National Library of Energy BETA

Sample records for 2 glenwood pu

  1. Glenwood Springs Vapor Caves Pool & Spa Low Temperature Geothermal...

    Open Energy Info (EERE)

    & Spa Low Temperature Geothermal Facility Jump to: navigation, search Name Glenwood Springs Vapor Caves Pool & Spa Low Temperature Geothermal Facility Facility Glenwood Springs...

  2. Glenwood Hot Springs Hotel Pool & Spa Low Temperature Geothermal...

    Open Energy Info (EERE)

    Hotel Pool & Spa Low Temperature Geothermal Facility Jump to: navigation, search Name Glenwood Hot Springs Hotel Pool & Spa Low Temperature Geothermal Facility Facility Glenwood...

  3. Glenwood Springs Amendments | Open Energy Information

    Open Energy Info (EERE)

    2002 DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Glenwood Springs Amendments Citation BLM Colorado River Valley Field Office...

  4. Glenwood Springs Resource Management Plan (1984) | Open Energy...

    Open Energy Info (EERE)

    Resource Management Plan (1984) Jump to: navigation, search OpenEI Reference LibraryAdd to library Land Use Plan: Glenwood Springs Resource Management Plan (1984) Organization BLM...

  5. Glenwood Hot Springs Lodge Space Heating Low Temperature Geothermal...

    Open Energy Info (EERE)

    Lodge Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Glenwood Hot Springs Lodge Space Heating Low Temperature Geothermal Facility Facility...

  6. City of Glenwood Springs, Colorado (Utility Company) | Open Energy...

    Open Energy Info (EERE)

    Springs City of Place: Colorado Phone Number: 970-384-6352 or 970-625-8095 Website: www.ci.glenwood-springs.co.us Outage Hotline: 970-384-6352 or 970-625-8095 References: EIA...

  7. Glenwood Springs Teacher Recognized for Renewable Energy Efforts - News

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

    Releases | NREL Glenwood Springs Teacher Recognized for Renewable Energy Efforts November 21, 2008 Students taking science classes at Yampah Mountain High School in Glenwood Springs, Colo., are learning about energy efficiency and renewable energy in a hands-on way. The students are learning about energy issues within their school and community through direct development and design of energy projects that benefit their school. Susy Ellison, a science teacher at Yampah Mountain High School,

  8. 238PuO2 Fuel and Dosimetry (Technical Report) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Technical Report: 238PuO2 Fuel and Dosimetry Citation Details In-Document Search Title: 238PuO2 Fuel and Dosimetry 238Pu is an ideal material for use as a heat source with its ...

  9. Internal Corrosion Analysis of Model 9975 Packaging Containing Pu or PuO{sub 2} During Shipping and Storage

    SciTech Connect (OSTI)

    Vormelker, P.

    1999-03-23

    The Materials Consultation Group of SRTC has completed an internal corrosion analysis of the Model 9975 packaging assembly containing either Pu or PuO2 for storage in K Reactor under ambient conditions for a period of 12 years. The 12-year storage period includes two years for shipping and up to ten years for storage.

  10. AFS-2 FLOWSHEET MODIFICATIONS TO ADDRESS THE INGROWTH OF PU(VI) DURING METAL DISSOLUTION

    SciTech Connect (OSTI)

    Crapse, K.; Rudisill, T.; O'Rourke, P.; Kyser, E.

    2014-07-02

    In support of the Alternate Feed Stock Two (AFS-2) PuO{sub 2} production campaign, Savannah River National Laboratory (SRNL) conducted a series of experiments concluding that dissolving Pu metal at 95°C using a 6–10 M HNO{sub 3} solution containing 0.05–0.2 M KF and 0–2 g/L B could reduce the oxidation of Pu(IV) to Pu(VI) as compared to dissolving Pu metal under the same conditions but at or near the boiling temperature. This flowsheet was demonstrated by conducting Pu metal dissolutions at 95°C to ensure that PuO{sub 2} solids were not formed during the dissolution. These dissolution parameters can be used for dissolving both Aqueous Polishing (AP) and MOX Process (MP) specification materials. Preceding the studies reported herein, two batches of Pu metal were dissolved in the H-Canyon 6.1D dissolver to prepare feed solution for the AFS-2 PuO{sub 2} production campaign. While in storage, UV-visible spectra obtained from an at-line spectrophotometer indicated the presence of Pu(VI). Analysis of the solutions also showed the presence of Fe, Ni, and Cr. Oxidation of Pu(IV) produced during metal dissolution to Pu(VI) is a concern for anion exchange purification. Anion exchange requires Pu in the +4 oxidation state for formation of the anionic plutonium(IV) hexanitrato complex which absorbs onto the resin. The presence of Pu(VI) in the anion feed solution would require a valence adjustment step to prevent losses. In addition, the presence of Cr(VI) would result in absorption of chromate ion onto the resin and could limit the purification of Pu from Cr which may challenge the purity specification of the final PuO{sub 2} product. Initial experiments were performed to quantify the rate of oxidation of Pu(IV) to Pu(VI) (presumed to be facilitated by Cr(VI)) as functions of the HNO{sub 3} concentration and temperature in simulated dissolution solutions containing Cr, Fe, and Ni. In these simulated Pu dissolutions studies, lowering the temperature from near boiling

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

    DOE Patents [OSTI]

    Tomczuk, Z.; Miller, W.E.

    1992-01-01

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

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

    DOE Patents [OSTI]

    Tomczuk, Zygmunt; Miller, William E.

    1994-01-01

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

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

    DOE Patents [OSTI]

    Tomczuk, Z.; Miller, W.E.

    1994-10-18

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

  14. Municipal geothermal heat utilization plan for Glenwood Springs, Colorado

    SciTech Connect (OSTI)

    Not Available

    1980-12-31

    A study has been made of the engineering and economic feasibility of utilizing the geothermal resource underlying Glenwood Springs Colorado, to heat a group of public buildings. The results have shown that the use of geothermal heat is indeed feasible when compared to the cost of natural gas. The proposed system is composed of a wellhead plate heat exchanger which feeds a closed distribution loop of treated water circulated to the buildings which form the load. The base case system was designed to supply twice the demand created by the seven public buildings in order to take advantage of some economies of scale. To increase the utilization factor of the available geothermal energy, a peaking boiler which burns natural gas is recommended. Disposal of the cooled brine would be via underground injection. Considerable study was done to examine the impact of reduced operating temperature on the existing heating systems. Several options to minimize this problem were identified. Economic analyses were completed to determine the present values of heat from the geothermal system and from the present natural gas over a 30 year projected system life. For the base case savings of over $1 million were shown. Sensitivities of the economics to capital cost, operating cost, system size and other parameters were calculated. For all reasonable assumptions, the geothermal system was cheaper. Financing alternatives were also examined. An extensive survey of all existing data on the geology of the study has led to the prediction of resource parameters. The wellhead temperature of produced fluid is suspected to lie between 140 and 180/sup 0/F (60 and 82/sup 0/C). Flowrates may be as high as 1000 gpm (3800 liters per minute) from a reservoir formation that is 300 ft (90 m) thick beginning about 500 ft (150 m) below the suggested drill site in the proposed Two Rivers Park.

  15. Characterization of high-fired PuO/sub 2/ as a certified reference material

    SciTech Connect (OSTI)

    Legeled, M.A.; Cacic, C.G.; Crawford, D.W.; Spaletto, M.I.

    1984-07-01

    The New Brunswick Laboratory (NBL), U.S. Department of Energy, has certified a plutonium dioxide reference material, CRM 122, for plutonium assay and isotopic composition. The PuO/sub 2/ standard, one of several certified Pu reference materials currently being developed at NBL for use in instrumentation calibration and measurement control for safeguards, establishes traceability to the national measurement base. This plutonium reference material in the oxide form provides more directly demonstrable traceability than metal because it undergoes the same chemical treatment for dissolution as PuO/sub 2/ fuel materials. Various tests for achieving a constant weight and for dissolving CRM 122 high-fired PuO/sub 2/ were conducted. Results of these tests as well as the certification data generated by controlled-potential coulometry for plutonium assay and by thermal ionization mass spectrometry for isotopic composition will also be presented and discussed.

  16. La-oxides as tracers for PuO{sub 2} to simulate contaminated aerosol behavior

    SciTech Connect (OSTI)

    Meyer, L.C.; Newton, G.J.; Cronenberg, A.W.; Loomis, G.G.

    1994-04-01

    An analytical and experimental study was performed on the use of lanthanide oxides (La-oxides) as surrogates for plutonium oxides (PuO{sub 2}) during simulated buried waste retrieval. This study determined how well the La-oxides move compared to PuO{sub 2} in aerosolized soils during retrieval scenarios. As part of the analytical study, physical properties of La-oxides and PuO{sub 2}, such as molecular diameter, diffusivity, density, and molecular weight are compared. In addition, an experimental study was performed in which Idaho National Engineering Laboratory (INEL) soil, INEL soil with lanthanides, and INEL soil with plutonium were aerosolized and collected in filters. Comparison of particle size distribution parameters from this experimental study show similarity between INEL soil, INEL soil with lanthanides, and INEL soil with plutonium.

  17. Hematological responses after inhaling {sup 238}PuO{sub 2}: An extrapolation from beagle dogs to humans

    SciTech Connect (OSTI)

    Scott, B.R.; Muggenburg, B.A.; Welsh, C.A.; Angerstein, D.A.

