal inhibition in hyaluronan synthesis ranged 22-80% in the cell lines tested. Active glucuronidation of 4-MU produced large quantities of 4-MU-glucuronide, depleting the cellular UDP-GlcUA pool. The maximal reduction varied between 38 and 95%. 4-MU also downregulated HAS mRNA levels: HAS3 was 84-60% lower in MDA-MB-361, A2058 and SKOV-3 cells. HAS2 was the major isoenzyme in MCF-7 cells and lowered by 81%, similar to 88% in A2058 cells. These data indicate that both HAS substrate and HAS2 and/or HAS3 mRNA are targeted by 4-MU. Despite different target point sensitivities, the reduction of hyaluronan caused by 4-MU was associated with a significant inhibition of cell migration, proliferation and invasion, supporting the importance of hyaluronan synthesis in cancer, and the therapeutic potential of hyaluronan synthesis inhibition.

  2. ZPR-3 Assembly 12 : A cylindrical assembly of highly enriched uranium, depleted uranium and graphite with an average {sup 235}U enrichment of 21 atom %.

    SciTech Connect (OSTI)

    Lell, R. M.; McKnight, R. D.; Perel, R. L.; Wagschal, J. J.; Nuclear Engineering Division; Racah Inst. of Physics

    2010-09-30

    Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 12 (ZPR-3/12) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 21 at.%. Approximately 68.9% of the total fissions in this assembly occur above 100 keV, approximately 31.1% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 9 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 12 began in late Jan. 1958, and the Assembly 12 program ended in Feb. 1958. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates and graphite plates loaded into stainless steel drawers which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, seven columns of 0.125 in.-wide depleted uranium plates and seven columns of 0.125 in.-wide graphite plates. The length of each column was 9 in. (228.6 mm) in each half of the core. The graphite plates were included to produce a softer neutron spectrum that would be more characteristic of a large power reactor. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the radial blanket was approximately 12 in. and the length of the radial blanket in each half of the matrix was 21 in. (533.4 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/12, the reference critical configuration was loading 10 which was critical on Feb. 5, 1958. The subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/12 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. An accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/12 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must d

  3. Floodplain/wetland assessment of the effects of construction and operation ofa depleted uranium hexafluoride conversion facility at the Paducah, Kentucky,site.

    SciTech Connect (OSTI)

    Van Lonkhuyzen, R.

    2005-09-09

    The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF{sub 6} inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This floodplain/wetland assessment has been prepared by DOE, pursuant to Executive Order 11988 (''Floodplain Management''), Executive Order 11990 (Protection of Wetlands), and DOE regulations for implementing these Executive Orders as set forth in Title 10, Part 1022, of the ''Code of Federal Regulations'' (10 CFR Part 1022 [''Compliance with Floodplain and Wetland Environmental Review Requirements'']), to evaluate potential impacts to floodplains and wetlands from the construction and operation of a conversion facility at the DOE Paducah site. Reconstruction of the bridge crossing Bayou Creek would occur within the Bayou Creek 100-year floodplain. Replacement of bridge components, including the bridge supports, however, would not be expected to result in measurable long-term changes to the floodplain. Approximately 0.16 acre (0.064 ha) of palustrine emergent wetlands would likely be eliminated by direct placement of fill material within Location A. Some wetlands that are not filled may be indirectly affected by an altered hydrologic regime, due to the proximity of construction, possibly resulting in a decreased frequency or duration of inundation or soil saturation and potential loss of hydrology necessary to sustain wetland conditions. Indirect impacts could be minimized by maintaining a buffer near adjacent wetlands. Wetlands would likely be impacted by construction at Location B; however, placement of a facility in the northern portion of this location would minimize wetland impacts. Construction at Location C could potentially result in impacts to wetlands, however placement of a facility in the southeastern portion of this location may best avoid direct impacts to wetlands. The hydrologic characteristics of nearby wetlands could be indirectly affected by adjacent construction. Executive Order 11990, ''Protection of Wetlands'', requires federal agencies to minimize the destruction, loss, or degradation of wetlands, and to preserve and enhance the natural and beneficial uses of wetlands. DOE regulations for implementing Executive Order 11990 as well as Executive Order 11988, ''Floodplain Management'', are set forth in 10 CFR Part 1022. Mitigation for unavoidable impacts may be developed in coordination with the appropriate regulatory agencies. Unavoidable impacts to wetlands that are within the jurisdiction of the USACE may require a CWA Section 404 Permit, which would trigger the requirement for a CWA Section 401 Water Quality Certification from the Commonwealth of Kentucky. A mitigation plan may be required prior to the initiation of construction. Cumulative impacts to floodplains and wetlands are anticipated to be negligible to minor under the proposed action, in conjunction with the effects of existing conditions and other activities. Habitat disturbance would involve settings commonly found i

  4. The IAEA Coordinated Research Program on HTGR Reactor Physics, Thermal-hydraulics and Depletion Uncertainty Analysis: Description of the Benchmark Test Cases and Phases

    SciTech Connect (OSTI)

    Frederik Reitsma; Gerhard Strydom; Bismark Tyobeka; Kostadin Ivanov

    2012-10-01

    The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The uncertainties in the HTR analysis tools are today typically assessed with sensitivity analysis and then a few important input uncertainties (typically based on a PIRT process) are varied in the analysis to find a spread in the parameter of importance. However, one wish to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Finally, there is also a renewed focus in supplying reliable covariance data (nuclear data uncertainties) that can then be used in uncertainty methods. Uncertainty and sensitivity studies are therefore becoming an essential component of any significant effort in data and simulation improvement. In order to address uncertainty in analysis and methods in the HTGR community the IAEA launched a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling early in 2012. The project is built on the experience of the OECD/NEA Light Water Reactor (LWR) Uncertainty Analysis in Best-Estimate Modelling (UAM) benchmark activity, but focuses specifically on the peculiarities of HTGR designs and its simulation requirements. Two benchmark problems were defined with the prismatic type design represented by the MHTGR-350 design from General Atomics (GA) while a 250 MW modular pebble bed design, similar to the INET (China) and indirect-cycle PBMR (South Africa) designs are also included. In the paper more detail on the benchmark cases, the different specific phases and tasks and the latest status and plans are presented.

  5. Design and implementation of a CO{sub 2} flood utilizing advanced reservoir characterization and horizontal injection wells in a shallow shelf carbonate approaching waterflood depletion. Technical progress report

    SciTech Connect (OSTI)

    Chimahusky, J.S.

    1996-04-19

    The first objective is to utilize reservoir characterization and advanced technologies to optimize the design of a CO{sub 2} project for the South Cowden Unit (SCU) located in Ector County, Texas. The SCU is a mature, relatively small, shallow shelf carbonate unit nearing waterflood depletion. The second objective is to demonstrate the performance and economic viability of the project in the field. This report includes work on the reservoir characterization and project design objective and the demonstration project objective.

  6. Design and implementation of a CO{sub 2} flood utilizing advanced reservoir characterization and horizontal injection wells in a shallow shelf carbonate approaching waterflood depletion. Quarterly report, July 1 - September 30, 1996

    SciTech Connect (OSTI)

    Chimahusky, J.S.

    1996-10-01

    The first objective is to utilize reservoir characterization and advanced technologies to optimize the design of a carbon dioxide project for the South Cowden Unit (SCU) located in Ector County, Texas. The SCU is a mature, relatively small, shallow shelf carbonate unit nearing waterflood depletion. The second object is to demonstrate the performance and economic viability of the project in the field. The report include work on the reservoir characterization and project design objective and demonstration project objective.

  7. Microsoft Word - FLYSHEET

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

    ... ducting surrounding a uranium hexafluoride (UF 6 ) pipe had instrument lines in it. ... an instruction for uranium hexafluoride pipe removal used for tapping and venting of ...

  8. PADUCAH 2015 YEAR IN REVIEW

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

    Office KEY ACCOMPLISHMENTS Transitioned site cleanup to new deactivation contractor Fluor Federal Services. Completed the demolition of the C-410C-420 UF6 Feed Plant, the...

  9. Data-Driven Mailing Helps Heat Up Untapped Seattle Market

    Broader source: Energy.gov [DOE]

    Abridged transcript of an interview with Community Power Works Project Manager Ruth Bell and Program/System Analyst Vince Schueler of the Washington State University Energy Program.

  10. Mailing Addresses and Information Numbers for Operations, Field...

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

    U.S. Department of Energy Southwestern Power Administration One West Third Street Tulsa, OK 74103-3502 Headquarters, Operations and Maintenance Offices 918-595-6600 U.S. Department...

  11. Customer Feedback during Development of 1998 MECS: Mail/Electronic...

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

    and its composition (by fuel type) in China; - commercial and industrial energy management market data, specifically in software market; - energy consumption in health,...

  12. Minutes from the June 28, 2012 Printing and Mail Teleconference

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

    Scott's contact information is: Shelly Scott shellyscott@ups.com 404 402-9827 (cell) Ms. Scott discussed issues relating to various UPS services available to the department. Next...

  13. Minutes from the March 14, 2013 Printing and Mail Teleconference

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

    content pages 1.36 One copy, b&w only 0.67 250 thermographic process color business cards 1-color - 11.22 2-colors - 21.58 Bleeds - for appearances only; printed image ...

  14. Minutes from the November 17, 2010 Printing and Mail Teleconference

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

    managers have contacted him regarding the business card contract. Mr. Woodruff said business cards can be purchased for as little as 25.00 for 500 face only business cards. ...

  15. Subscribe Today to E-mail Alerts from GTO

    Broader source: Energy.gov [DOE]

    Sign up today to get the most up-to-date information on Geothermal Technologies Office (GTO)-sponsored webinars and funding announcements as they become available—delivered right to your inbox for free.

  16. Fermilab | Press Room | Subscribe to Press Release mailing list

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

    Sheets and Brochures Fermilab Today symmetry Interactions.org Photo and Video Archive Resources for ... Employees Researchers, Postdocs and Graduate Students Job Seekers Neighbors...

  17. Minutes from the November 01, 2012 Printing and Mail Teleconference

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

    to have 3-year plan submissions to headquarters not later than November 9. Future bi-monthly meetings will be scheduled for the second Thursday of odd-numbered months. The...

  18. Minutes from the January 10, 2013 Printing and Mail Teleconference

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

    ... Each entity with an approved logo must establish a process for brand management, including ... by using a common format and layout of text showing the relationship to the parent brand. ...

  19. Partial substitution of Mo{sup 6+} by S{sup 6+} in the fast oxide ion conductor La{sub 2}Mo{sub 2}O{sub 9}: Synthesis, structure and sulfur depletion

    SciTech Connect (OSTI)

    Mhadhbi, Noureddine; Corbel, Gwenaeel; Lacorre, Philippe; Bulou, Alain

    2012-06-15

    Powder-solid state reaction route using La{sub 2}(SO{sub 4}){sub 3} as sulfur source was used to prepare compositions of the solid solution La{sub 2}Mo{sub 2-y}S{sub y}O{sub 9}. Single phases were only obtained in the substitution range extending up to y=0.8 (40 mol% S) at the annealing temperature of 850 Degree-Sign C with regard to the limit of stability of the lanthanum sulphate reactant. Within the synthesis conditions, a stabilization of the high temperature {beta}-form is observed from and above y=0.1 (5 mol% S). Temperature-controlled X-ray diffraction and thermogravimetric analyses have shown that La{sub 2}Mo{sub 2-y}S{sub y}O{sub 9} raw powders undergo thermal decompositions in two steps. Heating above 900 Degree-Sign C, a sulfur depletion to the benefit of molybdenum in La{sub 2}Mo{sub 2-y}S{sub y}O{sub 9} raw powders leads to the formation of La{sub 2}SO{sub 6}. At higher temperature, the exsolved La{sub 2}SO{sub 6} phase then decomposes into La{sub 2}O{sub 3}, which in turn reacts with the sulfur-depleted La{sub 2}Mo{sub 2}O{sub 9} phase to form La{sub 2}MoO{sub 6}. The present study also reveals that depending on the substitution rate y, the sulfur depletion can be induced by ball-milling of raw powders. Along the La{sub 2}Mo{sub 2-y}S{sub y}O{sub 9} series, the isovalent substitution of molybdenum by sulfur tends to restrict in magnitude, or even to suppress above 400 Degree-Sign C, the distortive thermal expansion of the cubic {beta}-type structure, thus strongly decreasing the conductance at high temperature. - Graphical abstract: La{sub 2}O{sub 3}-MoO{sub 3}-'SO{sub 3}' ternary phase diagram showing the exsolution path at low temperature (white arrows) and the total decomposition path at high temperature (black arrows) of {beta}-La{sub 2}Mo{sub 2-y}S{sub y}O{sub 9} raw powders. Highlights: Black-Right-Pointing-Pointer Isovalent substitution of molybdenum by sulfur in La{sub 2}Mo{sub 2}O{sub 9} up to 40 mol%. Black-Right-Pointing-Pointer Stabilization of the {beta}-form for a sulfur content greater than or equal to 5 mol%. Black-Right-Pointing-Pointer Decomposition by sulfur exsolution induced by thermal treatment or ball-milling. Black-Right-Pointing-Pointer Reduction or even cancellation of the distortive thermal expansion above 400 Degree-Sign C. Black-Right-Pointing-Pointer Decrease of conductance at high T involved by the low thermal expansion above 400 Degree-Sign C.

  20. Natural Gas Depleted Fields Storage Capacity

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

    6,917,547 7,074,773 7,104,948 7,038,245 7,074,916 7,085,773 1999-2014 Alaska 83,592 83,592 2013-2014 Alabama 11,000 11,000 13,500 13,500 13,500 13,500 1999-2014 Arkansas 21,760 21,760 21,359 21,853 21,853 21,853 1999-2014 California 513,005 542,511 570,511 592,411 587,711 587,711 1999-2014 Colorado 105,768 105,768 105,858 124,253 122,086 130,186 1999-2014 Illinois 103,606 218,106 220,070 220,070 25,920 25,923 1999-2014 Indiana 32,946 30,003 30,003 30,003 30,003 30,003 1999-2014 Iowa 0 0

  1. Mario Molina, Chlorofluorocarbons (CFCs), and Ozone Depletion

    Office of Scientific and Technical Information (OSTI)

    Prize-winning Research, Massachusetts Institute of Technology (MIT) The Science and Policies of the Ozone Layer -- A Historical Perspective, IDEaS - Nobel Laureate Mario J....

  2. Working Gas Capacity of Depleted Fields

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

    296,096 311,096 335,396 349,296 364,296 364,296 2008-2014 Colorado 48,129 49,119 48,709 60,582 60,582 63,774 2008-2014 Illinois 51,418 87,368 87,368 87,368 11,768 11,768...

  3. Hydrofluoric Acid Corrosion Testing on Unplated and Electroless Gold-Plated Samples

    SciTech Connect (OSTI)

    Osborne, P.E.; Icenhour, A.S.; Del Cul, G.D.

    2000-08-01

    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.

  4. Recovery Act Investment Accelerates Cleanup Work at DOE's Paducah Site |

    Energy Savers [EERE]

    Department of Energy Investment Accelerates Cleanup Work at DOE's Paducah Site Recovery Act Investment Accelerates Cleanup Work at DOE's Paducah Site July 15, 2011 - 12:00pm Addthis UF6 piping deactivation The black inlet hose is attached to a negative air machine that allows Feed Plant cleanup workers to safely deactivate uranium hexafluoride (UF6) piping, seen at right of the lift supporting the crew. UF6 piping deactivation The black inlet hose is attached to a negative air machine that

  5. Reversible Exsolution of Nanometric Fe2O3 Particles in BaFe2-x(PO4)2 (0 ? x ? 2/3):The Logic of Vacancy Ordering in Novel Metal-Depleted Two-Dimensional Lattices

    SciTech Connect (OSTI)

    Alcover, Ignacio Blazquez; David, Rénald; Daviero-Minaud, Sylvie; Filimonov, Dmitry; Huvé, Marielle; Roussel, Pascal; Kabbour, Houria; Mentré, Olivier

    2015-08-12

    We show here that the exsolution of Fe2+ ions out of two-dimensional (2D) honeycomb layers of BaFe2(PO4)2 into iron-deficient BaFe2–x(PO4)2 phases and nanometric ?-Fe2O3 (typically 50 nm diameter at the grain surface) is efficient and reversible until x = 2/3 in mild oxidizing/reducing conditions. It corresponds to the renewable conversion of 12 wt % of the initial mass into iron oxide. After analyzing single crystal X-ray diffraction data of intermediate members x = 2/7, x = 1/3, x = 1/2 and the ultimate Fe-depleted x = 2/3 term, we then observed a systematic full ordering between Fe ions and vacancies (VFe) that denote unprecedented easy in-plane metal diffusion driven by the Fe2+/Fe3+ redox. Besides the discovery of a diversity of original depleted triangular ?{Fe2/3+2–xO6} topologies, we propose a unified model correlating the x Fe-removal and the experimental Fe/VFe ordering into periodic one-dimensional motifs paving the layers, gaining insights into predictive crystahemistry of complex low dimensional oxides. When we increased the x values it led to a progressive change of the materials from 2D ferromagnets (Fe2+) to 2D ferrimagnets (Fe2/3+) to antiferromagnets for x = 2/3 (Fe3+).

  6. Blog | Department of Energy

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

    30, 2015 An excavator with a shear attachment performs "top-down" shearing during final stages of the demolition of the C-410C-420 UF6 Feed Plant Complex in June. Demolition...

  7. Microsoft PowerPoint - 1_JESSICA_WHITE-HORTON_NMMSS_2014_JWH...

    National Nuclear Security Administration (NNSA)

    F with 96 hrs at -60 o F and 250 o F - Indirect lightning effects - Withstand 50 ppm hydrogen fluoride at 90 o F and 90% humidity for 96 hrs - Withstand shock of 1.2 m UF 6...

  8. Cleanup Contractor Achieves 'Elite' Nuclear Material Accountability...

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

    ... They are being stored at the site for future recovery of UF6 material during plant decommissioning when systems are in place to remove the material safely and economically. LATA ...

  9. EA-1290: Disposition of Russian Federation Titled Natural Uranium

    Broader source: Energy.gov [DOE]

    This EA evaluates the potential environmental impacts of a proposal to transport up to an average of 9,000 metric tons per year of natural uranium as uranium hexafluoride (UF6) from the United...

  10. 150122 Traxys DOE RFI Comments

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

    utility customers under forward delivery contracts and NOT in the spot market. 4. Traxys' marketing strategy for UF6 acquired from FBP has been to sell the material in a market ...

  11. Market review - market values summary/February market review/current market data

    SciTech Connect (OSTI)

    1996-03-01

    This article is the February 1996 uranium market report. As reflected by the rising demand and decreasing supply of uranium, prices for UF6 and U3O8 increased. Separation services and conversion services prices remained constant. Data is presented for the recent trades, blocks or uranium for sale or loan, inquiries to purchase or borrow uranium, SWUs available and inquiries to purchase SWUs, and market values of U3O8 and UF6 expressed in selected currencies.

  12. NOTICE TO SUPPLIERS Fraudulent Quote Requests/Purchase Order E-Mail Activity

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

    * The email message may be poorly written, with misspellings and awkward sentence structure. * The sender's email address is not the same as CNS standard email address domain. The email address domain for Y-12: xxx@y12.doe.gov, for Pantex: xxx@pantex.com. Email from either site may also be in this form: xxx@cns.doe.gov. * The message and purchase order requests shipment/delivery of products to non-CNS facilities. * The message will include an attachment that is designed to look like a purchase

  13. NOTICE TO SUPPLIERS Fraudulent Quote Requests/Purchase Order E-Mail Activity

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

     The email message may be poorly written, with misspellings and awkward sentence structure.  The senders email address is not the same as CNS standard email address domain. The email address domain for Y-12: xxx@y12.doe.gov, for Pantex: xxx@pantex.com.  The message and purchase order requests shipment/delivery of products to non-CNS facilities.  The message will include an attachment that is designed to look like a purchase order, and includes a logo or other graphic, and a signature

  14. Cyber in the Cloud -- Lessons Learned from INL's Cloud E-Mail Acquisition

    SciTech Connect (OSTI)

    Troy Hiltbrand; Daniel Jones

    2012-12-01

    As we look at the cyber security ecosystem, are we planning to fight the battle as we did yesterday, with firewalls and intrusion detection systems (IDS), or are we sensing a change in how security is evolving and planning accordingly? With the technology enablement and possible financial benefits of cloud computing, the traditional tools for establishing and maintaining our cyber security ecosystems are being dramatically altered.

  15. C:MydocsMYDOCSHATTIERECS97recsForms97Mail.PDF

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

    The survey is voluntary and is authorized under the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. Information about specific households will be kept ...

  16. Site Office Contracting Officer E-mail address Ames Site Office...

    National Nuclear Security Administration (NNSA)

    Office Darby Dieterich Dieterich@nv.doe.gov Oak Ridge Site Office Lisa Carter Carterlb@oro.doe.gov Pacific Northwest Site Office Lance Vickerman Robert McLeod...

  17. ORISE: Contact information for REAC/TS - phone numbers, e-mail

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

    Contact Us Radiation Emergency Assistance CenterTraining Site staff contact information Emergency Number 865.576.1005 (Ask for REACTS) Nicholas Dainiak, M.D., FACP Medical and...

  18. E-Alerts: Combustion, engines, and propellants (reciprocation and rotating combustion engines). E-mail newsletter

    SciTech Connect (OSTI)

    1999-04-01

    Design, performance, and testing of reciprocating and rotating engines of various configurations for all types of propulsion. Includes internal and external combustion engines; engine exhaust systems; engine air systems components; engine structures; stirling and diesel engines.

  19. E-Alerts: Energy (engine studies (energy related)). E-mail newsletter

    SciTech Connect (OSTI)

    1999-04-01

    Operation and design of engines when related to energy conservation and energy use. Covers turbine, rotary, and reciprocating engines.

  20. C:MydocsMYDOCSHATTIERECS97recsForms97Mail.PDF

    Gasoline and Diesel Fuel Update (EIA)

    B (1997) Form Approval: OMB No.: 1905-0092 Nationwide Survey on Household Energy Use Expires: March 31, 2000 The numbers in parentheses are for office use only. This survey is being conducted for the U.S. Department of Energy by Response Analysis Corporation. The survey is voluntary and is authorized under the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. Information about specific households will be kept strictly confidential. The data will be summarized within

  1. By E-Mail Daniel Cohen Assistant General Counsel for Legislation...

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

    Order), DOE published its preliminary plan for retrospective analysis of existing rules. DOE seeks comment on its preliminary plan so that it can consider and incorporate...

  2. E-Alerts: Environmental pollution and control (solid waste pollution and control). E-mail newsletter

    SciTech Connect (OSTI)

    1999-04-01

    The paper discusses pollution by solid wastes including garbage, scrap, junked automobiles, spoil, sludge, containers; Disposal methods such as composts or land application, injection wells, incineration, sanitary landfills; Mining wastes; Processing for separation and materials recovery; Solid waste utilization; Recycling; Biological and ecological effects; Superfund (Records of Decision, etc.); SITE technology; Laws, legislation, and regulations; Public administration; Economics; Land use. The discussion includes disposal of concentrated or pure liquids such as brines, oils, chemicals, and hazardous materials.

  3. Supercell Depletion Studies for Prismatic High Temperature Reactors

    SciTech Connect (OSTI)

    J. Ortensi

    2012-10-01

    The traditional two-step method of analysis is not accurate enough to represent the neutronic effects present in the prismatic high temperature reactor concept. The long range coupling of the various regions in high temperature reactors poses a set of challenges that are not seen in either LWRs or fast reactors. Unlike LWRs, which exhibit large, localized effects, the dominant effects in PMRs are, for the most part, distributed over larger regions, but with lower magnitude. The 1-D in-line treatment currently used in pebble bed reactor analysis is not sufficient because of the 2-D nature of the prismatic blocks. Considerable challenges exist in the modeling of blocks in the vicinity of reflectors, which, for current small modular reactor designs with thin annular cores, include the majority of the blocks. Additional challenges involve the treatment of burnable poisons, operational and shutdown control rods. The use of a large domain for cross section preparation provides a better representation of the neutron spectrum, enables the proper modeling of BPs and CRs, allows the calculation of generalized equivalence theory parameters, and generates a relative power distribution that can be used in compact power reconstruction. The purpose of this paper is to quantify the effects of the reflector, burnable poison, and operational control rods on an LEU design and to delineate an analysis approach for the Idaho National Laboratory. This work concludes that the use of supercells should capture these long-range effects in the preparation of cross sections and along with a set of triangular meshes to treat BPs, and CRs a high fidelity neutronics computation is attainable.

  4. Number of Existing Natural Gas Depleted Fields Storage

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

    331 331 329 330 332 333 1999-2014 Alaska 5 5 2013-2014 Alabama 1 1 1 1 1 1 1999-2014 Arkansas 2 2 2 2 2 2 1999-2014 California 13 13 13 14 13 13 1999-2014 Colorado 9 9 9 10 10 10 1999-2014 Illinois 10 11 11 11 9 9 1999-2014 Indiana 10 9 9 10 10 10 1999-2014 Kansas 18 18 18 18 18 17 1999-2014 Kentucky 20 20 20 20 20 21 1999-2014 Louisiana 8 8 8 7 8 8 1999-2014 Maryland 1 1 1 1 1 1 1999-2014 Michigan 43 43 43 43 43 43 1999-2014 Mississippi 6 6 6 6 6 6 1999-2014 Montana 5 5 5 5 5 5 1999-2014

  5. Enterprise Assessments Targeted Review of the Paducah Depleted...

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

    ... two or more firefighters enter a building, at least two ... angle rescue, demolition search and rescue). (See ... This process does not evaluate risk in terms of fire ...

  6. Depleted Uranium Hexafluoride (DUF6) Fully Operational at the...

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

    ... Because much of the equipment had not been operated since installation, we expected a lot of gremlins and breakdowns, and in fact, we got them." The DUF6 Project paused briefly ...

  7. Conversion of depleted uranium hexafluoride to a solid uranium compound

    DOE Patents [OSTI]

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

    2001-01-01

    A process for converting UF.sub.6 to a solid uranium compound such as UO.sub.2 and CaF. The UF.sub.6 vapor form is contacted with an aqueous solution of NH.sub.4 OH at a pH greater than 7 to precipitate at least some solid uranium values as a solid leaving an aqueous solution containing NH.sub.4 OH and NH.sub.4 F and remaining uranium values. The solid uranium values are separated from the aqueous solution of NH.sub.4 OH and NH.sub.4 F and remaining uranium values which is then diluted with additional water precipitating more uranium values as a solid leaving trace quantities of uranium in a dilute aqueous solution. The dilute aqueous solution is contacted with an ion-exchange resin to remove substantially all the uranium values from the dilute aqueous solution. The dilute solution being contacted with Ca(OH).sub.2 to precipitate CaF.sub.2 leaving dilute NH.sub.4 OH.

  8. Optimization to reduce fuel consumption in charge depleting mode

    DOE Patents [OSTI]

    Roos, Bryan Nathaniel; Martini, Ryan D.

    2014-08-26

    A powertrain includes an internal combustion engine, a motor utilizing electrical energy from an energy storage device, and a plug-in connection. A Method for controlling the powertrain includes monitoring a fuel cut mode, ceasing a fuel flow to the engine based upon the fuel cut mode, and through a period of operation including acceleration of the powertrain, providing an entirety of propelling torque to the powertrain with the electrical energy from the energy storage device based upon the fuel cut mode.

  9. Application of thermal depletion model to geothermal reservoirs...

    Open Energy Info (EERE)

    method are presented, and possible application to the Salton Sea Geothermal Field, the Raft River System, and to reinjection of supersaturated fluids is discussed. Authors...

  10. March market review. [Spot market prices for uranium (1993)

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The spot market price for uranium in unrestricted markets weakened further during March, and at month end, the NUEXCO Exchange Value had fallen $0.15, to $7.45 per pound U3O8. The Restricted American Market Penalty (RAMP) for concentrates increased $0.15, to $2.55 per pound U3O8. Ample UF6 supplies and limited demand led to a $0.50 decrease in the UF6 Value, to $25.00 per kgU as UF6, while the RAMP for UF6 increased $0.75, to $5.25 per kgU. Nine near-term uranium transactions were reported, totalling almost 3.3 million pounds equivalent U3O8. This is the largest monthly spot market volume since October 1992, and is double the volume reported in January and February. The March 31 Conversion Value was $4.25 per kgU as UF6. Beginning with the March 31 Value, NUEXCO now reports its Conversion Value in US dollars per kilogram of uranium (US$/kgU), reflecting current industry practice. The March loan market was inactive with no transactions reported. The Loan Rate remained unchanged at 3.0 percent per annum. Low demand and increased competition among sellers led to a one-dollar decrease in the SWU Value, to $65 per SWU, and the RAMP for SWU declined one dollar, to $9 per SWU.