    1994-11-01

    The alpha emitter plutonium-238 ({sup 238}Pu), which is produced in uranium-fueled, light-water reactors, is used as a thermoelectric power source for space applications. Inhalation of a mixed oxide form of Pu is the most likely mode of exposure of workers and the general public. Occupational exposures to {sup 238}PuO{sub 2} have occurred in association with the fabrication of radioisotope thermoelectric generators. Organs and tissue at risk for deterministic and stochastic effects of {sup 238}Pu-alpha irradiation include the lung, liver, skeleton, and lymphatic tissue. Little has been reported about the effects of inhaled {sup 238}PuO{sub 2} on peripheral blood cell counts in humans. The purpose of this study was to investigate hematological responses after a single inhalation exposure of Beagle dogs to alpha-emitting {sup 238}PuO{sub 2} particles and to extrapolate results to humans.

  18. Ostwald Ripening and Its Effect on PuO2 Particle Size in Hanford Tank Waste

    SciTech Connect (OSTI)

    Delegard, Calvin H.

    2011-09-29

    Between 1944 and 1989, the Hanford Site produced 60 percent (54.5 metric tons) of the United States weapons plutonium and produced an additional 12.9 metric tons of fuels-grade plutonium. High activity wastes, including plutonium lost from the separations processes used to isolate the plutonium, were discharged to underground storage tanks during these operations. Plutonium in the Hanford tank farms is estimated to be {approx}700 kg but may be up to {approx}1000 kg. Despite these apparent large quantities, the average plutonium concentration in the {approx}200 million liter tank waste volume is only about 0.003 grams per liter ({approx}0.0002 wt%). The plutonium is largely associated with low solubility metal hydroxide/oxide sludges where its low concentration and intimate mixture with neutron-absorbing elements (e.g., iron) are credited in nuclear criticality safety. However, concerns have been expressed that plutonium, in the form of plutonium hydrous oxide, PuO{sub 2} {center_dot} xH{sub 2}O, could undergo sufficient crystal growth through Ostwald ripening in the alkaline tank waste to potentially be separable from neutron absorbing constituents by settling or sedimentation. It was found that plutonium that entered the alkaline tank waste by precipitation through neutralization from acid solution is initially present as 2- to 3-nm (0.002- to 0.003-{mu}m) scale PuO{sub 2} {center_dot} xH{sub 2}O crystallite particles and grows from that point at exceedingly slow rates, posing no risk to physical segregation. These conclusions are reached by both general considerations of Ostwald ripening and specific observations of the behaviors of PuO{sub 2} and PuO{sub 2} {center_dot} xH{sub 2}O upon aging in alkaline solution.

  19. Thermophysical properties of α−Pu{sub 2}O{sub 3}: A new potential model

    SciTech Connect (OSTI)

    Günay, S. D. Akdere, Ü.; Taşseven, Ç.; Akgenç, B.

    2013-12-16

    α−Pu{sub 2}O{sub 3} is an important material among plutonium based materials in nuclear industry. Pure plutonium surfaces quickly oxidizes into α−Pu{sub 2}O{sub 3} and PuO{sub 2} which are in the form of layers one on another. Here we have investigated thermal properties of α−Pu{sub 2}O{sub 3} by molecular dynamics simulation by using a partially ionic semi-empirical rigid ion potential. Mechanical properties, thermal expansion, and heat capacity are calculated. Results were compared with available experimental data and quantum calculation [2]. Due to the experimental limitations such as toxicity and radiation effects, studying the physical properties of such materials from molecular dynamics simulations have vital importance.

  20. The Solubility of 242PuO2 in the Presence of Aqueous Fe(II): The Impact of Precipitate Preparation

    SciTech Connect (OSTI)

    Felmy, Andrew R.; Moore, Dean A.; Buck, Edgar C.; Conradson, Steven D.; Kukkadapu, Ravi K.; Sweet, Lucas E.; Abrecht, David G.; Ilton, Eugene S.

    2014-01-28

    The solubility of different forms of precipitated 242PuO2(am) were examined in solutions containing aqueous Fe(II) over a range of pH values. The first series of 242PuO2(am) suspensions were prepared from a 242Pu(IV) stock that had been treated with thenoyltrifluoroacetone (TTA) to remove the 241Am originating from the decay of 241Pu. These 242PuO2(am) suspensions showed much higher solubilities at the same pH value and Fe(II) concentration than previous studies using 239PuO2(am). X ray absorption fine structure (XAFS) spectroscopy of the precipitates showed a substantially reduced Pu-Pu backscatter over that previously observed in 242PuO2(am) precipitates, indicating that the 242PuO2(am) precipitates purified using TTA lacked the long range order previously found in 239PuO2(am) precipitates. The Pu(IV) stock solution was subsequently repurified using an ion exchange resin and an additional series of 242PuO2(am) precipitates prepared. These suspensions showed higher redox potentials and total aqueous Pu concentrations than the TTA purified stock solution. The higher redox potential and aqueous Pu concentrations were in general agreement with previous studies on 242PuO2(am) precipitates, presumably due to the removal of possible organic compounds originally present in the TTA purified stock. 242PuO2(am) suspensions prepared with both stock solutions showed almost identical solubilities in Fe(II) containing solutions even though the initial aqueous Pu concentrations before the addition of Fe(II) were orders of magnitude different. By examining the solubility of 242PuO2(am) prepared from both stocks in this way we have essentially approached equilibrium from both the undersaturated and oversaturated

  1. The South Canon Number 1 Coal Mine fire: Glenwood Springs, Colorado

    SciTech Connect (OSTI)

    Glenn B. Stracher; Steven Renner; Gary Colaizzi; Tammy P. Taylor

    2004-07-01

    The South Canon Number 1 Coal Mine fire, in South Canyon west of Glenwood Springs, Colorado, is a subsurface fire of unknown origin, burning since 1910. Subsidence features, gas vents, ash, condensates, and red oxidized shales are surface manifestations of the fire. The likely success of conventional fire-containment methodologies in South Canyon is questionable, although drilling data may eventually suggest a useful control procedure. Drill casings in voids in the D coal seam on the western slope trail are useful for collecting gas samples, monitoring the temperature of subsurface burning, and measuring the concentration of gases such as carbon monoxide and carbon dioxide in the field. Coal fire gas and mineral condensates may contribute to the destruction of floral and faunal habitats and be responsible for a variety of human diseases; hence, the study of coal gas and its condensation products may prove useful in understanding environmental pollution created by coal mine fires. The 2002 Coal Seam Fire, which burned over 12,000 acres and destroyed numerous buildings in and around Glenwood Springs, exemplifies the potential danger an underground coal fire poses for igniting a surface fire.

  2. DOE plutonium disposition study: Pu consumption in ALWRs. Volume 2, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

  3. Stability constants important to the understanding of plutonium in environmental waters, hydroxy and carbonate complexation of PuO{sub 2}{sup +}

    SciTech Connect (OSTI)

    Bennett, D A

    1990-04-20

    The formation constants for the reactions PuO{sub 2}{sup +} + H{sub 2}O = PuO{sub 2}(OH) + H{sup +} and PuO{sub 2}{sup +} + CO{sub 3}{sup 2} = PuO{sub 2}(CO{sub 3}){sup {minus}} were determined in aqueous sodium perchlorate solutions by laser-induced photoacoustic spectroscopy. The molar absorptivity of the PuO{sub 2}{sup +} band at 569 nm decreased with increasing hydroxide concentration. Similarly, spectral changes occurred between 540 and 580 nm as the carbonate concentration was increased. The absorption data were analyzed by the non-linear least-squares program SQUAD to yield complexation constants. Using the specific ion interaction theory, both complexation constants were extrapolated to zero ionic strength. These thermodynamic complexation constants were combined with the oxidation-reduction potentials of Pu to obtain Eh versus pH diagrams. 120 refs., 35 figs., 12 tabs.

  4. A comment on the thermal conductivity of (U,Pu)O2 and (U,Th)O2 by molecular dynamics with adjustment for phonon-spin scattering

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

    Cooper, Michael William D.; Liu, Xiang -Yang; Stanek, Christopher Richard; Andersson, David Anders

    2016-07-15

    In this study, a new approach for adjusting molecular dynamics results on UO2 thermal conductivity to include phonon-spin scattering has been used to improve calculations on Ux Pu1–x O2 and UxTh1xO2. We demonstrate that by including spin scattering a strong asymmetry as a function of uranium actinide fraction, x, is obtained. Greater degradation is shown for UxTh1–xO2 than UxPu1-xO2. Minimum thermal conductivities are predicted at U0.97Pu0.03O2 and U0.58Th0.42O2, although the degradation in UxPu1–xO2 is negligible relative to pure UO2.

  5. Structure, phase transitions, and isotope effects in [(CH3)4N]2PuCl6

    SciTech Connect (OSTI)

    Wilson, Richard E.