  11. Market values summary/October market review/current market data

    SciTech Connect (OSTI)

    1994-11-01

    This article is the October uranium market summary. During this period, volume increased to 2.2 Mlb U3O8 on the spot concentrates market. The unrestricted and restricted exchange values remained steady at $7.00 and $9.05 per pound U3O8 respectively. There were two UF6 deals during this period, and with supply more than adequate to meet the demand, the restricted UF6 price remained unchanged at $29.00 per kgU as UF6. The unrestricted value increased slightly to $24.50. The conversion value was unchanged, and the enrichment services market/prices weakened. Both active supply and demand decreased during this period.

  12. Market values summary/April market review/current market data

    SciTech Connect (OSTI)

    1994-05-01

    This article is the April 1994 uranium market summary. The near-term market was slow, with three near-term deals for concentrates and none for UF6. This was reflected in the decline of the concentrates restricted value $9.30 per pound U3O8 and the UF6 restricted value to $29.75 per kgU as UF6. In each market, the unrestricted value remained unchanged at $7.00 and $24.50 due to the lack of trades in the unrestricted market. Transaction values in both the restricted and unrestricted market were constant at $9.45 and $7.05 per pound U3O8. The restricted SWU value rose a dollar to $88 per SWU, and the unrestricted SWU value remained steady at $67 per SWU. Active demand continued to decrease, while active supply increased.

  13. Market values summary/March market review/current market data

    SciTech Connect (OSTI)

    1995-04-01

    This article is the March 1995 uranium market summary. There were 14 near-term deals is natural uranium market for a total of 5.2 Mlb. The restricted exchange value moved upward to $11.75 per pound U3O8, and the unrestricted value rose to $7.35. The UF6 market was quite active, with 8 deals and with restricted and unrestricted prices for UF6 both up ($34.75 and $22.50 per kgU as UF6 respectively). The restricted and unrestricted transaction values also rose to $10.05 and $7.25 respectively. Enrichment services followed the overall trend, with increases to $92 and $78 per SWU. Active uranium supply dropped, as did active demand.

  14. Development of a model of an x-ray tube transmission source

    SciTech Connect (OSTI)

    Goda, Joetta M; Ianakiev, Kiril D; Moss, Cal E

    2009-01-01

    In support of the development of an x-ray tube based source for transmission measurements of UF6 gas, we have developed a one-dimensional, spreadsheet-based model of the source. Starting with the spectrum produced by an x-ray tube we apply the linear attenuation coefficients for various notch filters, the aluminum pipe, and UF6 gas. This model allows calculation of the transmitted spectrum based on the type of filter, the thickness of the filter, the x-ray tube high voltage, the Al pipe thickness, and the UF6 gas pressure. The sensitivity of the magnitude of the transmission peak produced by the notch filter to any of these variables can be explored quickly and easily to narrow the choices for experimental measurements. To validate the spreadsheet based model, comparisons have been made to various experimental data.

  15. Market values summary/April market review/current market data

    SciTech Connect (OSTI)

    1995-05-01

    This article is the April 1995 uranium market summary. Overall market activity during this period was low, with five deals in the concentrates market, two deals in the long-term natural uranium market, and three deals in the spot enrichment market. There were no spot trades in the UF6 or conversion market. The restricted and unrestricted exchange values were $11.60 and $7.35 respectively. The restricted and unrestricted UF6 values were $36.00 and $25.50, and the restricted and unrestricted transaction values were $10.30 and $7.25. Active uranium supply rose, and active demand fell.

  16. An Optically Stimulated Luminescence Uranium Enrichment Monitor

    SciTech Connect (OSTI)

    Miller, Steven D.; Tanner, Jennifer E.; Simmons, Kevin L.; Conrady, Matthew M.; Benz, Jacob M.; Greenfield, Bryce A.

    2010-08-11

    The Pacific Northwest National Laboratory (PNNL) has pioneered the use of Optically Stimulated Luminescence (OSL) technology for use in personnel dosimetry and high dose radiation processing dosimetry. PNNL has developed and patented an alumina-based OSL dosimeter that is being used by the majority of medical X-ray and imaging technicians worldwide. PNNL has conceived of using OSL technology to passively measure the level of UF6 enrichment by attaching the prototype OSL monitor to pipes containing UF6 gas within an enrichment facility. The prototype OSL UF6 monitor utilizes a two-element approach with the first element open and unfiltered to measure both the low energy and high energy gammas from the UF6, while the second element utilizes a 3-mm thick tungsten filter to eliminate the low energy gammas and pass only the high energy gammas from the UF6. By placing a control monitor in the room away from the UF6 pipes and other ionizing radiation sources, the control readings can be subtracted from the UF6 pipe monitor measurements. The ratio of the shielded to the unshielded net measurements provides a means to estimate the level of uranium enrichment. PNNL has replaced the commercially available MicroStar alumina-based dosimeter elements with a composite of polyethylene plastic, high-Z glass powder, and BaFBr:Eu OSL phosphor powder at various concentrations. The high-Z glass was added in an attempt to raise the average “Z” of the composite dosimeter and increase the response. Additionally, since BaFBr:Eu OSL phosphor is optimally excited and emits light at different wavelengths compared to alumina, the commercially available MicroStar reader was modified for reading BaFBr:Eu in a parallel effort to increase reader sensitivity. PNNL will present the design and performance of our novel OSL uranium enrichment monitor based on a combination of laboratory and UF6 test loop measurements. PNNL will also report on the optimization effort to achieve the highest possible performance from both the OSL enrichment monitor and the new custom OSL reader modified for this application. This project has been supported by the US Department of Energy’s National Nuclear Security Administration’s Office of Dismantlement and Transparency (DOE/NNSA/NA-241).

  17. Market review - Market values summary/October market review/current market data

    SciTech Connect (OSTI)

    1995-11-01

    This article is the October 1995 uranium market summary. In this reporting period, there were four transactions in the natural uranium market, no activity in the spot UF6 market, no activity in the spot conversion market, and only a single activity in the enrichment services market. Spot uranium volume dropped sharply, and active uranium supply rose. The rise in demand, however, more than offset this increase. Unrestricted exchange prices rose slightly, as did the unrestricted UF6 value. All other prices remained steady.

  18. Market values summary/October market review/current market data

    SciTech Connect (OSTI)

    1993-11-01

    This article is the October 1993 uranium market summary. In spite of the substantial quantity of material that moved through the unrestricted market during this period, the unrestricted exchange value remained constant at $6.90 per pound U3O8, and the unrestricted value dipped to $10.15. There were four deals in the concentrates market during this period. Both the restricted and the unrestricted UF6 values remained constant at $31.75 and $24.75 per kgU as UF6 respectively, as did the restricted and unrestricted SWU values ($82 and $68 respectively). Active supply increased, while active demand decreased.

  19. Market values summary/February market overview/current market data

    SciTech Connect (OSTI)

    1994-03-01

    This article is the February 1994 uranium market summary. During this reporting period, there were six deals in the natural uranium market involving 2.5 Mlb equivalent U3O8. The restricted exchange value eased to $9.45 per pound U3O8, and the unrestricted value remained unchanged at $7.00. There two deals for uranium as UF6, and the restricted UF6 value decreased to $30.00 per kgU as UF6. The unrestricted UF6 value was unchanged at $24.50. There were no long-term deals during this period, but several utilities were evaluating offers for over 10 Mlb equivalent U3O8 for delivery through 2005. The unrestricted transaction value remained steady at $7.15 per pound U3O8, while the restricted value dropped slightly to $9.75. The unrestricted SWU value was unchanged at $68 per SWU, but the restricted value once again increased by a dollar to $86. Active uranium supply decreased slightly, while active demand increased considerably.

  20. Market values summary/May market review/current market data

    SciTech Connect (OSTI)

    1994-06-01

    This article is the May 1994 uranium market survey. In the spot concentrates market, there was only one new deal, and as a result, the restricted exchange value eased to $9.25 per pound U3O8. The unrestricted exchange value remained constant at $7.00. There were two deals in the UF6 spot market, and the restricted UF6 value decreased to $29.40 per kgU as UF6. The unrestricted UF6 value was unchanged. There were two deals in the long-term marketplace. The restricted transaction value declined to $9.40 per pound U3O8, and the unrestricted transaction value remained fixed at $7.05. There were three deals in the enrichment services market, and the restricted SWU value dropped to $87 per SWU, while the unrestricted SWU value remained constant at $67. Active uranium supply decreased this reporting period, while active demand increased. Supply continued to overwhelm demand, however.

  1. Microsoft Word - NEGTN02-#188646-v22B-INVENTORY_PLAN_UNCLASSIFIED.DOC

    Office of Environmental Management (EM)

    Department of Energy Excess Uranium Inventory Management Plan December 16, 2008 Office of Nuclear Energy 2008 Table of Contents Executive Summary................................................................................................ES-1 Excess Uranium Inventories..........................................................................................1 Unallocated U.S. HEU.........................................................................................1 U.S.-Origin NU as UF 6

  2. Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Haghighi, M. H.; Szozda, R. M.; Jugan, M. R.

    2002-02-26

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR), south of the Oak Ridge National Laboratory (ORNL) main plant across Haw Ridge in Melton Valley. The MSRE was run by ORNL to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503 (Figure 1). The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed t o cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. As a result of the S&M program, it was discovered in 1994 that gaseous uranium (233U/232U) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 was generated when radiolysis of the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine.Some of the free fluorine combined with uranium fluorides (UF4) in the salt to form UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE.

  3. DOE Announces Transfer of Depleted Uranium to Advance the U.S...

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

    A more detailed description of the project is available HERE. The project will ensure a supply of U.S.-origin unobligated uranium to support the NNSA tritium production for up to ...

  4. Observation of stratospheric trace gases related to ozone depletion in the Antarctic spring

    SciTech Connect (OSTI)

    De Zafra, R.L.; Parrish, A.; Solomon, P.; Barrett, J.W.; Connor, B.; Jaramillo, M. )

    1987-01-01

    During the first National Ozone Expedition (NOZE I), which ran from 21 August to early November 1986 at McMurdo Station, the authors made frequent measurements of chlorine monoxide (CIO), ozone (O{sub 3}), nitrous oxide (N{sub 2}O), and occasional measurements of hydrogen cyanide. Observations were made with a ground-based millimeters wave spectrometer capable of detecting and measuring the pressure broadened rotational emission lines of these molecules in the 260-280 gigahertz frequency range. The spectral bandpass and resolution of the instrument is sufficient to recover altitude distributions over a range of approximately 20-55 kilometers and to detect emission from as low as approximately 13-15 kilometers. Results are given and discussed on the levels of chlorine monoxide, nitrous oxide, and ozone found.

  5. Running into an out of oil: Scenarios of global oil use and resource depletion to 2050

    SciTech Connect (OSTI)

    Greene, David L.; Hopson, Janet L.; Li, Jia

    2002-07-23

    Is a transition from conventional oil imminent? Is it likely to lock the world into a high-carbon energy future? This report attempts to shed some light on these questions.

  6. Depletion Analysis of Modular High Temperature Gas-cooled Reactor Loaded with LEU/Thorium Fuel

    SciTech Connect (OSTI)

    Sonat Sen; Gilles Youinou

    2013-02-01

    Thorium based fuel has been considered as an option to uranium-based fuel, based on considerations of resource utilization (Thorium is more widely available when compared to Uranium). The fertile isotope of Thorium (Th-232) can be converted to fissile isotope U-233 by neutron capture during the operation of a suitable nuclear reactor such as High Temperature Gas-cooled Reactor (HTGR). However, the fertile Thorium needs a fissile supporter to start and maintain the conversion process such as U-235 or Pu-239. This report presents the results of a study that analyzed the thorium utilization in a prismatic HTGR, namely Modular High Temperature Gas-Cooled Reactor (MHTGR) that was designed by General Atomics (GA). The collected for the modeling of this design come from Chapter 4 of MHTGR Preliminary Safety Information Document that GA sent to Department of Energy (DOE) on 1995. Both full core and unit cell models were used to perform this analysis using SCALE 6.1 and Serpent 1.1.18. Because of the long mean free paths (and migration lengths) of neutrons in HTRs, using a unit cell to represent a whole core can be non-trivial. The sizes of these cells were set to match the spectral index between unit cell and full core domains. It was found that for the purposes of this study an adjusted unit cell model is adequate. Discharge isotopics and one-group cross-sections were delivered to the transmutation analysis team. This report provides documentation for these calculations

  7. Improved Spatial Resolution in Thick, Fully-Depleted CCDs withEnhanced...

    Office of Scientific and Technical Information (OSTI)

    Christopher J. ; Holland, Stephen E. ; Karcher, Armin ; Kolbe,William F. ; Lorenzon, Wolfgang ; Roe, Natalie A. Publication Date: 2006-03-09 OSTI Identifier: 932675 Report...

  8. DOE Issues Final Request for Proposal for the Operation of Depleted...

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

    the DUF6 from the inventory at Paducah and Portsmouth to uranium oxide at design throughput of the conversion facilities, reusing andor transporting and disposing of the DUF6...

  9. Venezuelan equine encephalitis virus entry mechanism requires late endosome formation and resists cell membrane cholesterol depletion

    SciTech Connect (OSTI)

    Kolokoltsov, Andrey A.; Fleming, Elisa H.; Davey, Robert A. . E-mail: radavey@utmb.edu

    2006-04-10

    Virus envelope proteins determine receptor utilization and host range. The choice of receptor not only permits specific targeting of cells that express it, but also directs the virus into specific endosomal trafficking pathways. Disrupting trafficking can result in loss of virus infectivity due to redirection of virions to non-productive pathways. Identification of the pathway or pathways used by a virus is, thus, important in understanding virus pathogenesis mechanisms and for developing new treatment strategies. Most of our understanding of alphavirus entry has focused on the Old World alphaviruses, such as Sindbis and Semliki Forest virus. In comparison, very little is known about the entry route taken by more pathogenic New World alphaviruses. Here, we use a novel contents mixing assay to identify the cellular requirements for entry of a New World alphavirus, Venezuelan equine encephalitis virus (VEEV). Expression of dominant negative forms of key endosomal trafficking genes shows that VEEV must access clathrin-dependent endocytic vesicles for membrane fusion to occur. Unexpectedly, the exit point is different from Old World alphaviruses that leave from early endosomes. Instead, VEEV also requires functional late endosomes. Furthermore, unlike the Old World viruses, VEEV entry is insensitive to cholesterol sequestration from cell membranes and may reflect a need to access an endocytic compartment that lacks cholesterol. This indicates fundamental differences in the entry route taken by VEEV compared to Old World alphaviruses.

  10. In Situ NDA Conformation Measurements Performed at Auxiliary Charcoal Bed and Other Main Charcoal Beds After Uranium Removal from Molten Salt Reactor Experiment ACB at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Haghighi, M. H.; Kring, C. T.; McGehee, J. T.; Jugan, M. R.; Chapman, J.; Meyer, K. E.

    2002-02-26

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR). The MSRE was run by Oak Ridge National Laboratory (ORNL) to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503. The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed to cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. Beginning in 1987, it was discovered that gaseous uranium (U-233/U-232) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 had been generated when radiolysis in the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine. Some of the free fluorine combined with uranium fluorides (UF4) in the salt to produce UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE. One of the systems that UF6 migrated into due to this process was the offgas system which is vented to the MSRE main charcoal beds and MSRE auxiliary charcoal bed (ACB). Recently, the majority of the uranium laden-charcoal material residing within the ACB was safely and successfully removed using the uranium deposit removal system and equipment. After removal a series of NDA measurements was performed to determine the amount of uranium material remaining in the ACB, the amount of uranium material removed from the ACB, and the amount of uranium material remaining in the uranium removal equipment due to removal activities.

  11. Metal-Air Electric Vehicle Battery: Sustainable, High-Energy Density, Low-Cost Electrochemical Energy Storage – Metal-Air Ionic Liquid (MAIL) Batteries

    SciTech Connect (OSTI)

    2009-12-21

    Broad Funding Opportunity Announcement Project: ASU is developing a new class of metal-air batteries. Metal-air batteries are promising for future generations of EVs because they use oxygen from the air as one of the battery’s main reactants, reducing the weight of the battery and freeing up more space to devote to energy storage than Li-Ion batteries. ASU technology uses Zinc as the active metal in the battery because it is more abundant and affordable than imported lithium. Metal-air batteries have long been considered impractical for EV applications because the water-based electrolytes inside would decompose the battery interior after just a few uses. Overcoming this traditional limitation, ASU’s new battery system could be both cheaper and safer than today’s Li-Ion batteries, store from 4-5 times more energy, and be recharged over 2,500 times.

  12. Natural uranium/conversion services/enrichment services

    SciTech Connect (OSTI)

    1993-12-31

    This article is the 1993 uranium market summary. During this reporting period, there were 50 deals in the concentrates market, 26 deals in the UF6 market, and 14 deals for enrichment services. In the concentrates market, the restricted value closed $0.15 higher at $9.85, and the unrestricted value closed down $0.65 at $7.00. In the UF6 market, restricted prices fluctuated and closed higher at $31.00, and unrestricted prices closed at their initial value of $24.75. The restricted transaction value closed at $10.25 and the unrestricted value closed at $7.15. In the enrichment services market, the restricted value moved steadily higher to close at $84.00 per SWU, and the unrestricted value closed at its initial value of $68.00 per SWU.

  13. Applications of Nuclear Resonance Fluorescence

    SciTech Connect (OSTI)

    Warren, Glen A.; Detwiler, Rebecca S.; Peplowski, Patrick N.

    2010-11-11

    Nuclear Resonance Fluorescence (NRF) has the potential of addressing a wide variety of applications, which require isotopic and/or elemental information about a sample. We have investigated a variety of non-proliferation applications that may be addressed by NRF. From these applications, we have selected two, measuring uranium enrichment in UF6 cylinders and material verification in dismantlement, to investigate in more detail. Analytical models have been developed to evaluate these applications, and test measurements have been conducted to validate those models. We found that it is unlikely with current technology to address the requirements for UF6 cylinder enrichment measurements. In contrast, NRF is a very promising approach for material verification for dismantlement.

  14. Market values summary/February market review/current market data

    SciTech Connect (OSTI)

    1995-03-01

    This article is the February 1995 uranium market summary. In the natural uranium and concentrates market, there were 10 deals, and the restricted value moved upward to $10.40. The unrestricted value remained fixed at $7.25. In the UF6 market, there were two deals in the restricted market, and the restricted value rose to $32.75 per kgU as UF6. The unrestricted value remained at $25.00. The restricted transaction value rose to $9.75, and the unrestricted value rose to $7.15. In the enrichment services market, there were three deals. The restricted SWU value rose to $90 per SWU, and the unrestricted value rose to $75 per SWU. Active uranium supply and active uranium demand dropped this reporting period.

  15. Market values summary/August market review/current market data

    SciTech Connect (OSTI)

    1994-09-01

    This article is the August 1994 uranium market summary. There were 16 deals in the natural uranium market. The restricted exchange value dropped slightly to $9.10 per pound U3O8, while the unrestricted exchange value remained steady at $7.10. Similarly, the restricted UF6 value eased to $29.30 kgU as UF6, and the unrestricted value remained constant at $24.50. The restricted transaction value declined slightly to $9.15 per pound U3O8, while the unrestricted value increased to $7.15. Both active supply and demand increased by a comparable amount. The unrestricted SWU value was unchanged, but the restricted value decreased by a dollar to $86 per SWU.

  16. Market values summary/December market review/current market data

    SciTech Connect (OSTI)

    1994-01-01

    This article is the December 1993 uranium market summary. During this period, there were six deals in the restricted concentrates market and none in the unrestricted market. The restricted value dropped slightly to $9.85 per pound U3O8, while the unrestricted market rose slightly to $7.00. The UF6 market was also slow, with a slight decrease in the restricted UF6 value to $31.00 and no change in the unrestricted value ($24.00). The unrestricted transaction value was $7.15 per pound U3O8, and the restricted value was $10.25. In the enrichment services market, the unrestricted SWU value remained fixed at $68.00 per SWU, while the unrestricted value increased by a dollar to $84.00 per SWU. Active uranium supply decreased, while active demand increased.

  17. Market values summary/March market review/current market data

    SciTech Connect (OSTI)

    1994-04-01

    This article is the March 1993 uranium market summary. In the natural uranium and concentrates market, there were eight transactions. Both the restricted and unrestricted values were unchanged at $9.45 and $7.00 per pound of U3O8 respectively. In the UF6 market, there were three deals. Both restricted and unrestricted values were also unchanged at $30.00 and $24.50 per kgU as UF6 respectively. The restricted transaction value dropped slightly to $9.45, and the unrestricted value dropped to $7.05. In the enrichment services market, there were six deals reported, with the restricted SWU value rising to $87.00 and the unrestricted SWU value dropping to $67.00. Active uranium demand decreased considerably, while active supply increased.

  18. 2014 Uranium Marketing Annual Report

    Gasoline and Diesel Fuel Update (EIA)

    U.S. Energy Information Administration / 2014 Uranium Marketing Annual Report 2014 Uranium Marketing Annual Report Release Date: May 13, 2015 Next Release Date: May 2016 thousand pounds U 3 O 8 equivalent 2010 2011 2012 2013 P2014 Owners and operators of U.S. civilian nuclear power reactors inventories 86,527 89,835 97,647 113,077 116,047 Uranium concentrate (U 3 O 8 ) 13,076 14,718 15,963 18,131 20,501 Natural UF 6 35,767 35,883 29,084 38,332 40,972 Enriched UF 6 25,392 19,596 38,428 40,841

  19. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Silverstein, Eva (1) Smith, Kendrick M., E-mail: siavoshrezvan@gmail.com, E-mail: ... Mirbabayi, Mehrdad ; Senatore, Leonardo ; Smith, Kendrick M., E-mail: ...

  20. Slowed demand ushers in summer season

    SciTech Connect (OSTI)

    1996-07-01

    This article is the June 1996 market summary in uranium market. During this reporting period, there were six deals in the U3O8 spot market and three long-term deals for U3O8. There were four deals for UF6 conversion, and the spot market for uranium separation services had no transactions. This was little change from the previous month`s activities, and this slowness was reflected in the price trends of little or no increase.

  1. April market review. [Spot market prices for uranium (1993)

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    The spot market price for uranium outside the USA weakened further during April, and at month end, the NUEXCO Exchange Value had fallen $0.35, to $7.10 per pound U3O8. This is the lowest Exchange Value observed in nearly twenty years, comparable to Values recorded during the low price levels of the early 1970s. The Restricted American Market Penalty (RAMP) for concentrates increased $0.40, to $2.95 per pound U3O8. Transactions for significant quantities of uranium concentrates that are both deliverable in and intended for consumption in the USA could have been concluded on April 30 at $10.05 per pound U3O8, up $0.05 from the sum of corresponding March Values. Four near-term concentrates transactions were reported, totalling nearly 1.5 million pounds equivalent U3O8. One long-term sale was reported. The UF6 Value also declined, as increased competition among sellers led to a $0.50 decrease, to $24.50 per kgU as UF6. However, the RAMP for UF6 increased $0.65, to $5.90 per kgU as UF6, reflecting an effective US market level of $30.40 per kgU. Two near term transactions were reported totalling approximately 1.1 million pounds equivalent U3O8. In total, eight uranium transactions totalling 28 million pounds equivalent U3O8 were reported, which is about average for April market activity.

  2. Via Electronic Submission

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

    January 22, 2015 Mr. David Henderson U.S. Department of Energy Office of Nuclear Energy Mailstop NE-52 19901 Germantown Road Germantown, Maryland 20874-1290 Re: Excess Uranium Management: Effects of DOE Transfers of Excess Uranium on Domestic Uranium Mining, Conversion and Enrichment Industries: Request for Information Dear Mr. Henderson: Fluor-B&W Portsmouth LLC is currently the contractor at the Portsmouth Ohio site who receives transfers of Departement of Energy (DOE) owned natural UF6 as

  3. Enforcement Letter, NEL-2011-01 - March 31, 2011 | Department of Energy

    Office of Environmental Management (EM)

    1 - March 31, 2011 Enforcement Letter, NEL-2011-01 - March 31, 2011 March 31, 2011 Enforcement Letter issued to LATA Environmental Services of Kentucky, LLC, regarding work control issues that resulted in the release of uranium hexafluoride (UF6) at the Paducah Gaseous Diffusion Plant On March 31, 2011, the U.S. Department of Energy (DOE) Office of Health, Safety and Security's Office of Enforcement issued an Enforcement Letter (NEL-2011-01) to LATA Environmental Services of Kentucky, LLC

  4. FBP-DOE PPPO 17Aug2012

    Office of Environmental Management (EM)

    FBP Update Impacts Of DOE Uranium Barter Program On U.S. Domestic Industry Fluor-B&W Portsmouth LLC April 1, 2014 Frank Hahne FBP advocates full appropriation funding for Portsmouth D&D; but continued DOE UF6 uranium barter sales if appropriations are not forthcoming - In FBP's analysis based on objective measures to date conclude that the U.S. uranium mining, conversion and enrichment industries have not experienced an adverse material impact from DOE's Uranium Barter Program...... *

  5. Comment to NOI re Retrospective Risk Pooling Program For Suppliers |

    Office of Environmental Management (EM)

    Department of Energy to NOI re Retrospective Risk Pooling Program For Suppliers Comment to NOI re Retrospective Risk Pooling Program For Suppliers Comment by Cameco Resources On Retrospective Risk Pooling Program For Suppliers, 75 Fed. Reg. 43945 (July 27, 2010), Section 934 Rule Making. As discussed below, Cameco believes that producers and providers of uranium concentrates and UF6 conversion services, whether directly or as an intermediary, should be excluded from the definition of nuclear

  6. The IMCA: A field instrument for uranium enrichment measurements

    SciTech Connect (OSTI)

    Gardner, G.H.; Koskelo, M.; Moeslinger, M.; Mayer, R.L. II; McGinnis, B.R.; Wishard, B.

    1996-12-31

    The IMCA (Inspection Multi-Channel Analyzer) is a portable gamma-ray spectrometer designed to measure the enrichment of uranium either in a laboratory or in the field. The IMCA consists of a Canberra InSpector Multi-Channel Analyzer, sodium iodide or a planar germanium detector, and special application software. The system possesses a high degree of automation. The IMCA uses the uranium enrichment meter principle, and is designed to meet the International Atomic Energy Agency (IAEA) requirements for the verification of enriched uranium materials. The IMCA is available with MGA plutonium isotopic analysis software or MGAU uranium analysis software as well. In this paper, the authors present a detailed description of the hardware and software of the IMCA system, as well as results from preliminary measurements testing compliance of IMCA with IAEA requirements using uranium standards and UF6 cylinders. Measurements performed on UF6 cylinders in the field under variable environmental conditions (temperatures ranging from 0 to 35 C) have shown that good results can be achieved. The enrichment of UF6 contained in the cylinder is determined by using calibration constants generated from an instrument calibration, using traceable uranium oxide standards, performed in the laboratory under controlled environmental conditions. The IMCA software is designed to make the necessary matrix and container corrections to ensure that accurate results are achieved in the field.

  7. May market review. [Spot market prices for uranium (1993)

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    Seven uranium transactions totalling nearly three million pounds equivalent U3O8 were reported during May, but only two, totalling less than 200 thousand pounds equivalent U3O8, involved concentrates. As no discretionary buying occurred during the month, and as near-term supply and demand were in relative balance, prices were steady, while both buyers and sellers appeared to be awaiting some new market development to signal the direction of future spot-market prices. The May 31, 1993, Exchange Value and the Restricted American market Penalty (RAMP) for concentrates were both unchanged at $7.10, and $2.95 per pound U3O8, respectively. NUEXCO's judgement was that transactions for significant quantities of uranium concentrates that were both deliverable in and intended for consumption in the USA could have been concluded on May 31 at $10.05 per pound U3O8. Two near-term concentrate transactions were reported in which one US utility purchased less than 200 thousand pounds equivalent U3O8 from two separate sellers. These sales occurred at price levels at or near the May 31 Exchange Value plus RAMP. No long-term uranium transactions were reported during May. Consequently, the UF6 Value decreased $0.20 to $24.30 per kgU as UF6, reflecting some weakening of the UF6 market outside the USA.

  8. Balendra Sutharshan | Argonne National Laboratory

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

    Balendra Sutharshan Chief Operations Officer - EGS E-mail bsutharshan

  9. Ryne T. Willig | Argonne National Laboratory

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

    Ryne T. Willig Safety Associate - EGS E-mail rwillig

  10. Osman Eryilmaz | Argonne National Laboratory

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

    Osman Eryilmaz Principal Materials Scientist E-mail eryilmaz

  11. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Zaldarriaga, Matias, E-mail: stassev@cfa.harvard.edu, E-mail: matiasz@ias.edu School of ... Zaldarriaga, Matias, E-mail: stassev@cfa.harvard.edu, E-mail: matiasz@ias.edu We obtain ...

  12. QER - Comment of Irrigation & Electrical Districts Association...

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

    kiefer@flake.senate.gov; ken.montoya@mail.house.gov; grant.kerr@mail.house.gov; Glenn Miller; Jeff Small; Greg Safsten; beau.brunson@mail.house.gov; doug.gascon@mail.house.gov;...