    2015-11-02

    The single crystal X-ray diffraction structure of [(CH3)4N]2PuCl6 is presented for the first time, resolving long standing confusion and speculation regarding the structure of this compound in the literature. A temperature dependent study of this compound shows that the structure of [(CH3)4N]2PuCl6 undergoes no fewer than two phase transitions between 100 and 360 K. The phase of [(CH3)4N]2PuCl6 at room temperature is Fd-3c a = 26.012(3) Å. At 360 K, the structure is in space group Fm-3m with a = 13.088(1) Å. The plutonium octahedra and tetramethylammonium cations undergo a rotative displacement and the degree of rotation varies with temperature, giving rise to the phase transition from Fm-3m to Fd-3c as the crystal is cooled. Synthesis and structural studies of the deuterated salt [(CD3)4N]2PuCl6 suggest that there is an isotopic effect associated with this phase transition as revealed by a changing transition temperature in the deuterated versus protonated compound indicating that the donor-acceptor interactions between the tetramethylammonium cations and the hexachloroplutonate anions are driving the phase transformation.

  6. Effects of Aging on PuO2?xH2O Particle Size in Alkaline Solution

    SciTech Connect (OSTI)

    Delegard, Calvin H.

    2013-05-01

    Between 1944 and 1989, 54.5 metric tons of the United States weapons-grade plutonium and an additional 12.9 metric tons of fuel-grade plutonium were produced and separated from irradiated fuel at the Hanford Site. Acidic high-activity wastes containing around 600 kg of plutonium were made alkaline and discharged to underground storage tanks from separations, isolation, and recycle processes to yield average plutonium concentration of about 0.003 grams per liter (or ~0.0002 wt%) in the ~200 million liter tank waste volume. The plutonium is largely associated with low-solubility metal hydroxide/oxide sludges where its low concentration and intimate mixture with neutron-absorbing elements (e.g., iron) are credited in nuclear criticality safety. However, concerns have been expressed that plutonium, in the form of plutonium hydrous oxide, PuO2?xH2O, could undergo sufficient crystal growth through dissolution and reprecipitation in the alkaline tank waste to potentially become separable from neutron absorbing constituents by settling or sedimentation. Thermodynamic considerations and laboratory studies of systems chemically analogous to tank waste show that the plutonium formed in the alkaline tank waste by precipitation through neutralization from acid solution probably entered as 24-nm PuO2?xH2O crystallite particles that, because of their low solubility and opposition from radiolytic processes, grow from that point at exceedingly slow rates, thus posing no risk of physical segregation.

  7. Modeling of selected ceramic processing parameters employed in the fabrication of 238PuO2 fuel pellets

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

    Brockman, R. A.; Kramer, D. P.; Barklay, C. D.; Cairns-Gallimore, D.; Brown, J. L.; Huling, J. C.; Van Pelt, C. E.

    2011-10-01

    Recent deep space missions utilize the thermal output of the radioisotope plutonium-238 as the fuel in the thermal to electrical power system. Since the application of plutonium in its elemental state has several disadvantages, the fuel employed in these deep space power systems is typically in the oxide form such as plutonium-238 dioxide (238PuO2). As an oxide, the processing of the plutonium dioxide into fuel pellets is performed via ''classical'' ceramic processing unit operations such as sieving of the powder, pressing, sintering, etc. Modeling of these unit operations can be beneficial in the understanding and control of processing parameters withmore » the goal of further enhancing the desired characteristics of the 238PuO2 fuel pellets. A finite element model has been used to help identify the time-temperature-stress profile within a pellet during a furnace operation taking into account that 238PuO2 itself has a significant thermal output. The results of the modeling efforts will be discussed.« less

  8. Modelling the thermal conductivity of (UxTh1-x)O2 and (UxPu1-x)O2

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

    Cooper, M. W. D.; Middleburgh, S. C.; Grimes, R. W.

    2015-07-15

    The degradation of thermal conductivity due to the non-uniform cation lattice of (UxTh1-x)O2 and (UxPu1-x)O2 solid solutions has been investigated by molecular dynamics, using the non-equilibrium method, from 300 to 2000 K. Degradation of thermal conductivity is predicted in (UxTh1-x)O2 and (UxPu1-x)O2 as compositions deviate from the pure end members: UO2, PuO2 and ThO2. The reduction in thermal conductivity is most apparent at low temperatures where phonon-defect scattering dominates over phonon-phonon interactions. The effect is greater for (UxTh1-x)O2 than UxPu1-x)O2 due to the greater mismatch in cation size. Parameters for an analytical expressions have been developed that describe the predictedmore » thermal conductivities over the full temperature and compositional ranges. Finally, these expressions may be used in higher level fuel performance codes.« less

  9. Properties measurements of (U{sub 0.7}Pu{sub 0.3})O{sub 2-x} in PO{sub 2}-controlled atmosphere

    SciTech Connect (OSTI)

    Kato, M.; Murakami, T.; Sunaoshi, T.; Nelson, A.T.; McClellan, K.J.

    2013-07-01

    The investigation of physical properties of uranium and plutonium mixed oxide (MOX) fuels is important for the development of fast reactor fuels. It is well known that MOX is a nonstoichiometric oxide, and the physical properties change drastically with the Oxygen-to-Metal (O/M) ratio. A control technique for O/M ratio was established for measurements of high temperature properties of uranium and plutonium mixed oxide fuels. Sintering behavior, thermal expansion and O/M change of (U{sub 0.7}Pu{sub 0.3})O{sub 2.00} and (U{sub 0.7}Pu{sub 0.3})O{sub 1.99} were investigated in PO{sub 2}-controlled atmosphere which was controlled by H{sub 2}/H{sub 2}O gas system. Sintering behavior changed drastically with O/M ratio, and shrinkage of (U{sub 0.7}Pu{sub 0.3})O{sub 2.00} was faster and more advanced at lower temperatures as compared with (U{sub 0.7}Pu{sub 0.3})O{sub 1.99}. Thermal expansion was observed to be slightly increased with decreasing O/M ratio. (authors)

  10. Commentary on Inhaled 239PuO2 in Dogs — A Prophylaxis against Lung Cancer?

    SciTech Connect (OSTI)

    Cuttler, Jerry M.; Feinendegen, Ludwig E.

    2015-01-01

    Several studies on the effect of inhaled plutonium-dioxide particulates and the incidence of lung tumors in dogs reveal beneficial effects when the cumulative alpha-radiation dose is low. There is a threshold at an exposure level of about 100 cGy for excess tumor incidence and reduced lifespan. The observations conform to the expectations of the radiation hormesis dose-response model and contradict the predictions of the LNT hypothesis. These studies suggest investigating the possibility of employing low-dose alpha-radiation, such as from 239PuO2 inhalation, as a prophylaxis against lung cancer.

  11. Decontamination of soils and materials containing medium-fired PuO{sub 2} using inhibited fluorides with polymer filtration technology

    SciTech Connect (OSTI)

    Temer, D.J.; Villarreal, R.; Smith, B.F.

    1997-10-01

    The decontamination of soils and/or materials from medium-fired plutonium oxide (PuO{sub 2}) with an effective and efficient decontamination agent that will not significantly dissolve the matrix requires a new and innovative technology. After testing several decontamination agents and solutions for dissolution of medium-fired PuO{sub 2}, the most successful decontamination solutions were fluoride compounds, which were effective in breaking the Pu-oxide bond but would not extensively dissolve soil constituents and other materials. The fluoride compounds, tetra fluoboric acid (HBF{sub 4}) and hydrofluorosilicic acid (H{sub 2}F{sub 6}Si), were effective in dissolving medium-fired PuO{sub 2}, and did not seem to have the potential to dissolve the matrix. In both compounds, the fluoride atom is attached to a boron or silicon atom that inhibits the reactivity of the fluoride towards other compounds or materials containing atoms less attracted to the fluoride atom in an acid solution. Because of this inhibition of the reactivity of the fluoride ion, these compounds are termed inhibited fluoride compounds or agents. Both inhibited fluorides studied effectively dissolved medium-fired PuO{sub 2} but exhibited a tendency to not attack stainless steel or soil. The basis for selecting inhibited fluorides was confirmed during leaching tests of medium-fired PuO{sub 2} spiked into soil taken from the Idaho National Engineering Laboratory (INEL). When dissolved in dilute HNO{sub 3}, HCl, or HBr, both inhibited fluoride compounds were effective at solubilizing the medium-fired PuO{sub 2} from spiked INEL soil.

  12. Ir/PuO/sub 2/ compatibility: transfer of impurities from plutonium dioxide to iridium metal during high temperature aging

    SciTech Connect (OSTI)

    Taylor, D.H.; Christie, W.H.; Pavone, D.

    1984-01-01

    Plutonium oxide fuel pellets for powering radioisotopic thermoelectric generators for NASA space vehicles are encapsulated in iridium which has been grain-boundary-stabilized with thorium and aluminum. After aging for 6 months at 1310/sup 0/C under vacuum, enhanced grain growth is observed in the near-surface grains of the iridium next to the PuO/sub 2/. Examination of the grain boundaries by AES and SIMS shows a depletion of thorium and aluminum. Iron, chromium, and nickel from the fuel were found to diffuse into the iridium along the grain boundaries. Enhanced grain growth appears to result from thorium depletion in the grain boundaries of the near-surface grains next to the fuel. However, in one instance grain growth was slowed by the formation of thorium oxide by oxygen diffusing up the grain boundaries.