  13. Jack VanKuiken | Argonne National Laboratory

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

    Systems Engineer Jack VanKuiken E-mail jvankuiken

  14. Hyekyung Kim | Argonne National Laboratory

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

    Hyekyung Kim Hyekyung Kim Postdoctoral Appointee E-mail clarisse

  15. K-311-1/K-310-3 Purge Cascade Process Description, Oak Ridge Environmental Management Accelerated Cleanup Project, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Shoemaker J.E.

    2009-05-13

    K-311-1 was constructed along with the rest of the K-25 Building in the 1943-1945 timeframe. K-311-1 was equipped with Size 3 converters and Size 38 Allis Chalmers{trademark} single-stage centrifugal compressors driven by 3600 rpm electric motors, and the unit operated as the 'bottom' unit flow-wise in K-25. The depleted flow from the bottom stage in K-311-1 passed through booster compressors and flowed to the K-601 Building where the depleted or 'tails' material was removed. In 1948, after the K-27 Building was completed, the decision was made to operate K-27 and K-25 in series rather than operate the two buildings as separate entities. To facilitate this operation, concrete bases were poured and two sets of booster compressors were installed in the extreme West end of the K-311-1 cell floor. These compressors were enclosed in heated housings and consisted of Size 38 compressors. One pair was to boost the 'B' flow between K-25 and K-27, and one pair was to boost the 'A' flow between the buildings. Each station operated with one compressor on-stream and the other in standby. (Reference 9) Each station also was equipped with a Size 2 after-cooler located in the discharge stream downstream of the junction of the onstream and standby compressors. Additional gaseous diffusion capacity was added at Oak Ridge as K-29, K-31, and K-33 were constructed and placed in service in the early 1950s. As a result of the additional process equipment added by these buildings, in-leakage of light gases to the cascade including light gases introduced into the cascade as a result of purging operations threatened to exceed the capacity of the existing K-312 Purge Cascade facilities in the K-25 Building. As a result, in 1954 K-311-1 was converted to a side purge cascade to remove light gases from the process gas stream as the stream entered K-25 from K-27. Low molecular weight gas in-leakage in K-33, K-31, K-29, and K-27 was removed by the K-311-1 Side Purge Facility and a relatively pure stream of UF6 then passed from K-311-1 into the upstream cells in K-25. In-leakage of light gases in the K-25 Building continued to be removed by the K-312 Purge Facilities. K-311-1 operated as a Side Purge Cascade from 1954 until the K-25 Building was shut down in 1964; at that time K-311-1 became the Oak Ridge Gaseous Diffusion Plant (ORGDP) Top (and only) Purge Cascade. The adjacent K-310-3 Unit was operated along with K-311-1 as the top purge cascade and K-310-2 was also operated at times to supplement cells in the K311-1/K-310-3 Purge Cascade. K-311-1 was shut down on February 14, 1977, after the newer, larger capacity K-402-9 Purge Cascade was placed in operation. K-310-3 continued to operate until the K-402-8 Coolant Removal Unit was placed in service, and K-310-3 was shut down on March 14, 1978. Since the K-311-1 and K-310-3 units continued to operate after K-25 shutdown, removal of equipment such as valves and piping for other projects did not occur in this area. As a result, these two units have not been exposed to atmospheric wet air over the years as much of the remainder of K-25 has been exposed. Any deposits or residual gases contained in K-311-1 or K-310-3 are not likely to be fully hydrolyzed.

  16. A NEW SUB-PERIOD-MINIMUM CATACLYSMIC VARIABLE WITH PARTIAL HYDROGEN DEPLETION AND EVIDENCE OF SPIRAL DISK STRUCTURE

    SciTech Connect (OSTI)

    Littlefield, C.; Garnavich, P.; Magno, K.; Applegate, A.; Pogge, R.; Irwin, J.; Marion, G. H.; Kirshner, R.; Vinko, J.

    2013-06-15

    We present time-resolved spectroscopy and photometry of CSS 120422:111127+571239 (=SBS 1108+574), a recently discovered SU UMa-type dwarf nova whose 55 minute orbital period is well below the cataclysmic variable (CV) period minimum of {approx}78 minutes. In contrast with most other known CVs, its spectrum features He I emission of comparable strength to the Balmer lines, implying a hydrogen abundance less than 0.1 of long-period CVs-but still at least 10 times higher than that in AM CVn stars. Together, the short orbital period and remarkable helium-to-hydrogen ratio suggest that mass transfer in CSS 120422 began near the end of the donor star's main-sequence lifetime, meaning that this CV is a strong candidate progenitor of an AM CVn system as described by Podsiadlowski et al. Moreover, a Doppler tomogram of the H{alpha} line reveals two distinct regions of enhanced emission. While one is the result of the stream-disk impact, the other is probably attributable to spiral disk structure generated when material in the outer disk achieves a 2:1 orbital resonance with respect to the donor.

  17. HIGH PRECISION ABUNDANCES OF THE OLD SOLAR TWIN HIP 102152: INSIGHTS ON Li DEPLETION FROM THE OLDEST SUN

    SciTech Connect (OSTI)

    Monroe, TalaWanda R.; Melendez, Jorge; Tucci Maia, Marcelo; Freitas, Fabricio C.; Yong, David; Asplund, Martin; Alves-Brito, Alan; Casagrande, Luca; Bergemann, Maria; Bedell, Megan; Bean, Jacob; Lind, Karin; Castro, Matthieu; Do Nascimento, Jose-Dias; Bazot, Michael

    2013-09-10

    We present the first detailed chemical abundance analysis of the old 8.2 Gyr solar twin, HIP 102152. We derive differential abundances of 21 elements relative to the Sun with precisions as high as 0.004 dex ({approx}<1%), using ultra high-resolution (R = 110,000), high S/N UVES spectra obtained on the 8.2 m Very Large Telescope. Our determined metallicity of HIP 102152 is [Fe/H] = -0.013 {+-} 0.004. The atmospheric parameters of the star were determined to be 54 K cooler than the Sun, 0.09 dex lower in surface gravity, and a microturbulence identical to our derived solar value. Elemental abundance ratios examined versus dust condensation temperature reveal a solar abundance pattern for this star, in contrast to most solar twins. The abundance pattern of HIP 102152 appears to be the most similar to solar of any known solar twin. Abundances of the younger, 2.9 Gyr solar twin, 18 Sco, were also determined from UVES spectra to serve as a comparison for HIP 102152. The solar chemical pattern of HIP 102152 makes it a potential candidate to host terrestrial planets, which is reinforced by the lack of giant planets in its terrestrial planet region. The following non-local thermodynamic equilibrium Li abundances were obtained for HIP 102152, 18 Sco, and the Sun: log {epsilon} (Li) = 0.48 {+-} 0.07, 1.62 {+-} 0.02, and 1.07 {+-} 0.02, respectively. The Li abundance of HIP 102152 is the lowest reported to date for a solar twin, and allows us to consider an emerging, tightly constrained Li-age trend for solar twin stars.

  18. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Waxman, Eli, E-mail: fotini@star.ucl.ac.uk, E-mail: connolly@physics.osu.edu, E-mail: fba@star.ucl.ac.uk, E-mail: o.lahav@ucl.ac.uk, E-mail: sat@star.ucl.ac.uk, E-mail: ...

  19. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Waxman, Eli, E-mail: fotini@star.ucl.ac.uk, E-mail: connolly@physics.osu.edu, E-mail: fba@star.ucl.ac.uk, E-mail: o.lahav@ucl.ac.uk, E-mail: sat@star.ucl.ac.uk, E-mail: ...

  20. A search for correlation of ultra-high energy cosmic rays with...

    Office of Scientific and Technical Information (OSTI)

    David 3 ; Waxman, Eli, E-mail: fotini@star.ucl.ac.uk, E-mail: connolly@physics.osu.edu, E-mail: fba@star.ucl.ac.uk, E-mail: o.lahav@ucl.ac.uk, E-mail: sat@star.ucl.ac.uk, ...

  1. Email Updates about the Small Business Vouchers Pilot | NREL

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

    Email Updates about the Small Business Vouchers Pilot Subscribe Please enter and submit your e-mail address to receive periodic updates about the Small Business Vouchers Pilot. E-mail Address: Subscribe Unsubscribe Please enter and submit your e-mail address to unsubscribe from the mailing list for the Small Business Vouchers Pilot. E-mail Address: Unsubscribe

  2. Application of the sources code in nuclear safeguards

    SciTech Connect (OSTI)

    Beddingfield, D. H.

    2002-01-01

    The Sources Code System provides a greatly expanded calculational capacity in the field of nuclear safeguards. It is becoming more common that we are called upon to perform assays on materials for which no standards exist. These materials tend to be mixtures of nuclear materials and low-Z compounds (spent fuels in a variety of matrices, in-process compounds such as UF6, MOX with varying water content). We will present soma applications of the Sources Code and discuss the application calculated (a,n) source terms in neutron coincidence counting for nuclear safeguards.

  3. 150122 Traxys DOE RFI Comments

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

    TRAXYS RESPONSES to DOE'S RFI ON EXCESS URANIUM MANAGEMENT Summary Statements based on Traxys' contracts and EIA Form 858 Filings: 1. Traxys is a primary, direct participant in the sale and introduction to market of the majority of DOE's excess uranium sales via a contractual relationship with Fluor B&W Portsmouth (FBP) to purchase and monetize all the UF6 it receives from DOE for services. Based on this unique position, Traxys is the only company that can factually comment and have actual

  4. DOE Releases '2015 Year in Review' of Paducah Site | Department of

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

    Energy Paducah Site DOE Releases '2015 Year in Review' of Paducah Site December 30, 2015 - 11:30am Addthis An excavator with a shear attachment performs “top-down” shearing during final stages of the demolition of the C-410/C-420 UF6 Feed Plant Complex in June. Demolition debris was downsized and loaded into rail cars for shipment off site. The complex was the last of 32 inactive facilities to be removed as part of the cleanup scope that existed before commercial uranium enrichment

  5. Paducah News | Department of Energy

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

    Paducah Site » Paducah Community Outreach » Paducah News Paducah News December 30, 2015 An excavator with a shear attachment performs "top-down" shearing during final stages of the demolition of the C-410/C-420 UF6 Feed Plant Complex in June. Demolition debris was downsized and loaded into rail cars for shipment off site. The complex was the last of 32 inactive facilities to be removed as part of the cleanup scope that existed before commercial uranium enrichment operations ended at

  6. DOE - Office of Legacy Management -- Koppers Co Inc - PA 25

    Office of Legacy Management (LM)

    Koppers Co Inc - PA 25 FUSRAP Considered Sites Site: KOPPERS CO., INC. (PA.25 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Pittsburgh , Pennsylvania PA.25-1 Evaluation Year: 1987 PA.25-2 Site Operations: Conducted pilot-scale studies on the commercial production of UF4 and UF6. PA.25-1 Site Disposition: Eliminated - No Authority - Facility was licensed to handle nuclear materials PA.25-2 PA.25-3 Radioactive Materials Handled:

  7. DOE - Office of Legacy Management -- Spencer Chemical Co - KS 0-01

    Office of Legacy Management (LM)

    KS 0-01 FUSRAP Considered Sites Site: SPENCER CHEMICAL CO. (KS.0-01 ) Eliminated from further consideration under FUSRAP - an AEC licensed operation Designated Name: Not Designated Alternate Name: Jayhawk Works KS.0-01-1 Location: Pittsburg , Kansas KS.0-01-1 Evaluation Year: 1985 KS.0-01-2 Site Operations: Processed enriched uranium (UF-6) and scrap to produce primarily uranium dioxide (UO-2) under AEC licenses. KS.0-01-3 KS.0-01-4 Site Disposition: Eliminated - No Authority - AEC licensed

  8. DOE - Office of Legacy Management -- Spencer Chemical Co - MO 0-01

    Office of Legacy Management (LM)

    MO 0-01 FUSRAP Considered Sites Site: SPENCER CHEMICAL CO. (MO.0-01) Eliminated from further consideration under FUSRAP - an AEC licensed operation Designated Name: Not Designated Alternate Name: Jayhawk Works MO.0-01-1 Location: Joplin , Missouri MO.0-01-1 Evaluation Year: 1985 MO.0-01-2 Site Operations: Processed enriched uranium (UF-6) and scrap to produce primarily uranium dioxide (UO-2) under AEC licenses. MO.0-01-3 MO.0-01-4 Site Disposition: Eliminated - No Authority MO.0-01-2 Radioactive

  9. Mr. J. C. Delaney

    Office of Legacy Management (LM)

    .59 Mr. J. C. Delaney Division of Licensing and Regulation U. s. Atomic Energy CommikiiOn Washington:' 25, D. C. Dear Mr. Delaney: We are submitting herewiththres copies of our license application covering a facility for handling uranium up to and including 5% en- richment in U-235. The system is designed to process either UF6 ,~ or scrap to an oxide, nitrate or sulfate. At the present time we are operating a similar but smaller facility under license No. SNM-la, .and plan to continue its

  10. Sign me up to receive news and event updates

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    Mailing List Sign me up to receive news and event updates Find out what's happening @ the Bradbury Science Museum by joining our mailing list. Your Name Your Email Additional Comments Reset Submit Events Calendar Happening Now Mailing List

  11. New natural shapes of non-Gaussianity from high-derivative interaction...

    Office of Scientific and Technical Information (OSTI)

    Authors: Behbahani, Siavosh R. 1 ; Mirbabayi, Mehrdad 2 ; Senatore, Leonardo 3 ; Smith, Kendrick M., E-mail: siavoshrezvan@gmail.com, E-mail: mehrdadm@ias.edu, E-mail: ...

  12. Evaluation of the exothermicity of the chemi-ionization reaction...

    Office of Scientific and Technical Information (OSTI)

    Authors: Cox, Richard M ; Kim, JungSoo ; Armentrout, P. B., E-mail: armentrout@chem.utah.edu, E-mail: mheaven@emory.edu, E-mail: albert.viggiano@us.af.mil 1 ; Bartlett, Joshua ; ...

  13. Laboratory Equipment Donation Program - Administrative Login

    Office of Scientific and Technical Information (OSTI)

    Password: Logon Reset Forgot your username or password or need to change your e-mail address? Send e-mail to pf-lepd@osti.gov. Need to change OPMO contact (i.e., e-mail, name, ...

  14. Microsoft Word - Current Contact Information2.docx

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

    Contact Information: Name: Date: Z Number: Home Phone: ( ) Cell Phone: ( ) Work Phone: ( ) Mailing Address: Street or PO Box_____________________________________________ Apt #____________ City___________________________ State_________________________ Zip Code_____________ Personal e-mail: Work e-mail:

  15. IN-SPIRE: Creating a Visualization from Microsoft Outlook

    ScienceCinema (OSTI)

    None

    2012-12-31

    IN-SPIRE can harvest text from Microsoft Outlook e-mail messages via a simple drag-and-drop mechanism. This is great for mailing lists or systems that send search results via e-mail.

  16. DOE HQ F 1410.8 | Department of Energy

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

    DOE HQ F 1410.8 Form used to notify mail recipients that they have mail to be picked up. PDF icon Notification of Incoming Mail More Documents & Publications DOE HQ F 1410.2 ...

  17. Undergraduate Students | Photosynthetic Antenna Research Center

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

    Undergraduate Students Undergraduate Students Ingrid Archibald Undergraduate Student E-mail: ingridarchibald@wustl.edu Divya Babbula Undergraduate Student E-mail: divya.babbula@wustl.edu Hannah Behar Undergraduate Student Sasha Berger Undergraduate Student E-mail: sashaberger@wustl.edu Stephanie Botkin E-mail: stephanie.botkin@wustl.edu Kyle Cepeda Undergraduate Student E-mail: kcepeda@wustl.edu Maya Dehart Undergraduate Student E-mail: mayadehart@wustl.edu Andrew Ells Undergraduate Student

  18. My Account | Critical Materials Institute

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    My Account Primary tabs Log in Request new password(active tab) Username or e-mail address * E-mail new password

  19. © Marketing Edge Consulting Group and TargetGov Successful Marketing...

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

    ... More Virtual Networks * Website * E-mail * Podcasts * Webinars * E-mail Newsletter * Online advertising * Online Social Networks 20 Marketing Edge Consulting Group and TargetGov ...

  20. Hybrid-state emission in a polythienylenevinylene derivative...

    Office of Scientific and Technical Information (OSTI)

    Authors: Lafalce, Evan, E-mail: elafalce@mail.usf.edu ; Jiang, Xiaomei ; Pan, Jianjun 1 ; Whittington, Christi ; Larsen, Randy 2 ; Sanow, Logan P. ; Zhang, Cheng 3 + Show ...

  1. BPA-2014-00787-FOIA Correspondence

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

    Mailing List of approximately 3500 members, to include the mailings regarding the 2012 Fish Accord MOA with the Kalispell Tribe. 2) The press release inviting public comment on...

  2. User account | The Ames Laboratory

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    User account User account Primary tabs Log in Request new password(active tab) Username or e-mail address * E-mail new password

  3. Bryan Fry | Photosynthetic Antenna Research Center

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

    Bryan Fry Bryan Fry Bryan Fry Graduate Student E-mail: bryanfry@mail.med.upenn.edu Website: University of Pennsylvania Graduate...

  4. Graduate Students | Photosynthetic Antenna Research Center

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

    People / Graduate Students Graduate Students Sam Barnett Graduate Student E-mail: sbarnett1@sheffield.ac.uk Angela Barragan Graduate Student E-mail: ambarrag@gmail.com Hui-Yuan Chen Graduate Student E-mail: chen.hui-yuan@wustl.edu Jack Chidgey Graduate Student E-mail: j.chidgey@sheffield.ac.uk Kaitlyn Faries Kaitlyn Faries Graduate Student E-mail: kaitlyn.faries@wustl.edu Phone: 314.935.6566 Bryan Fry Graduate Student E-mail: bryanfry@mail.med.upenn.edu Kirsty Hacking Graduate Student E-mail:

  5. Contact Us | NREL

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

    Contact Us Find mailing addresses, phone numbers, and contact information for NREL staff. Mailing Address and Phone Numbers Golden, Colorado Laboratories and Offices National...

  6. RCPO1 - A Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability

    SciTech Connect (OSTI)

    Ondis, L.A., II; Tyburski, L.J.; Moskowitz, B.S.

    2000-03-01

    The RCP01 Monte Carlo program is used to analyze many geometries of interest in nuclear design and analysis of light water moderated reactors such as the core in its pressure vessel with complex piping arrangement, fuel storage arrays, shipping and container arrangements, and neutron detector configurations. Written in FORTRAN and in use on a variety of computers, it is capable of estimating steady state neutron or photon reaction rates and neutron multiplication factors. The energy range covered in neutron calculations is that relevant to the fission process and subsequent slowing-down and thermalization, i.e., 20 MeV to 0 eV. The same energy range is covered for photon calculations.

  7. DESIGN AND IMPLEMENTATION OF A CO2 FLOOD UTILIZING ADVANCED RESERVOIR CHARACTERIZATION AND HORIZONTAL INJECTION WELLS IN A SHALLOW SHELF CARBONATE APPROACHING WATERFLOOD DEPLETION

    SciTech Connect (OSTI)

    K.J. Harpole; Ed G. Durrett; Susan Snow; J.S. Bles; Carlon Robertson; C.D. Caldwell; D.J. Harms; R.L. King; B.A. Baldwin; D. Wegener; M. Navarrette

    2002-09-01

    The purpose of this project was to economically design an optimum carbon dioxide (CO{sub 2}) flood for a mature waterflood nearing its economic abandonment. The original project utilized advanced reservoir characterization and CO{sub 2} horizontal injection wells as the primary methods to redevelop the South Cowden Unit (SCU). The development plans; project implementation and reservoir management techniques were to be transferred to the public domain to assist in preventing premature abandonment of similar fields. The Unit was a mature waterflood with water cut exceeding 95%. Oil must be mobilized through the use of a miscible or near-miscible fluid to recover significant additional reserves. Also, because the unit was relatively small, it did not have the benefit of economies of scale inherent in normal larger scale projects. Thus, new and innovative methods were required to reduce investment and operating costs. Two primary methods used to accomplish improved economics were use of reservoir characterization to restrict the flood to the higher quality rock in the unit and use of horizontal injection wells to cut investment and operating costs. The project consisted of two budget phases. Budget Phase I started in June 1994 and ended late June 1996. In this phase Reservoir Analysis, Characterization Tasks and Advanced Technology Definition Tasks were completed. Completion enabled the project to be designed, evaluated, and an Authority for Expenditure (AFE) for project implementation submitted to working interest owners for approval. Budget Phase II consisted of the implementation and execution of the project in the field. Phase II was completed in July 2001. Performance monitoring, during Phase II, by mid 1998 identified the majority of producing wells which under performed their anticipated withdrawal rates. Newly drilled and re-activated wells had lower offtake rates than originally forecasted. As a result of poor offtake, higher reservoir pressure was a concern for the project as it limited CO{sub 2} injectivity. To reduce voidage balance, and reservoir pressure, a disposal well was therefore drilled. Several injection surveys indicated the CO{sub 2} injection wells had severe conformance issues. After close monitoring of the project to the end of 1999, it was evident the project would not recover the anticipated tertiary reserves. The main reasons for under-performance were poor in zone CO{sub 2} injection into the upper San Andres layers, poorer offtake rates from newly drilled replacement wells and a higher than required reservoir pressure. After discussion internally within Phillips, externally with the Department of Energy (DOE) and SCU partners, a redevelopment of South Cowden was agreed upon to commence in year 2000. The redevelopment essentially abandoned the original development for Budget Phase II in favor of a revised approach. This involved conformance techniques to resolve out of zone CO{sub 2} injection and use of horizontal wells to improve in zone injectivity and productivity. A phased approach was used to ensure short radius lateral drilling could be implemented effectively at South Cowden. This involved monitoring drilling operations and then production response to determine if larger investments during the second phase were justified. Redevelopment Phase 1 was completed in May 2000. It was deemed a success in regard to finding suitable/cost-effective technology for drilling horizontal laterals and finding a technique that could sustain long-term productivity from the upper layers of the San Andres reservoir. Four existing vertical producing wells were isolated from their existing completions and sidetracked with horizontal laterals into the upper layers of the San Andres. Overall average offtake rates for the four wells increased by a factor of 12 during the first four months after completion of Phase 1. Phase 2 of the redevelopment focused on current CO{sub 2} vertical injection wells. Techniques were applied to resolve near well conformance concerns and then either single or dual laterals were dril

  8. Design and Implementation of a CO2 Flood Utilizing Advanced Reservoir Characterization and Horizontal Injection Wells In a Shallow Shelf Carbonate Approaching Waterflood Depletion, Class II

    SciTech Connect (OSTI)

    Wier, Don R. Chimanhusky, John S.; Czirr, Kirk L.; Hallenbeck, Larry; Gerard, Matthew G.; Dollens, Kim B.; Owen, Rex; Gaddis, Maurice; Moshell, M.K.

    2002-11-18

    The purpose of this project was to economically design an optimum carbon dioxide (CO2) flood for a mature waterflood nearing its economic abandonment. The original project utilized advanced reservoir characterization and CO2 horizontal injection wells as the primary methods to redevelop the South Cowden Unit (SCU). The development plans; project implementation and reservoir management techniques were to be transferred to the public domain to assist in preventing premature abandonment of similar fields.

  9. Ethane enrichment and propane depletion in subsurface gases indicate gas hydrate occurrence in marine sediments at southern Hydrate Ridge offshore Oregon

    SciTech Connect (OSTI)

    Milkov, Alexei V.; Claypool, G E.; Lee, Young-Joo; Torres, Marta E.; Borowski, W S.; Tomaru, H; Sassen, Roger; Long, Philip E.

    2004-07-02

    The recognition of finely disseminated gas hydrate in deep marine sediments heavily depends on various indirect techniques because this mineral quickly decomposes upon recovery from in situ pressure and temperature conditions. Here, we discuss molecular properties of closely spaced gas voids (formed as a result of core recovery) and gas hydrates from an area of relatively low gas flux at the flanks of the southern Hydrate Ridge Offshore Oregon (ODP Sites 1244, 1245 and 1247).

  10. Preliminary Concept of Operations for a Global Cylinder Identification and Monitoring System

    SciTech Connect (OSTI)

    Whitaker, J. M.; White-Horton, J. L.; Morgan, J. B.

    2013-08-01

    This report describes a preliminary concept of operations for a Global Cylinder Identification and Monitoring System that could improve the efficiency of the International Atomic Energy Agency (IAEA) in conducting its current inspection activities and could provide a capability to substantially increase its ability to detect credible diversion scenarios and undeclared production pathways involving UF6 cylinders. There exist concerns that a proliferant State with access to enrichment technology could obtain a cylinder containing natural or low-enriched uranium hexafluoride (UF6) and produce a significant quantity (SQ)1 of highly enriched uranium in as little as 30 days. The National Nuclear Security Administration (NNSA) through the Next Generation Safeguards Initiative sponsored a multi-laboratory team to develop an integrated system that provides for detecting scenarios involving 1) diverting an entire declared cylinder for enrichment at a clandestine facility, 2) misusing a declared cylinder at a safeguarded facility, and 3) using an undeclared cylinder at a safeguarded facility. An important objective in developing this integrated system was to improve the timeliness for detecting the cylinder diversion and undeclared production scenarios. Developing this preliminary concept required in-depth analyses of current operational and safeguards practices at conversion, enrichment, and fuel fabrication facilities. The analyses evaluated the processing, movement, and storage of cylinders at the facilities; the movement of cylinders between facilities (including cylinder fabrication); and the misuse of safeguarded facilities.

  11. Results of Inspections of Operation of the ORNL Mock Feed/Withdrawal System

    SciTech Connect (OSTI)

    White-Horton, Jessica L; Laughter, Mark D; Krichinsky, Alan M

    2010-01-01

    Remote monitoring of process activities is one tool under consideration by the International Atomic Energy Agency (IAEA) to handle increasing demands for conducting verification inspections at safeguarded facilities. The ability for the IAEA to continuously monitor feed and withdrawal (F&W) station operations (e.g., load cells and other process attributes) would provide independent verification of normal plant operations, supply data that would make safeguards more effective and efficient, and enable information-driven inspections. Researchers at Oak Ridge National Laboratory (ORNL) have assembled a mock UF6 F&W system using water in lieu of UF6 to test the feasibility of advanced process monitoring systems and concepts (such as remote monitoring) for safeguards. One use of the F&W mockup involves exploring how a safeguards inspector would interact with the data and use it to perform onsite inspections more effectively, so the researchers divided staff into two groups: operators and inspectors. This paper will discuss this process and the promising results of the inspections that have been performed at the mock facility to verify operator declarations and detect material diversion. This paper also will present the intuitive and user-friendly graphic interface researchers used to analyze the information. Although the data gathered previously came from a computer local to the F&W system, future work will include remote transmission and analysis of the data.

  12. FEMO, A FLOW AND ENRICHMENT MONITOR FOR VERIFYING COMPLIANCE WITH INTERNATIONAL SAFEGUARDS REQUIREMENTS AT A GAS CENTRIFUGE ENRICHMENT FACILITY

    SciTech Connect (OSTI)

    Gunning, John E; Laughter, Mark D; March-Leuba, Jose A

    2008-01-01

    A number of countries have received construction licenses or are contemplating the construction of large-capacity gas centrifuge enrichment plants (GCEPs). The capability to independently verify nuclear material flows is a key component of international safeguards approaches, and the IAEA does not currently have an approved method to continuously monitor the mass flow of 235U in uranium hexafluoride (UF6) gas streams. Oak Ridge National Laboratory is investigating the development of a flow and enrichment monitor, or FEMO, based on an existing blend-down monitoring system (BDMS). The BDMS was designed to continuously monitor both 235U mass flow and enrichment of UF6 streams at the low pressures similar to those which exists at GCEPs. BDMSs have been installed at three sites-the first unit has operated successfully in an unattended environment for approximately 10 years. To be acceptable to GCEP operators, it is essential that the instrument be installed and maintained without interrupting operations. A means to continuously verify flow as is proposed by FEMO will likely be needed to monitor safeguards at large-capacity plants. This will enable the safeguards effectiveness that currently exists at smaller plants to be maintained at the larger facilities and also has the potential to reduce labor costs associated with inspections at current and future plants. This paper describes the FEMO design requirements, operating capabilities, and development work required before field demonstration.