  13. Theoretical aspects of the magnetism in the ferromagnetic A Fe sub 2 systems ( A =U, Np, Pu, and Am)

    SciTech Connect (OSTI)

    Eriksson, O.; Johansson, B. ); Brooks, M.S.S. )

    1990-05-01

    We report on spin-polarized energy-band calculations for the cubic Laves-phase systems UFe{sub 2}, NpFe{sub 2}, PuFe{sub 2}, and AmFe{sub 2}. The calculations were performed with the local-density approximation for the exchange and correlation potential together with a term that shifts the one-electron eigenvalues and takes into account the different interelectronic repulsions for electrons with different 5{ital f} magnetic quantum numbers. The spin-orbit interaction was also included in the band Hamiltonian. Thus the parameter-free calculations incorporate Hund's first, second, and third rules. The magnetism in the first three compounds was found to be dominated by a large orbital contribution coupled antiparallel to the spin moment. In the calculations for AmFe{sub 2}, the 5{ital f} electrons were treated as core electrons. The magnetism was here found to behave very much like the magnetism of similar rare-earth Laves-phase compounds.

  14. The thermal conductivity of mixed fuel UxPu1-xO2: molecular dynamics simulations

    SciTech Connect (OSTI)

    Liu, Xiang-Yang; Cooper, Michael William Donald; Stanek, Christopher Richard; Andersson, Anders David Ragnar

    2015-10-16

    Mixed oxides (MOX), in the context of nuclear fuels, are a mixture of the oxides of heavy actinide elements such as uranium, plutonium and thorium. The interest in the UO2-PuO2 system arises from the fact that these oxides are used both in fast breeder reactors (FBRs) as well as in pressurized water reactors (PWRs). The thermal conductivity of UO2 fuel is an important material property that affects fuel performance since it is the key parameter determining the temperature distribution in the fuel, thus governing, e.g., dimensional changes due to thermal expansion, fission gas release rates, etc. For this reason it is important to understand the thermal conductivity of MOX fuel and how it differs from UO2. Here, molecular dynamics (MD) simulations are carried out to determine quantitatively, the effect of mixing on the thermal conductivity of UxPu1-xO2, as a function of PuO2 concentrations, for a range of temperatures, 300 – 1500 K. The results will be used to develop enhanced continuum thermal conductivity models for MARMOT and BISON by INL. These models express the thermal conductivity as a function of microstructure state-variables, thus enabling thermal conductivity models with closer connection to the physical state of the fuel.

  15. Static electric dipole polarizabilities of An{sup 5+/6+} and AnO{sub 2}{sup +/2+} (An = U, Np, and Pu) ions

    SciTech Connect (OSTI)

    Parmar, Payal E-mail: kipeters@wsu.edu Peterson, Kirk A. E-mail: kipeters@wsu.edu; Clark, Aurora E. E-mail: kipeters@wsu.edu

    2014-12-21

    The parallel components of static electric dipole polarizabilities have been calculated for the lowest lying spin-orbit states of the penta- and hexavalent oxidation states of the actinides (An) U, Np, and Pu, in both their atomic and molecular diyl ion forms (An{sup 5+/6+} and AnO{sub 2}{sup +/2+}) using the numerical finite-field technique within a four-component relativistic framework. The four-component Dirac-Hartree-Fock method formed the reference for MP2 and CCSD(T) calculations, while multireference Fock space coupled-cluster (FSCC), intermediate Hamiltonian Fock space coupled-cluster (IH-FSCC) and Kramers restricted configuration interaction (KRCI) methods were used to incorporate additional electron correlation. It is observed that electron correlation has significant (?5 a.u.{sup 3}) impact upon the parallel component of the polarizabilities of the diyls. To the best of our knowledge, these quantities have not been previously reported and they can serve as reference values in the determination of various electronic and response properties (for example intermolecular forces, optical properties, etc.) relevant to the nuclear fuel cycle and material science applications. The highest quality numbers for the parallel components (?{sub zz}) of the polarizability for the lowest ? levels corresponding to the ground electronic states are (in a.u.{sup 3}) 44.15 and 41.17 for UO{sub 2}{sup +} and UO{sub 2}{sup 2+}, respectively, 45.64 and 41.42 for NpO{sub 2}{sup +} and NpO{sub 2}{sup 2+}, respectively, and 47.15 for the PuO{sub 2}{sup +} ion.

  16. Modeling of selected ceramic processing parameters employed in the fabrication of 238PuO2 fuel pellets

    SciTech Connect (OSTI)

    Brockman, R. A.; Kramer, D. P.; Barklay, C. D.; Cairns-Gallimore, D.; Brown, J. L.; Huling, J. C.; Van Pelt, C. E.

    2011-10-01

    Recent deep space missions utilize the thermal output of the radioisotope plutonium-238 as the fuel in the thermal to electrical power system. Since the application of plutonium in its elemental state has several disadvantages, the fuel employed in these deep space power systems is typically in the oxide form such as plutonium-238 dioxide (238PuO2). As an oxide, the processing of the plutonium dioxide into fuel pellets is performed via ''classical'' ceramic processing unit operations such as sieving of the powder, pressing, sintering, etc. Modeling of these unit operations can be beneficial in the understanding and control of processing parameters with the goal of further enhancing the desired characteristics of the 238PuO2 fuel pellets. A finite element model has been used to help identify the time-temperature-stress profile within a pellet during a furnace operation taking into account that 238PuO2 itself has a significant thermal output. The results of the modeling efforts will be discussed.

  17. Method of removing Pu(IV) polymer from nuclear fuel reclaiming liquid

    DOE Patents [OSTI]

    Tallent, Othar K.; Mailen, James C.; Bell, Jimmy T.; Arwood, Phillip C.

    1982-01-01

    A Pu(IV) polymer not extractable from a nuclear fuel reclaiming solution by conventional processes is electrolytically converted to Pu.sup.3+ and PuO.sub.2.sup.2+ ions which are subsequently converted to Pu.sup.4+ ions extractable by the conventional processes.

  18. Radiolysis of Salts and Long-Term Storage Issues for Both Pure and Impure PuO{sub 2} Materials in Plutonium Storage Containers

    SciTech Connect (OSTI)

    Lav Tandon

    2000-05-01

    The Material Identification and Surveillance (MIS) project sponsored a literature search on the effects of radiation on salts, with focus on alkali chlorides. The goal of the survey was to provide a basis for estimating the magnitude of {alpha} radiation effects on alkali chlorides that can accompany plutonium oxide (PuO{sub 2}) into storage. Chloride radiolysis can yield potentially corrosive gases in plutonium storage containers that can adversely affect long-term stability. This literature search was primarily done to provide a tutorial on this topic, especially for personnel with nonradiation chemistry backgrounds.

  19. Pu Qian | Photosynthetic Antenna Research Center

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

    Pu Qian Pu Qian placeholder image Pu Qian Postdoctoral Associate E-mail: p.qian@sheffield.ac.uk Postdoctoral Associates

  20. High-silicon {sup 238}PuO{sub 2} fuel characterization study: Half module impact tests

    SciTech Connect (OSTI)

    Reimus, M.A.H.

    1997-01-01

    The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of [sup 238]Pu decay to an array of thermoelectric elements. The modular GPHS design was developed to address both survivability during launch abort and return from orbit. Previous testing conducted in support of the Galileo and Ulysses missions documented the response of GPHSs to a variety of fragment- impact, aging, atmospheric reentry, and Earth-impact conditions. The evaluations documented in this report are part of an ongoing program to determine the effect of fuel impurities on the response of the heat source to conditions baselined during the Galileo/Ulysses test program. In the first two tests in this series, encapsulated GPHS fuel pellets containing high levels of silicon were aged, loaded into GPHS module halves, and impacted against steel plates. The results show no significant differences between the response of these capsules and the behavior of relatively low-silicon fuel pellets tested previously.

  1. Program Pu Futures 2006

    SciTech Connect (OSTI)

    Fluss, M

    2006-06-12

    The coordination chemistry of plutonium remains relatively unexplored. Thus, the fundamental coordination chemistry of plutonium is being studied using simple multi-dentate ligands with the intention that the information gleaned from these studies may be used in the future to develop plutonium-specific sequestering agents. Towards this goal, hard Lewis-base donors are used as model ligands. Maltol, an inexpensive natural product used in the commercial food industry, is an ideal ligand because it is an all-oxygen bidentate donor, has a rigid structure, and is of small enough size to impose little steric strain, allowing the coordination preferences of plutonium to be the deciding geometric factor. Additionally, maltol is the synthetic precursor of 3,4-HOPO, a siderophore-inspired bidentate moiety tested by us previously as a possible sequestering agent for plutonium under acidic conditions. As comparisons to the plutonium structure, Ce(IV) complexes of the same and related ligands were examined as well. Cerium(IV) complexes serve as good models for plutonium(IV) structures because Ce(IV) has the same ionic radius as Pu(IV) (0.94 {angstrom}). Plutonium(IV) maltol crystals were grown out of a methanol/water solution by slow evaporation to afford red crystals that were evaluated at the Advanced Light Source at Lawrence Berkeley National Laboratory using single crystal X-ray diffraction. Cerium(IV) complexes with maltol and bromomaltol were crystallized via slow evaporation of the mother liquor to afford tetragonal, black crystals. All three complexes crystallize in space group I4{sub 1}/a. The Ce(IV) complex is isostructural with the Pu(IV) complex, in which donating oxygens adopt a trigonal dodecahedral geometry around the metal with the maltol rings parallel to the crystallographic S{sub 4} axis and lying in a non-crystallographic mirror plane of D{sub 2d} molecular symmetry (Fig 1). The metal-oxygen bonds in both maltol complexes are equal to within 0.04 {angstrom

  2. Pu-bearing materials - from fundamental science to storage standards.

    SciTech Connect (OSTI)

    Tam, S. W.; Liu, Y.; Decision and Information Sciences; Michigan Technical Univ.

    2008-01-01

    The behavior of plutonium (Pu) oxides in the presence of water/moisture in a confined space and the associated issues of hydrogen and oxygen generation due to radiolysis have important implications for the storage and transportation of Pu-bearing materials. This paper reviews the results of recent studies of gas generation in the Pu-O-H system, including the determination of release rates via engineering-scale measurement. The observations of the significant differences in gas generation behavior between 'pure' Pu-bearing materials and those that contain salt impurities are addressed. In conjunction with the discussion of these empirical observations, the work also addresses recent scientific advances in the investigations of the Pu-O-H system using state-of-the-art ab initio electronic structure calculations, as well as advanced synchrotron techniques to determine the electronic structure of the various Pu-containing phases. The role of oxidizing species such as the hydroxyl radical from the radiolysis of water is examined. Discussed also is the challenge in the predictive ab-initio calculations of the electronic structure of the Pu-H-O system, due to the nature of the 5f valence electrons in Pu. Coupled with the continuing material surveillance program, it is anticipated that this work may help determine the electronic structure of the various Pu-containing phases and the role of impurity salts on gas generation and the long-term stability of oxygen/hydrogen-containing plutonium oxides beyond PuO{sub 2}.

  3. Effect of equilibration time on Pu desorption from goethite

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

    Wong, Jennifer C.; Zavarin, Mavrik; Begg, James D.; Kersting, Annie B.; Powell, Brian A.

    2015-01-28

    Strongly sorbing ions such as plutonium may become irreversibly bound to mineral surfaces over time implicates near- and far-field transport of Pu. Batch adsorption–desorption data were collected as a function of time and pH to study the surface stability of Pu on goethite. Pu(IV) was adsorbed to goethite over the pH range 4.2 to 6.6 for different periods of time (1, 6, 15, 34 and 116 d). Moreover, following adsorption, Pu was leached from the mineral surface with desferrioxamine B (DFOB), a complexant capable of effectively competing with the goethite surface for Pu. The amount of Pu desorbed from the goethitemore » was found to vary as a function of the adsorption equilibration time, with less Pu removed from the goethite following longer adsorption periods. This effect was most pronounced at low pH. Logarithmic desorption distribution ratios for each adsorption equilibration time were fit to a pH-dependent model. Model slopes decreased between 1 and 116 d adsorption time, indicating that overall Pu(IV) surface stability on goethite surfaces becomes less dependent on pH with greater adsorption equilibration time. The combination of adsorption and desorption kinetic data suggest that non-redox aging processes affect Pu sorption behavior on goethite.« less

  4. Effect of equilibration time on Pu desorption from goethite

    SciTech Connect (OSTI)

    Wong, Jennifer C.; Zavarin, Mavrik; Begg, James D.; Kersting, Annie B.; Powell, Brian A.

    2015-01-28

    Strongly sorbing ions such as plutonium may become irreversibly bound to mineral surfaces over time implicates near- and far-field transport of Pu. Batch adsorption–desorption data were collected as a function of time and pH to study the surface stability of Pu on goethite. Pu(IV) was adsorbed to goethite over the pH range 4.2 to 6.6 for different periods of time (1, 6, 15, 34 and 116 d). Moreover, following adsorption, Pu was leached from the mineral surface with desferrioxamine B (DFOB), a complexant capable of effectively competing with the goethite surface for Pu. The amount of Pu desorbed from the goethite was found to vary as a function of the adsorption equilibration time, with less Pu removed from the goethite following longer adsorption periods. This effect was most pronounced at low pH. Logarithmic desorption distribution ratios for each adsorption equilibration time were fit to a pH-dependent model. Model slopes decreased between 1 and 116 d adsorption time, indicating that overall Pu(IV) surface stability on goethite surfaces becomes less dependent on pH with greater adsorption equilibration time. The combination of adsorption and desorption kinetic data suggest that non-redox aging processes affect Pu sorption behavior on goethite.

  5. Addendum 2 to CSER 94-007 and CSER 94-008 Title: Burning one whole Pu button in muffle furnace in the HC-21C hood

    SciTech Connect (OSTI)

    Chiao, T., Westinghouse Hanford

    1996-09-24

    This addendum reviews the current CPS` and their supporting CSERs for HC-21A and HC-21C Hoods and provides the criticality safety analysis for burning a whole Pu button in HC-21C.

  6. Elastic properties of Pu metal and Pu-Ga alloys

    SciTech Connect (OSTI)

    Soderlind, P; Landa, A; Klepeis, J E; Suzuki, Y; Migliori, A

    2010-01-05

    We present elastic properties, theoretical and experimental, of Pu metal and Pu-Ga ({delta}) alloys together with ab initio equilibrium equation-of-state for these systems. For the theoretical treatment we employ density-functional theory in conjunction with spin-orbit coupling and orbital polarization for the metal and coherent-potential approximation for the alloys. Pu and Pu-Ga alloys are also investigated experimentally using resonant ultrasound spectroscopy. We show that orbital correlations become more important proceeding from {alpha} {yields} {beta} {yields} {gamma} plutonium, thus suggesting increasing f-electron correlation (localization). For the {delta}-Pu-Ga alloys we find a softening with larger Ga content, i.e., atomic volume, bulk modulus, and elastic constants, suggest a weakened chemical bonding with addition of Ga. Our measurements confirm qualitatively the theory but uncertainties remain when comparing the model with experiments.

  7. Co-operativity among defect sites in AnO2+ and An4O9 (An = U, Np or Pu)

    SciTech Connect (OSTI)

    Andersson, Anders David; Lezama Pacheco, Juan; Uberuaga, Blas P; Conradson, Steven D

    2008-01-01

    Actinide dioxides derived from the AnO{sub 2} fluorite lattice are of high technological relevance due to their application in nuclear reactor fuels. Oxidation of AnO{sub 2} compounds emerges as a central theme in fuel fabrication, reactor operation, long-term storage forms for both spent fuels and surplus weapons materials, and environmental actinide migration. In this paper, we use density functional theory calculations to study the oxidation of uranium, neptunium and plutonium dioxides, AnO{sub 2} (An = U, Np or Pu), in O{sub 2} and O{sub 2}/H{sub 2}O environments. We pay particular attention to the formation of oxygen clusters (co-operativity) in AnO{sub 2+x} and how this phenomenon govern oxidation thermodynamics and the development of ordered An{sub 4}O{sub 9} compounds. The so-called split di-interstitial, which is composed of two nearest neighbor octahedral oxygen interstitials that are distorted in such a way that they dislocate one regular fluorite lattice oxygen ion to form a cluster of triangular geometry, is predicted to be the fundamental building block of the most stable cluster configurations. We also identify how the formation of oxygen defect clusters and the degree of oxidation in AnO{sub 2+x} are both governed by the characer of the An-5f to excess O-2p charger transfer, i.e. the charge transfer to the O-2p orbitals of the interstitial-like (+x) ions, and the ability of the excess O-2p orbitals to hybridize with regular fluorite lattice ions.

  8. Pu Anion Exchange Process Intensification

    SciTech Connect (OSTI)

    Taylor-Pashow, K.

    2015-10-08

    This project seeks to improve the efficiency of the plutonium anion-exchange process for purifying Pu through the development of alternate ion-exchange media. The objective of the project in FY15 was to develop and test a porous foam monolith material that could serve as a replacement for the current anion-exchange resin, Reillex® HPQ, used at the Savannah River Site (SRS) for purifying Pu. The new material provides advantages in efficiency over the current resin by the elimination of diffusive mass transport through large granular resin beads. By replacing the large resin beads with a porous foam there is much more efficient contact between the Pu solution and the anion-exchange sites present on the material. Several samples of a polystyrene based foam grafted with poly(4-vinylpyridine) were prepared and the Pu sorption was tested in batch contact tests.

  9. Economical Production of Pu-238

    SciTech Connect (OSTI)

    Steven D. Howe; Douglas Crawford; Jorge Navarro; Terry Ring

    2013-02-01

    All space exploration missions traveling beyond Jupiter must use radioisotopic power sources for electrical power. The best isotope to power these sources is plutonium-238. The US supply of Pu-238 is almost exhausted and will be gone within the next decade. The Department of Energy has initiated a production program with a $10M allocation from NASA but the cost is estimated at over $100 M to get to production levels. The Center for Space Nuclear Research has conceived of a potentially better process to produce Pu-238 earlier and for significantly less cost. The new process will also produce dramatically less waste. Potentially, the front end costs could be provided by private industry such that the government only had to pay for the product produced. Under a NASA Phase I NIAC grant, the CSNR has evaluated the feasibility of using a low power, commercially available nuclear reactor to produce at least 1.5 kg of Pu-238 per year. The impact on the neutronics of the reactor have been assessed, the amount of Neptunium target material estimated, and the production rates calculated. In addition, the size of the post-irradiation processing facility has been established. In addition, a new method for fabricating the Pu-238 product into the form used for power sources has been identified to reduce the cost of the final product. In short, the concept appears to be viable, can produce the amount of Pu-238 needed to support the NASA missions, can be available within a few years, and will cost significantly less than the current DOE program.

  10. Overview of advanced technologies for stabilization of {sup 238}Pu-contaminated waste

    SciTech Connect (OSTI)

    Ramsey, K.B.; Foltyn, E.M.; Heslop, J.M.

    1998-02-01

    This paper presents an overview of potential technologies for stabilization of {sup 238}Pu-contaminated waste. Los Alamos National Laboratory (LANL) has processed {sup 238}PuO{sub 2} fuel into heat sources for space and terrestrial uses for the past several decades. The 88-year half-life of {sup 238}Pu and thermal power of approximately 0.6 watts/gram make this isotope ideal for missions requiring many years of dependable service in inaccessible locations. However, the same characteristic which makes {sup 238}Pu attractive for heat source applications, the high Curie content (17 Ci/gram versus 0.06 Ci/gram for 239{sup Pu}), makes disposal of {sup 238}Pu-contaminated waste difficult. Specifically, the thermal load limit on drums destined for transport to the Waste Isolation Pilot Plant (WIPP), 0.23 gram per drum for combustible waste, is impossible to meet for nearly all {sup 238}Pu-contaminated glovebox waste. Use of advanced waste treatment technologies including Molten Salt Oxidation (MSO) and aqueous chemical separation will eliminate the combustible matrix from {sup 238}Pu-contaminated waste and recover kilogram quantities of {sup 238}PuO{sub 2} from the waste stream. A conceptual design of these advanced waste treatment technologies will be presented.

  11. DEVELOPMENT PROGRAM FOR PU-238 AQUEOUS RECOVERY PROCESS

    SciTech Connect (OSTI)

    M. PANSOY-HJELVIK; M. REIMUS; ET AL

    2000-10-01

    Aqueous processing is necessary for the removal of impurities from {sup 238}Pu dioxide ({sup 238}PuO{sub 2}) fuel due to unacceptable levels of {sup 234}U and other non-actinide impurities in the scrap fuel. Impurities at levels above General Purpose Heat Source (GPHS) fuel specifications may impair the performance.of the heat sources. Efforts at Los Alamos have focused on developing the bench scale methodology for the aqueous process steps which includes comminution, dissolution, ion exchange, precipitation, and calcination. Recently, work has been performed to qualify the bench scale methodology, to show that the developed process produces pure {sup 238}PuO{sub 2} meeting GPHS fuel specifications. In addition, this work has enabled us to determine how waste volumes may be minimized during full-scale processing. Results of process qualification for the bench scale aqueous recovery operation and waste minimization efforts are presented.

  12. Development of U and Pu Co-Recovery Process (Co-Processing) for Future Reprocessing

    SciTech Connect (OSTI)

    Yamamoto, K.; Yanagibashi, F.; Fujimoto, I.; Sato, T.; Ohbu, T.; Taki, K.; Hayashi, S.

    2013-07-01

    Co-processing process, which is the modified Purex process focused on co-recovery of Pu and U, has been studied at Operation Testing Laboratory, Tokai Reprocessing Plant in JAEA. The set up of the process was performed with flow-sheets study by process calculation to avoid Pu isolation in the whole process and to co-recover Pu/U product solution with a suitable Pu/U ratio (0.5< Pu/U <2). The initial Pu/U ratios of the feed solutions were taken as 1%, 3% and 20% considering the composition of the future spent fuels. The verification of the flow-sheets for each feed solutions were carried out with mixer-setters and active Pu/U feed solutions, focusing on the partitioning unit, and favorable back extraction performances of Pu accompanied by U were observed at all cases of the given feed solutions. According to these results, the co-processing process showed a good prospect to treat all kinds of future fuels from LWR, LWR-MOX and FBR, and a good prospect to be simplified by omitting the Pu/U purification cycle.

  13. Average Structure Evolution of ?-phase Pu-Ga Alloys

    SciTech Connect (OSTI)

    Smith, Alice Iulia; Page, Katharine L.; Gourdon, Olivier; Siewenie, Joan E.; Richmond, Scott; Saleh, Tarik A.; Ramos, Michael; Schwartz, Daniel S.

    2015-03-30

    [Full Text] Plutonium metal is a highly unusual element, exhibiting six allotropes at ambient pressure, from room temperature to its melting point. Many phases of plutonium metal are unstable with temperature, pressure, chemical additions, and time. This strongly affects structure and properties, and becomes of high importance, particularly when considering effects on structural integrity over long time periods. The fcc ?-phase deserves additional attention, not only in the context of understanding the electronic structure of Pu, but also as one of the few high-symmetry actinide phases that can be stabilized down to ambient pressure and room temperature by alloying it with trivalent elements. We will present results on recent work on aging of Pu-2at.%Ga and Pu-7at.%Ga alloys

  14. A=3H (2010PU04)

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

    2010PU04) GENERAL: Ground State: Jπ = 1/2+ μ = 2.978960 ± 0.000001 μN Mass Excess, M - A = 14.9498060 ± 0.0000023 MeV T1/2 = 12.32 ± 0.02 y = 4500 ± 8 days Decay Mode: β- decay Binding Energy, EB = 8.481798 ± 0.000002 MeV Neutron Separation Energy, Sn = 6.257233 ± 0.000002 MeV The ground state wave functions for 3H and 3He consist mainly of a spatially symmetric S state (about 90%), a mixed symmetry S' state (about 1%), a D state (about 9%) and a small P state (less than 0.1%). Some

  15. A=3He (2010PU04)

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

    2010PU04) GENERAL: Ground State: Jπ = 1/2+ μ = -2.127497718 ± 0.000000025 μN Mass Excess, M - A = 14.93121475 ± 0.00000242 MeV Decay Mode: stable Binding Energy, EB = 7.718043 ± 0.000002 MeV Proton Separation Energy, Sp = 5.493478 ± 0.000002 MeV A topic of interest in connection with the mass 3 nuclei is the difference in binding energies of 3H and 3He and the relationship of this difference to charge symmetry breaking (CSB). The binding energy of 3H is larger than that of 3He by a little

  16. Energy Dependence of Fission Product Yields for 239Pu, 235U,...

    Office of Scientific and Technical Information (OSTI)

    Title: Energy Dependence of Fission Product Yields for 239Pu, 235U, and 238U Authors: Tornow, Werner 1 ; Bredeweg, Todd Allen 2 ; Wilhelmy, Jerry B. 2 ; Vieira, David J. 2 ...

  17. Characterization of Pu-238 Heat Source Granule Containment

    SciTech Connect (OSTI)

    Richardson, Paul Dean II; Sanchez, Joey Leo; Wall, Angelique Dinorah; Chavarria, Rene

    2015-02-11

    The Milliwatt Radioisotopic Themoelectric Generator (RTG) provides power for permissive-action links. Essentially these are nuclear batteries that convert thermal energy to electrical energy using a doped silicon-germanium thermopile. The thermal energy is provided by a heat source made of 238Pu, in the form of 238PuO2 granules. The granules are contained by 3 layers of encapsulation. A thin T-111 liner surrounds the 238PuO2 granules and protects the second layer (strength member) from exposure to the fuel granules. An outer layer of Hastalloy-C protects the T-111 from oxygen embrittlement. The T-111 strength member is considered the critical component in this 238PuO2 containment system. Any compromise in the strength member seen during destructive testing required by the RTG surveillance program is characterized. The T-111 strength member is characterized through Scanning Electron Microscopy (SEM), and Metallography. SEM is used in the Secondary Electron mode to reveal possible grain boundary deformation and/or cracking in the region of the strength member weld. Deformation and cracking uncovered by SEM are further characterized by Metallography. Metallography sections are mounted and polished, observed using optical microscopy, then documented in the form of microphotographs. SEM mat further be used to examine polished Metallography mounts to characterize elements using the SEM mode of Energy Dispersive X-ray spectroscopy (EDS).

  18. LLNL Workshop on TEM of Pu

    SciTech Connect (OSTI)

    King, W.E.

    1996-09-10

    On Sept. 10, 1996, LLNL hosted a workshop aimed at answering the question: Is it possible to carry out transmission electron microscopy (TEM) on plutonium metal in an electron microscope located outside the LLNL plutonium facility. The workshop focused on evaluation of a proposed plan for Pu microscopy both from a technical and environment, health, and safety point of view. After review and modification of the plan, workshop participants unanimously concluded that: (1) the technical plan is sound, (2) this technical plan, including a proposal for a new TEM, provides significant improvements and unique capabilities compared with the effort at LANL and is therefore complementary, (3) there is no significant environment, health, and safety obstacle to this plan.

  19. Savannah River Site: Plutonium Preparation Project (PuPP) at...

    Energy Savers [EERE]

    Site: Plutonium Preparation Project (PuPP) at Savannah River Site Savannah River Site: Plutonium Preparation Project (PuPP) at Savannah River Site Full Document and Summary ...

  20. The Evolution in Pu Nanocluster Electronic Structure: from Atomicity...

    Office of Scientific and Technical Information (OSTI)

    Conference: The Evolution in Pu Nanocluster Electronic Structure: from Atomicity to Three Dimensionality Citation Details In-Document Search Title: The Evolution in Pu Nanocluster ...

  1. Multiscale Speciation of U and Pu at Chernobyl, Hanford, Los Alamos,

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

    McGuire AFB, Mayak, and Rocky Flats | Stanford Synchrotron Radiation Lightsource Multiscale Speciation of U and Pu at Chernobyl, Hanford, Los Alamos, McGuire AFB, Mayak, and Rocky Flats Friday, June 26, 2015 X-ray fluorescence maps of (clockwise from upper right) Ga, U, Ca, Pu, Ti, and K in a 350 micron PuO2-UO2 composite particle produced by the fire that consumed a nuclear armed BOMARC missile at McGuire AFB in 1960, measured with the two micron focused x-ray beam at SSRL. EST June 2,

  2. A=3n (2010PU04)

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

    2010PU04) GENERAL: There is no experimental evidence for either bound states or narrow resonances of the three neutron system. Theoretical studies in the 3n system using the...

  3. Determining site-specific drum loading criteria for storing combustible {sup 238}Pu waste

    SciTech Connect (OSTI)

    Marshall, R.S.; Callis, E.L.; Cappis, J.H.; Espinoza, J.M.; Foltyn, E.M.; Reich, B.T.; Smith, M.C.

    1994-02-01

    Waste containing hydrogenous-combustible material contaminated with {sup 238}Pu can generate hydrogen gas at appreciable rates through alpha radiolysis. To ensure safe transportation of WIPP drums, the limit for {sup 238}Pu-combustible waste published in the WIPP TRUPACT-11 CONTENT (TRUCON) CODES is 21 milliwafts per 55 gallon drum. This corresponds to about 45 milligrams of {sup 238}PuO{sub 2} used for satellite heat source-electrical generators. The Los Alamos waste storage site adopted a {sup 238}Pu waste storage criteria based on these TRCUCON codes. However, reviews of the content in drums of combustible waste generated during heat source assembly at Los Alamos showed the amount of {sup 238}Pu is typically much greater than 45 milligrams. It is not feasible to appreciably reduce Los Alamos {sup 238}Pu waste drum loadings without significantly increasing waste volumes or introducing unsafe practices. To address this concern, a series of studies were implemented to evaluate the applicability of the TRUCON limits for storage of this specific waste. Addressed in these evaluations were determination of the hydrogen generation rate, hydrogen diffusion rates through confinement layers and vent filters, and packaging requirements specific to Los Alamos generated {sup 238}Pu contaminated combustible waste. These studies also showed that the multiple-layer packaging practices in use at Los Alamos could be relaxed without significantly increasing the risk of contamination. Based on a model developed to predict H{sub 2} concentrations in packages and drum headspace, the site specific effective hydrogen generation rate, and hydrogen-diffusion values, and revising the waste packaging practices, we were able to raise the safe loading limit for {sup 238}Pu waste drums for on site storage to the gram levels typical of currently generated {sup 238}Pu waste.

  4. Characterization of Pu-238 heat source granule containment

    SciTech Connect (OSTI)

    Richardson Ii, P D; Thronas, D L; Romero, J P; Sandoval, F E; Neuman, A D; Duncan, W S

    2008-01-01

    The Milliwatt Radioisotopic Thermoelectric Generator (RTG) provides power for permissive-action links. These nuclear batteries convert thermal energy to electrical energy using a doped silicon-germanium thermopile. The thermal energy is provided by a heat source made of {sup 238}Pu, in the form of {sup 238}PuO{sub 2} granules. The granules are contained in 3 layers of encapsulation. A thin T-111 liner surrounds the {sup 238}PuO{sub 2} granules and protects the second layer (strength member) from exposure to the fuel granules. The T-111 strength member contains the fuel under impact condition. An outer clad of Hastelloy-C protects the T-111 from oxygen embrittlement. The T-111 strength member is considered the critical component in this {sup 238}PuO{sub 2} containment system. Any compromise in the strength member is something that needs to be characterized. Consequently, the T-111 strength member is characterized upon it's decommissioning through Scanning Electron Microscopy (SEM), and Metallography. SEM is used in Secondary Electron mode to reveal possible grain boundary deformation and/or cracking in the region of the strength member weld. Deformation and cracking uncovered by SEM are further characterized by Metallography. Metallography sections are mounted and polished, observed using optical microscopy, then documented in the form of photomicrographs. SEM may further be used to examine polished Metallography mounts to characterize elements using the SEM mode of Energy Dispersive X-ray Spectroscopy (EDS). This paper describes the characterization of the metallurgical condition of decommissioned RTG heat sources.

  5. Absolute measurement of the 242Pu neutron-capture cross section

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

    Buckner, M. Q.; Wu, C. Y.; Henderson, R. A.; Bucher, B.; Chyzh, A.; Bredeweg, T. A.; Baramsai, B.; Couture, A.; Jandel, M.; Mosby, S.; et al

    2016-04-21

    Here, the absolute neutron-capture cross section of 242Pu was measured at the Los Alamos Neutron Science Center using the Detector for Advanced Neutron-Capture Experiments array along with a compact parallel-plate avalanche counter for fission-fragment detection. The first direct measurement of the 242Pu(n,γ) cross section was made over the incident neutron energy range from thermal to ≈ 6 keV, and the absolute scale of the (n,γ) cross section was set according to the known 239Pu(n,f) resonance at En,R = 7.83 eV. This was accomplished by adding a small quantity of 239Pu to the 242Pu sample. The relative scale of the crossmore » section, with a range of four orders of magnitude, was determined for incident neutron energies from thermal to ≈ 40 keV. Our data, in general, are in agreement with previous measurements and those reported in ENDF/B-VII.1; the 242Pu(n,γ) cross section at the En,R = 2.68 eV resonance is within 2.4% of the evaluated value. However, discrepancies exist at higher energies; our data are ≈30% lower than the evaluated data at En ≈ 1 keV and are approximately 2σ away from the previous measurement at En ≈ 20 keV.« less

  6. A Brief Review of Past INL Work Assessing Radionuclide Content in TMI-2 Melted Fuel Debris: The Use of 144Ce as a Surrogate for Pu Accountancy

    SciTech Connect (OSTI)

    D. L. Chichester; S. J. Thompson

    2013-09-01

    This report serves as a literature review of prior work performed at Idaho National Laboratory, and its predecessor organizations Idaho National Engineering Laboratory (INEL) and Idaho National Engineering and Environmental Laboratory (INEEL), studying radionuclide partitioning within the melted fuel debris of the reactor of the Three Mile Island 2 (TMI-2) nuclear power plant. The purpose of this review is to document prior published work that provides supporting evidence of the utility of using 144Ce as a surrogate for plutonium within melted fuel debris. When the TMI-2 accident occurred no quantitative nondestructive analysis (NDA) techniques existed that could assay plutonium in the unconventional wastes from the reactor. However, unpublished work performed at INL by D. W. Akers in the late 1980s through the 1990s demonstrated that passive gamma-ray spectrometry of 144Ce could potentially be used to develop a semi-quantitative correlation for estimating plutonium content in these materials. The fate and transport of radioisotopes in fuel from different regions of the core, including uranium, fission products, and actinides, appear to be well characterized based on the maximum temperature reached by fuel in different parts of the core and the melting point, boiling point, and volatility of those radioisotopes. Also, the chemical interactions between fuel, fuel cladding, control elements, and core structural components appears to have played a large role in determining when and how fuel relocation occurred in the core; perhaps the most important of these reaction appears to be related to the formation of mixed-material alloys, eutectics, in the fuel cladding. Because of its high melting point, low volatility, and similar chemical behavior to plutonium, the element cerium appears to have behaved similarly to plutonium during the evolution of the TMI-2 accident. Anecdotal evidence extrapolated from open-source literature strengthens this logical feasibility for

  7. Hydrothermal Alteration of Glass from Underground Nuclear Tests: Formation and Transport of Pu-clay Colloids at the Nevada National Security Site

    SciTech Connect (OSTI)

    Zavarin, M.; Zhao, P.; Joseph, C.; Begg, J.; Boggs, M.; Dai, Z.; Kersting, A. B.

    2015-05-27

    The testing of nuclear weapons at the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), has led to the deposition of substantial quantities of plutonium into the environment. Approximately 2.8 metric tons (3.1×104 TBq) of Pu were deposited in the NNSS subsurface as a result of underground nuclear testing. While 3H is the most abundant anthropogenic radionuclide deposited in the NNSS subsurface (4.7×106 TBq), plutonium is the most abundant from a molar standpoint. The only radioactive elements in greater molar abundance are the naturally occurring K, Th, and U isotopes. 239Pu and 240Pu represent the majority of alpha-emitting Pu isotopes. The extreme temperatures associated with underground nuclear tests and the refractory nature of Pu results in most of the Pu (98%) being sequestered in melted rock, referred to as nuclear melt glass (Iaea, 1998). As a result, Pu release to groundwater is controlled, in large part, by the leaching (or dissolution) of nuclear melt glass over time. The factors affecting glass dissolution rates have been studied extensively. The dissolution of Pu-containing borosilicate nuclear waste glasses at 90ºC has been shown to lead to the formation of dioctahedral smectite colloids. Colloid-facilitated transport of Pu at the NNSS has been observed. Recent groundwater samples collected from a number of contaminated wells have yielded a wide range of Pu concentrations from 0.00022 to 2.0 Bq/L. While Pu concentrations tend to fall below the Maximum Contaminant Level (MCL) established by the Environmental Protection Agency (EPA) for drinking water (0.56 Bq/L), we do not yet understand what factors limit the Pu concentration or its transport behavior. To quantify the upper limit of Pu concentrations produced as a result of melt glass dissolution and determine the nature of colloids and Pu associations, we performed a 3 year nuclear melt glass dissolution experiment

  8. COMPUTER SIMULATIONS TO ADDRESS PU-FE EUTECTICISSUE IN 3013 STORAGE VESSEL

    SciTech Connect (OSTI)

    Gupta, N; Allen Smith, A

    2007-03-06

    On November 22, 2005, the Manager of the Plutonium Finishing Plant (PFP) in Richland, WA issued an Occurrence Report involving a potential Pu-Fe eutectic failure mechanism for the stainless steel (SS) 3013 cans containing plutonium (Pu) metal. Four additional reports addressed nuclear safety concerns about the integrity of stainless steel containers holding plutonium during fire scenarios. The reports expressed a belief that the probability and consequences of container failure due to the formation of a plutonium-iron eutectic alloy had been overlooked. Simplified thermal model to address the Pu-Fe eutectic concerns using axisymmetric model similar to the models used in the 9975 SARP were performed. The model uses Rocky Flats configuration with 2 stacked Pu buttons inside a 3013 assembly. The assembly has an outer can, an inner can, and a convenience can, all stainless steel. The boundary conditions are similar to the regulatory 30 minutes HAC fire analyses. Computer simulations of the HAC fire transients lasting 4 hours of burn time show that the interface between the primary containment vessel and the Pu metal in the 9975 package will not reach Pu-Fe eutectic temperature of 400 C.

  9. Removal of Pu238 from Neptunium Solution by Anion Exchange

    SciTech Connect (OSTI)

    KYSER, EDWARD

    2003-12-01

    A new anion flowsheet for use in HB-Line was tested in the lab with Reillex{trademark} HPQ for removal of Pu{sup 238} contamination from Np. Significant rejection of Pu{sup 238} was observed by washing with 6 to 12 bed volumes (BV) of reductive wash containing reduced nitric acid concentration along with both ferrous sulfamate (FS) and hydrazine. A shortened-height column was utilized in these tests to match changes in the plant equipment. Lab experiments scaled to plant batch sizes of 1500 to 2200 g Np were observed with modest losses for up-flow washing. Down-flow washing was observed to have high losses. The following are recommended conditions for removing Pu{sup 238} from Np solutions by anion exchange in HB-Line: (1) Feed conditions: Up-flow 6.4-8 M HNO{sub 3}, 0.02 M hydrazine, 0.05 M excess FS, less than 5 days storage of solution after FS addition. (2) Reductive Wash conditions: Up-flow 6-12 BV of 6.4 M HNO{sub 3}, 0.05 M FS, 0.05 M hydrazine. 1.8 mL/min/cm{sup 2} flowrate. (3) Decontamination Wash conditions: Up-flow 1-2 BV of 6.4-8 M HNO{sub 3}, no FS, no hydrazine. (4) Elution conditions: Down-flow 0.17 M HNO{sub 3}, 0.05 M hydrazine, no FS.

  10. Neutron Resonance Parameters and Covariance Matrix of 239Pu

    SciTech Connect (OSTI)

    Derrien, Herve; Leal, Luiz C; Larson, Nancy M

    2008-08-01

    In order to obtain the resonance parameters in a single energy range and the corresponding covariance matrix, a reevaluation of 239Pu was performed with the code SAMMY. The most recent experimental data were analyzed or reanalyzed in the energy range thermal to 2.5 keV. The normalization of the fission cross section data was reconsidered by taking into account the most recent measurements of Weston et al. and Wagemans et al. A full resonance parameter covariance matrix was generated. The method used to obtain realistic uncertainties on the average cross section calculated by SAMMY or other processing codes was examined.

  11. A New Bench-Top Approach to Isotopic Purification of 244Pu

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

    Liezers, Martin; Farmer, Orville T.; Thomas, Linda MP; Hager, George J.; Eiden, Gregory C.

    2016-03-01

    A new approach to isotopic purification has been developed and applied to the production of a small quantity of 244Pu with an isotopic purity >99.996 %, as compared against the standard 244Pu available that displays an isotopic purity of 97.87 %. The presence of Pu isotopes 239Pu, 240Pu, 241Pu and 242Pu have been greatly reduced, allowing for higher spiking levels of the isotopically purified 244Pu tracer. Details of the isotopic purification process will be described along with the effect this improved Pu tracer could have on analytical Pu mass spectrometry measurements.

  12. Understanding oxygen adsorption on 9.375 at. % Ga-stabilized δ-Pu (111) surface: A DFT study

    SciTech Connect (OSTI)

    Hernandez, Sarah C.; Wilkerson, Marianne P.; Huda, Muhammad N.

    2015-08-30

    Plutonium (Pu) metal reacts rapidly in the presence of oxygen (O), resulting in an oxide layer that will eventually have an olive green rust appearance over time. Recent experimental work suggested that the incorporation of gallium (Ga) as an alloying impurity to stabilize the highly symmetric high temperature δ-phase lattice may also provide resistance against corrosion/oxidation of plutonium. In this paper, we modeled a 9.375 at. % Ga stabilized δ-Pu (111) surface and investigated adsorption of atomic O using all-electron density functional theory. Key findings revealed that the O bonded strongly to a Pu-rich threefold hollow fcc site with a chemisorption energy of –5.06 eV. Migration of the O atom to a Pu-rich environment was also highly sensitive to the surface chemistry of the Pu–Ga surface; when the initial on-surface O adsorption site included a bond to a nearest neighboring Ga atom, the O atom relaxed to a Ga deficient environment, thus affirming the O preference for Pu. Only one calculated final on-surface O adsorption site included a Ga-O bond, but this chemisorption energy was energetically unfavorable. Chemisorption energies for interstitial adsorption sites that included a Pu or Pu-Ga environment suggested that over-coordination of the O atom was energetically unfavorable as well. Electronic structure properties of the on-surface sites, illustrated by the partial density of states, implied that the Ga 4p states indirectly but strongly influenced the Pu 6d states strongly to hybridize with the O 2p states, while also weakly influenced the Pu 5f states to hybridize with the O 2p states, even though Ga was not participating in bonding with O.

  13. Understanding oxygen adsorption on 9.375 at. % Ga-stabilized δ-Pu (111) surface: A DFT study

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

    Hernandez, Sarah C.; Wilkerson, Marianne P.; Huda, Muhammad N.

    2015-08-30

    Plutonium (Pu) metal reacts rapidly in the presence of oxygen (O), resulting in an oxide layer that will eventually have an olive green rust appearance over time. Recent experimental work suggested that the incorporation of gallium (Ga) as an alloying impurity to stabilize the highly symmetric high temperature δ-phase lattice may also provide resistance against corrosion/oxidation of plutonium. In this paper, we modeled a 9.375 at. % Ga stabilized δ-Pu (111) surface and investigated adsorption of atomic O using all-electron density functional theory. Key findings revealed that the O bonded strongly to a Pu-rich threefold hollow fcc site with amore » chemisorption energy of –5.06 eV. Migration of the O atom to a Pu-rich environment was also highly sensitive to the surface chemistry of the Pu–Ga surface; when the initial on-surface O adsorption site included a bond to a nearest neighboring Ga atom, the O atom relaxed to a Ga deficient environment, thus affirming the O preference for Pu. Only one calculated final on-surface O adsorption site included a Ga-O bond, but this chemisorption energy was energetically unfavorable. Chemisorption energies for interstitial adsorption sites that included a Pu or Pu-Ga environment suggested that over-coordination of the O atom was energetically unfavorable as well. Electronic structure properties of the on-surface sites, illustrated by the partial density of states, implied that the Ga 4p states indirectly but strongly influenced the Pu 6d states strongly to hybridize with the O 2p states, while also weakly influenced the Pu 5f states to hybridize with the O 2p states, even though Ga was not participating in bonding with O.« less

  14. Modeling and production of 240Am by deuteron-induced activation of a 240Pu target

    SciTech Connect (OSTI)

    Finn, Erin C.; McNamara, Bruce K.; Greenwood, Lawrence R.; Wittman, Richard S.; Soderquist, Chuck Z.; Woods, Vincent T.; VanDevender, Brent A.; Metz, Lori A.; Friese, Judah I.

    2015-02-01

    A novel reaction pathway for production of 240Am is reported. Models of reaction cross-sections in EMPIRE II suggests that deuteron-induced activation of a 240Pu target produces maximum yields of 240Am from 11.5 MeV incident deuterons. This activation had not been previously reported in the literature. A 240Pu target was activated under the modeled optimum conditions to produce 240Am. The modeled cross-section for the 240Pu(d, 2n)240Am reaction is on the order of 20-30 mbarn, but the experimentally estimated value is 5.3 0.2 mbarn. We discuss reasons for the discrepancy as well as production of other Am isotopes that contaminate the final product.

  15. Sintering of compacts of UN, (U,Pu)N, and PuN

    DOE Patents [OSTI]

    Tennery, V.J.; Godfrey, T.G.; Bomar, E.S.

    1973-10-16

    >A method is provided for preparing a densified compact of a metal nitride selected from the group consisting of UN, (U,Pu)N, and PuN which comprises heating a green compact of at least one selected nitride in the mononitride single-phase region, as displayed by a phase diagram of the mononitride of said compact, in a nitrogen atmosphere at a pressure of nitrogen less than 760 torr. At a given temperature, this process produces a singlephase structure and a maximal sintered density as measured by mercury displacement. (Official Gazette)

  16. Nuclear magnetic resonance offers new insights into Pu 239

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

    Nuclear magnetic resonance offers new insights into Pu 239 Nuclear magnetic resonance offers new insights into Pu 239 Fingerprint of element found by LANL/Japanese team