  13. EIS-0359: DOE Notice of Availability of the Draft Supplement Analysis

    Broader source: Energy.gov [DOE]

    Disposal of Depleted Uranium Oxide Conversion Produce Generated from DOE's Inventory of Depleted Uranium Hexafluoride

  14. William Brocker | Argonne National Laboratory

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

    William Brocker ESH/QA Coordinator - EGS E-mail wbrocker

  15. Susan R. Podoba | Argonne National Laboratory

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

    Susan R. Podoba Executive Secretary to the Associate Laboratory Director - EGS E-mail spodoba

  16. Todd E. Combs | Argonne National Laboratory

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

    Todd E. Combs Interim Associate Laboratory Director - EGS E-mail tcombs

  17. Sharon Nykolyshyn | Argonne National Laboratory

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

    Sharon Nykolyshyn Executive Secretary - EGS Telephone 630-252-3739 E-mail snykolyshyn

  18. Robert Erck | Argonne National Laboratory

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

    Photo of Robert Erck Robert Erck Metallurgist E-mail erck

  19. Rodney East | Argonne National Laboratory

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

    Systems/Network Engineer Rodney East Telephone 630.252.2878 E-mail east

  20. Ron Tollner | Argonne National Laboratory

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

    Ron Tollner Manager, Building & Systems Operations Telephone 630.252.4457 E-mail tollner

  1. A. Scott Dunlop | Argonne National Laboratory

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

    A. Scott Dunlop National Security Facility Director - EGS E-mail adunlop

  2. Rachel E. Koritala | Argonne National Laboratory

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

    Scientific Associate Rachel E. Koritala Telephone 63.252.5564 E-mail koritala

  3. Peter Fuesz | Argonne National Laboratory

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

    Scientific Associate Peter Fuesz Telephone 630.252.7151 E-mail fuesz

  4. Renee M. Nault | Argonne National Laboratory

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

    Renee M. Nault Senior Manager, Business Development - EGS E-mail rmnault

  5. Aaron Greco | Argonne National Laboratory

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

    Aaron Greco Principal Materials Scientist E-mail agreco@anl.gov Website Argonne Experts

  6. Nicholaos Demas | Argonne National Laboratory

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

    Photo of Nick Demas Nicholaos Demas Assistant Materials Scientist E-mail ndemas

  7. Alex Martinson | Argonne National Laboratory

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

    Alex Martinson Telephone (630) 252-7520 E-mail martinson

  8. Oyelayo Ajayi | Argonne National Laboratory

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

    Photo of Layo Ajayi Oyelayo Ajayi Principal Materials Scientist E-mail ajayi

  9. George Crabtree | Argonne National Laboratory

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

    George Crabtree News Personalized energy Telephone (630) 252-5509 E-mail crabtree

  10. David Eckstein | Argonne National Laboratory

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

    Eckstein Principal Application Developer Telephone 630.252.7918 E-mail deckstein@anl.gov

  11. Denise M. Voss | Argonne National Laboratory

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

    Denise M. Voss Executive Secretary to the Chief Operations Officer - EGS E-mail dvoss

  12. Eugene Stewart | Argonne National Laboratory

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

    Technician Sr. Eugene Stewart Telephone 630.252.4466 E-mail estewart

  13. Eric Rask | Argonne National Laboratory

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    Rask Eric Rask Principal Research Engineer E-mail erask@anl.gov

  14. Edward J. Daniels | Argonne National Laboratory

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    Edward J. Daniels Sr. Energy Systems Scientist Telephone (630) 252-5279 E-mail edaniels

  15. Jordi Roglans-Ribas | Argonne National Laboratory

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

    Jordi Roglans-Ribas Director, Nuclear Engineering Division E-mail roglans

  16. Judi Yaeger | Argonne National Laboratory

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

    Technician Sr. Judi Yaeger Telephone 630.252.5166 E-mail jyaeger

  17. Julie Emery | Argonne National Laboratory

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

    Julie Emery User Program Coordinator Telephone (630) 252-6952 E-mail jemery

  18. Hubert Ley | Argonne National Laboratory

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

    Hubert Ley Hubert Ley Director, Transportation Research and Analysis Computing Center (TRACC) E-mail hley

  19. Hussein S. Khalil | Argonne National Laboratory

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

    Hussein S. Khalil Nuclear Energy and Security Program Leader - EGS E-mail hkhalil

  20. Mary A. McIntyre | Argonne National Laboratory

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

    A. McIntyre Business Strategist - EGS E-mail mmcintyre

  1. Mary Ellen Hennebry | Argonne National Laboratory

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

    Ellen Hennebry Assistant to the Associate Laboratory Director - EGS E-mail mehennebry

  2. Daniel Molzahn | Argonne National Laboratory

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

    Photo of Daniel Molzahn Daniel Molzahn Computational Engineer, Energy Systems Modeling & Simulation E-mail dmolzahn...

  3. Feedback following the Industry Engagement of the NNSA Unique Identifier and Global Monitoring 5 year plan

    SciTech Connect (OSTI)

    White-Horton, Jessica L; Whitaker, J Michael; Durbin, Karyn R.

    2013-01-01

    The National Nuclear Security Administration s project for developing a unique identifier and a concept for a global monitoring system for UF6 cylinders made significant progress on developing functional requirements and a concept of operation for such a system. The multi-laboratory team is working to define the functional requirements for both the unique identifier and the global monitoring system and to develop a preliminary concept of operations to discuss with key industry stakeholders. Team members began meeting with industry representatives in January 2013 to discuss the preliminary concept and solicit feedback and suggestions. The team has met with representatives from United States Enrichment Corporation, Cameco, URENCO, Honeywell/ConverDyn, and others. This paper presents an overview of the preliminary concept of operations and shares the feedback obtained from the industry engagement meetings.

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

    SciTech Connect (OSTI)

    Brim, Cornelia P.

    2013-04-01

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

  5. Development of Halide and Oxy-Halides for Isotopic Separations

    SciTech Connect (OSTI)

    Leigh R. Martin; Aaron T. Johnson; Jana Pfeiffer; Martha R. Finck

    2014-10-01

    The goal of this project was to synthesize a volatile form of Np for introduction into mass spectrometers at INL. Volatile solids of the 5f elements are typically those of the halides (e.g. UF6), however fluorine is highly corrosive to the sensitive internal components of the mass separator, and the other volatile halides exist as several different stable isotopes in nature. However, iodide is both mono-isotopic and volatile, and as such presents an avenue for creation of a form of Np suitable for introduction into the mass separator. To accomplish this goal, the technical work in the project sought to establish a novel synthetic route for the conversion NpO2+ (dissolved in nitric acid) to NpI3 and NpI4.

  6. Research and Technical Associates | Photosynthetic Antenna Research Center

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

    and Technical Associates Research and Technical Associates Maitrayee Bhattacharyya Senior Research Associate E-mail: maitrayee@biology2.wustl.edu Amanda Brindley Laboratory Technician E-mail: a.brindley@sheffield.ac.uk Ashley Cadby Ashley Cadby Senior Lecturer E-mail: a.cadby@sheffield.ac.uk Phone: +44 114 222 4295 Matthew Cuneo Instrument Scientist E-mail: cuneomj@ornl.gov Bohdana Discher Bohdana Discher Research Associate E-mail: bohdana@mail.med.upenn.edu Phone: 215.898.5668 Sudipa

  7. A Robust Infrastructure Design for Gas Centrifuge Enrichment Plant Unattended Online Enrichment Monitoring

    SciTech Connect (OSTI)

    Younkin, James R; Rowe, Nathan C; Garner, James R

    2012-01-01

    An online enrichment monitor (OLEM) is being developed to continuously measure the relative isotopic composition of UF6 in the unit header pipes of a gas centrifuge enrichment plant (GCEP). From a safeguards perspective, OLEM will provide early detection of a facility being misused for production of highly enriched uranium. OLEM may also reduce the number of samples collected for destructive assay and if coupled with load cell monitoring can provide isotope mass balance verification. The OLEM design includes power and network connections for continuous monitoring of the UF6 enrichment and state of health of the instrument. Monitoring the enrichment on all header pipes at a typical GCEP could require OLEM detectors on each of the product, tails, and feed header pipes. If there are eight process units, up to 24 detectors may be required at a modern GCEP. Distant locations, harsh industrial environments, and safeguards continuity of knowledge requirements all place certain demands on the network robustness and power reliability. This paper describes the infrastructure and architecture of an OLEM system based on OLEM collection nodes on the unit header pipes and power and network support nodes for groupings of the collection nodes. A redundant, self-healing communications network, distributed backup power, and a secure communications methodology. Two candidate technologies being considered for secure communications are the Object Linking and Embedding for Process Control Unified Architecture cross-platform, service-oriented architecture model for process control communications and the emerging IAEA Real-time And INtegrated STream-Oriented Remote Monitoring (RAINSTORM) framework to provide the common secure communication infrastructure for remote, unattended monitoring systems. The proposed infrastructure design offers modular, commercial components, plug-and-play extensibility for GCEP deployments, and is intended to meet the guidelines and requirements for unattended and remotely monitored safeguards systems.

  8. EIS-0360: DOE Notice of Availability of the Draft Supplement Analysis

    Broader source: Energy.gov [DOE]

    Disposal of Depleted Uranium Oxide Conversion Produce Generated from DOE's Inventory of Depleted Uranium Hexafluoride, Clive, Utah

  9. BPA-2014-00787-FOIA Request

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

    - D-1 Subject: FW: FOIA COE SL-003 BPA JOURNAL MAILING List Kalispell MOA 3-28-2014 Hi Christy and Kim, Pursuant to the FOIA, I request a copy of: 1) The BPA Journal Mailing...

  10. Safety Staff Contact Information

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

    e-mail address is being protected from spambots. You need JavaScript enabled to view it (EPS) This e-mail address is being protected from spambots. You need JavaScript enabled to...

  11. Microsoft Word - CLWR Draft SEIS Comment

    National Nuclear Security Administration (NNSA)

    Comment forms may be mailed to: Comment forms may be sent by electronic mail to: Mr. Curtis Chambellan tritium.readiness.seis@doeal.gov CLWR SEIS Document Manager U.S. DOENNSA...

  12. TITLE AUTHORS SUBJECT SUBJECT RELATED DESCRIPTION PUBLISHER AVAILABILI...

    Office of Scientific and Technical Information (OSTI)

    solar neighborhood XXXV Distances to M dwarf systems within PC in the southern sky Winters Jennifer G Jao Wei Chun Dieterich Sergio B E mail winters astro gsu edu E mail jao astro...

  13. Magnetohydrodynamics and deep mixing in evolved stars. I. Two...

    Office of Scientific and Technical Information (OSTI)

    Authors: Nucci, M. C. 1 ; Busso, M., E-mail: mariaclara.nucci@unipg.it, E-mail: busso@fisica.unipg.it 2 + Show Author Affiliations Department of Mathematics and Informatics, ...

  14. This Week In Petroleum Printer-Friendly Version

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

    and e-mails to EIA analysts. In fact, last year an e-mail was circulating around the Internet telling which oil companies imported the most crude oil from Persian Gulf countries...

  15. Bohdana Discher | Photosynthetic Antenna Research Center

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    Bohdana Discher Bohdana Discher Bohdana Discher Bohdana Discher Research Associate E-mail: bohdana@mail.med.upenn.edu Phone: 215.898.5668 Fax: 215.898.0465 Office: 1004...

  16. Scientific Advisory Committee | Photosynthetic Antenna Research...

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    Lagarias Scientific Advisory Committee Member E-mail: jclagarias@ucdavis.edu Thomas Moore Thomas Moore Scientific Advisory Committee Chair E-mail: tom.moore@asu.edu Phone:...

  17. ALSNews Vol. 320

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    Read more... Contact: This e-mail address is being protected from spambots. You need JavaScript enabled to view it and This e-mail address is being protected from spambots. You...

  18. ALSNews Vol. 364

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    more... Contacts: This e-mail address is being protected from spambots. You need JavaScript enabled to view it and This e-mail address is being protected from spambots. You...

  19. A comparison between characteristics of atmospheric-pressure...

    Office of Scientific and Technical Information (OSTI)

    Authors: Zhang, Cheng ; Shao, Tao, E-mail: st@mail.iee.ac.cn ; Wang, Ruixue ; Yan, Ping 1 ; Key Laboratory of Power Electronics and Electric Drive, Chinese Academy of Sciences, ...

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  1. Research Affiliates | Photosynthetic Antenna Research Center

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    Engel Gregory Engel Research Affiliate E-mail: gsengel@uchicago.edu Phone: 773.834.0818 Harry Frank Harry Frank Research Affiliate E-mail: harry.frank@uconn.edu Phone: 860.486.2844...

  2. August

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  4. BPA-2011-01724-FOIA Correspondence

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    the following: * An e-mail dated April 5, 2011 from Scott Bettin, BPA biologist, to Philip Key, BPA attorney. This e-mail is referred to in footnote 219 on page 77 of the...

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  6. Contacts | Department of Energy

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    information to contact the State and Local Solution Center by mail or email: U.S. Department of Energy State and Local Solution Center Mail Stop EE-5W 1000 Independence Ave., SW...

  7. Contact Us | Argonne National Laboratory

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    Contact Us Contact Us Postdoctoral Program Lead Kristene (Tina) Henne Phone: 630.252.2907 E-mail: khenne@anl.gov Administrative Support Kathy Eggers Phone: 630.252.6034 E-mail:...

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  9. LANL: AOT & LANSCE The Pulse April 2011

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    665-7657or e-mailing rbromero@lanl.gov. Your TA-53 WSST members WSST Chair: Eric Larson WSST Co-chair: Kristy Ortega WSST Secretary: Jean Trujillo E-mail: wsst53@lanl.gov...

  10. Search for: All records | SciTech Connect

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    Flanagan, anna ., E-mail: sb933@cornell.edu, E-mail: eef3@cornell.edu (1) Save Results Save this search to My Library Excel (limit 2000) CSV (limit 5000) XML (limit 5000) Have ...

  11. Acknowledgements of Federal Support | U.S. DOE Office of Science...

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  14. Radionuclide inventories : ORIGEN2.2 isotopic depletion calculation for high burnup low-enriched uranium and weapons-grade mixed-oxide pressurized-water reactor fuel assemblies.

    SciTech Connect (OSTI)

    Gauntt, Randall O.; Ross, Kyle W.; Smith, James Dean; Longmire, Pamela

    2010-04-01

    The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the elemental composition of irradiated low-enriched uranium (LEU)/mixed-oxide (MOX) pressurized-water reactor fuel assemblies. Described in this report are the input parameters for the ORIGEN2.2 calculations. The rationale for performing the ORIGEN2.2 calculation was to generate inventories to be used to populate MELCOR radionuclide classes. Therefore the ORIGEN2.2 output was subsequently manipulated. The procedures performed in this data reduction process are also described herein. A listing of the ORIGEN2.2 input deck for two-cycle MOX is provided in the appendix. The final output from this data reduction process was three tables containing the radionuclide inventories for LEU/MOX in elemental form. Masses, thermal powers, and activities were reported for each category.

  15. A modeling study of the effect of depth of burial of depleted uranium and thorium on radon gas flux at a dry desert alluvial soil radioactive waste management site (RWMS)

    SciTech Connect (OSTI)

    Lindstrom, F.T.; Cawlfield, D.E.; Emer, D.F.; Shott, G.J.

    1993-08-01

    An integral part of designing low-level waste (LLW) disposal pits and their associated closure covers in very dry desert alluvium is the use of a radon gas transport and fate model. Radon-222 has the potential to be a real heath hazard. The production of radon-222 results from the radioactive decay (a particle emission) of radium-226 in the uranium-235 and 238 Bateman chains. It is also produced in the thorium-230 series. Both long lived radionuclides have been proposed for disposal in the shallow land burial pits in Area 5 RWMS compound of Nevada Test Site (NTS). The constructed physics based model includes diffusion and barometric pressure-induced advection of an M-chain of radionuclides. The usual Bateman decay mechanics are included for each radionuclide. Both linear reversible and linear irreversible first order sorption kinetics are assumed for each radionuclide. This report presents the details of using the noble gas transport model, CASCADR9, in an engineering design study mode. Given data on the low-level waste stream, which constitutes the ultimate source of radon-222 in the RWMS, CASCADR9 is used to generate the surface flux (pCi/cm{sup 2}-sec) of radon-222 under the realistic atmospheric and alluvial soil conditions found in the RWMS at Area 5, of the NTS. Specifically, this study examines the surface flux of radon-222 as a function of the depth of burial below the land surface.

  16. Stuart Feinberg | Argonne National Laboratory

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    ES&H/QA Coordinator Stuart Feinberg Telephone 630.252.4673 E-mail sfeinberg@anl.gov

  17. Scott Massow | Argonne National Laboratory

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    Scott Massow Assistant Facility Manager Telephone 630.252.4620 E-mail smassow@anl.gov

  18. Supratik Guha | Argonne National Laboratory

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    NST Division Director Supratik Guha Telephone 630.252.7740 Fax 630.252.6866 E-mail sguha

  19. Suzanne Miller | Argonne National Laboratory

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    Engineering Specialist Senior Suzanne Miller Telephone 630.252.6790 Fax 630.252.5739 E-mail csmiller

  20. Webmaster

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    The Bioenergy Technologies Office always welcomes your feedback and suggestions. Contact us via mail, phone or email.

  1. Christine Meyer | Photosynthetic Antenna Research Center

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    Meyer Christine Meyer Christine Meyer Undergraduate Student E-mail: christinemeyer@wustl.edu Website: Washington University...

  2. Shrirang Abhyankar | Argonne National Laboratory

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    Photo of Shrirang Abhyankar Shrirang Abhyankar Computational Engineer Telephone (630) 252-0219 E-mail abhyshr

  3. Rachel Mirelez | Argonne National Laboratory

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    Administrative Secretary Rachel Mirelez Telephone 630.252.4651 Fax 630.252.6866 E-mail rmirelez

  4. Amgad Elgowainy | Argonne National Laboratory

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    Amgad Elgowainy Team Leader/Principal Energy Systems Analyst E-mail aelgowainy@anl.gov Projects Models and Tools

  5. Anthony Avarca | Argonne National Laboratory

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    Anthony Avarca Systems Administrator Sr. Telephone 630.252.4940 E-mail aavarca@anl.gov

  6. Nozomi Shirato | Argonne National Laboratory

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    Assistant Physicst Nozomi Shirato Telephone 630.252.3605 Fax 630.252.5739 E-mail nshirato

  7. Alec R. Sandy | Argonne National Laboratory

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    Alec Sandy Alec R. Sandy Physicist, Time Resolved Research Group Leader Telephone 630-252-0281 E-mail asandy

  8. Nestor J. Zaluzec | Argonne National Laboratory

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    Nestor J. Zaluzec Senior Materials Scientist Telephone 630.252.4798 E-mail zaluzec@aaem.amc

  9. Nikki Magdaong | Photosynthetic Antenna Research Center

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    Nikki Magdaong Nikki Magdaong Nikki Magdaong Postdoctoral Research Associate E-mail: magdaong.nikki@wustl.edu Postdoctoral Associates...

  10. Amit Mandal | Photosynthetic Antenna Research Center

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    Amit Mandal Amit Mandal Amit Mandal Postdoctoral Research Associate E-mail: mandala@wustl.edu Website: Washington University Postdoctoral...

  11. Andrew Novick | Photosynthetic Antenna Research Center

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    Novick Andrew Novick Andrew Novick Undergraduate Student E-mail: novick@wustl.edu Website: Washington University in St. Louis...

  12. Andrew Ells | Photosynthetic Antenna Research Center

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

    Ells Andrew Ells Andrew Ells Undergraduate Student E-mail: andrew.ells@wustl.edu Website: Washington University...

  13. Gaozhong Shen | Photosynthetic Antenna Research Center

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

    Gaozhong Shen Gaozhong Shen Gaozhong Shen Senior Research Associate E-mail: gxs22@psu.edu Website: Pennsylvania State

  14. H. Larry Collins | Argonne National Laboratory

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    H. Larry Collins Director, Intelligence Analysis Division E-mail lcollins@anl.gov Projects Counterintelligence National Security Facility...

  15. Vijaya Subramanian | Photosynthetic Antenna Research Center

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    Vijaya Subramanian Vijaya Subramanian placeholder image Vijaya Subramanian Postdoctoral Associate E-mail: vijaya65@hotmail.com Postdoctoral Associates

  16. High throughput lessons from the LHC experience.Johnston.TNC2013

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

    high throughput in widely distributed data management and analysis systems: Lessons from the LHC William E. Johnston ESnet, Lawrence Berkeley National Laboratory e-mail: wej@es.net Eli Dart ESnet, Lawrence Berkeley National Laboratory e-mail: dart@es.net Michael Ernst RHIC and ATLAS Computing Facility, Brookhaven National Laboratory e-mail: mernst@bnl.gov Brian Tierney ESnet, Lawrence Berkeley National Laboratory e-mail: bltierney@es.net Paper type Technical paper Abstract Today's large-scale

  17. Eva Stringer | Argonne National Laboratory

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    Administrative Secretary Eva Stringer Telephone 630.252.6889 Fax 630.252.4646 E-mail stringer

  18. Evgeny Ostroumov | Photosynthetic Antenna Research Center

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    Evgeny Ostroumov Evgeny Ostroumov Evgeny Ostroumov Associate Professional Specialist E-mail: ostroumov@princeton.edu Website: Princeton

  19. Cvetelin Vasilev | Photosynthetic Antenna Research Center

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

    Cvetelin Vasilev Cvetelin Vasilev Cvetelin Vasilev Cvetelin Vasilev Postdoctoral Associate E-mail: c.vasilev@sheffield.ac.uk

  20. Jag Kottapalli | Photosynthetic Antenna Research Center

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

    Jag Kottapalli Jag Kottapalli Jag Kottapalli Undergraduate Student E-mail: jkottapalli@wustl.edu Website: Washington University Undergraduate Students

  1. Jeremy King | Photosynthetic Antenna Research Center

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    Jeremy King Jeremy King Jeremy King Graduate Student E-mail: jdking@wustl.edu Website: Washington University Graduate

  2. Naryanan (Bobby) Kasthuri | Argonne National Laboratory

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    Neuroscience Researcher Naryanan (Bobby) Kasthuri Telephone 630.252.4966 Fax 630.252.5739 E-mail bobbykasthuri

  3. Joshua Auld | Argonne National Laboratory

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    Joshua Auld Joshua Auld Principal Computational Transportation Engineer E-mail jauld@anl.gov Website Profile

  4. Joshua Mancini | Photosynthetic Antenna Research Center

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    Joshua Mancini Joshua Mancini Joshua Mancini Graduate Student E-mail: joshuamancini07@gmail.com Website: University of Pennsylvania

  5. Kathryn Tietz | Argonne National Laboratory

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    Kathryn Tietz Administrative Secretary Telephone 630.252.4958 Fax 630.252.5739 E-mail ktietz

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    Kathy Vanoskey Administrative Secretary Telephone 630.252.4106 Fax 630. 252.6866 E-mail kvanoskey

  7. Kent Bostick | Argonne National Laboratory

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    Photo of Kent Bostick Kent Bostick Deputy Director of National and Global Security Programs - EGS E-mail kbostick

  8. Khem Acharya | Photosynthetic Antenna Research Center

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    Khem Acharya Khem Acharya Khem Acharya Alumnus E-mail: khem@k-state.edu Website: Kansas State University

  9. Contact Us | Photosynthetic Antenna Research Center

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    Contact Us Contact Us Your name * Your e-mail address * Subject * Message * Leave this field blank Submit...

  10. 033rlrpt.PDF

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

    ... Employees who chose to enter unescorted were excluded from the sample. Recommendation and ... * electronically mailed trainingjob requirement questionnaires to selected ...

  11. Matthew Cuneo | Photosynthetic Antenna Research Center

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    Cuneo Matthew Cuneo Matthew Cuneo Instrument Scientist E-mail: cuneomj@ornl.gov Website: Oak Ridge National Lab

  12. Daniel Oblinsky | Photosynthetic Antenna Research Center

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    Daniel Oblinsky Daniel Oblinsky Daniel Oblinsky Graduate Student E-mail: doblinsky@gmail.com Website: Princeton University Graduate Students...

  13. C:\Forms\HQ F 1410.8.cdr

    Energy Savers [EERE]

    U.S. Department of Energy Notification of Incoming Mail Receipt for Incoming Personal Mail Sender Name: Date Processed: Processed by: (Signature and Date of Person Picking up Mail) Employee Name: Routing Symbol: Room Number: Date Received: HQ F 1410.8 (8-84) HQ F 1410.8 (8-84) Date Contacted: MESSAGE To Sender: Mail must be picked up by: or item will be returned to sender. Part 1 Part 2

  14. EERE Publication and Product Library

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    Mail Requests You have not requested any products. You can request that products and publications be mailed to you by clicking on the "Request by Mail" link in the publication listings. Return to this page to complete your request

  15. Postdoctoral Associates | Photosynthetic Antenna Research Center

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    Postdoctoral Associates Postdoctoral Associates Alastair Gardiner Research Associate E-mail: alastair.gardiner@glasgow.ac.uk Phil Jackson Phil Jackson Postdoctoral Research Associate E-mail: p.j.jackson@sheffield.ac.uk Phone: 44 (0) 114 222 7599 placeholder image Jieying Jiao Assistant Specialist E-mail: jieying.jiao@ucr.edu Haijun Liu Postdoctoral Associate E-mail: hliu6@biology2.wustl.edu Phone: 314.935.4899 Xun Lu Postdoctoral Research Associate E-mail: lux1@ornl.gov placeholder image Craig

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    Alumni Alumni Khem Acharya Alumnus E-mail: khem@k-state.edu Peter Adams Alumnus Christine Ajinjeru Alumna Woo-Jin An Woo-Jin An Alumnus E-mail: woojinan@wustl.edu Stephen Anthony Alumnus David Armstrong Alumnus Khuram Ashraf Khuram Ashraf Alumnus David Bina David Bina Alumnus E-mail: david.bina@seznam.cz Pratim Biswas Pratim Biswas Alumnus E-mail: pratim.biswas@wustl.edu placeholder image Harry Bolson Alumnus E-mail: hbbholson@wustl.edu William Bricker William Bricker Alumnus placeholder image

  17. A Robust and Flexible Design for GCEP Unattended Online Enrichment Monitoring: An OLEM Collection Node Network

    SciTech Connect (OSTI)

    Younkin, James R; March-Leuba, Jose A; Garner, James R

    2013-01-01

    Oak Ridge National Laoratory (ORNL) has engineered an on-line enrichment monitor (OLEM) to continuously measure U-235 emissions from the UF6 gas flowing through a unit header pipe of a gas centrifuge enrichment plant (GCEP) as a component of the International Atomic Energy Agency s (IAEA) new generation of technology to support enrichment plant safeguards1. In contrast to other enrichment monitoring approaches, OLEM calibrates and corrects for the pressure and temperature dependent UF6 gas-density without external radiation sources by using the inherent unit header pipe pressure dynamics and combining U-235 gamma-ray spectrometery using a shielded NaI detector with gas pressure and temperature data near the spectrum measurement point to obtain the enrichment of the gas as a function of time. From a safeguards perspective, OLEM can provide early detection of a GCEP being misused for production of highly enriched uranium, but would not detect directly the isolation and use of a cascade within the production unit to produce HEU. OLEM may also reduce the number of samples collected for destructive assay and, if coupled with load cell monitoring, could support isotope mass balance verification and unattended cylinder verification. The earlier paper presented OLEM as one component along with shared load cells and unattended cylinder verification, in the IAEA emering toolbox for unattended instruments at GCEPs1 and described the OLEM concept and how previous modeling studies and field measurements helped confirm the viability of a passive on-line enrichment monitor for meeting IAEA objectives and to support the development of performance targets. Phase I of the United States Support Program (USSP) OLEM project completed a preliminary hardware, software and communications design; phase II will build and test field prototypes in controlled laboratory settings and then at an operational facility. That paper also discussed many of the OLEM collection node commercial off the shelf (COTS) components and summarized the OLEM collection node data security provisions. This paper will discuss a secure and redundant network of OLEM collection nodes, auxiliary detection units and supporting junction boxes distributed throughout a facility for monitoring enrichment on product, feed and tails unit header pipes; the purpose and capability of the built-in Electronic Optical Sealing System (EOSS) network gateway; and a network approach for obtaining reliable and authenticated pressure measurements.

  18. Milestones Keep DUF6 Plants Moving Ahead | Department of Energy

    Office of Environmental Management (EM)

    Milestones Keep DUF6 Plants Moving Ahead Milestones Keep DUF6 Plants Moving Ahead May 30, 2013 - 12:00pm Addthis Cylinders containing depleted uranium hexafluoride. Cylinders containing depleted uranium hexafluoride. The depleted uranium hexafluoride conversion plant in Paducah. The depleted uranium hexafluoride conversion plant in Paducah. Workers inspect cylinders containing depleted uranium hexafluoride. Workers inspect cylinders containing depleted uranium hexafluoride. The operating room at

  19. EIS-0283-SA-03: Supplement Analysis | Department of Energy

    Energy Savers [EERE]

    Analysis Transportation of Depleted Uranium Hexafluoride for Conversion to Depleted Uranium Oxide This SA evaluates a proposal to transport cylinders of DUF from the Paducah...

  20. Adventures on the C3H5O potential energy surface: OH + propyne OH + allene and related reactions

    Office of Scientific and Technical Information (OSTI)

    Adventures on the C 3 H 5 O potential energy surface: OH + propyne, OH + allene and related reactions Judit Zádor 1 *, James A. Miller 2 1 Combustion Research Facility, Mail Stop 9055, Sandia National Laboratories, Livermore, CA 94551-0969, USA 2 Chemistry Division, Argonne National Laboratory, Argonne, IL 60439, USA *Corresponding author's mailing address: Combustion Research Facility, Mail Stop 9055, Sandia National Laboratories, Livermore, CA 94551-0969 USA Fax: +1 (925) 294-2276 email: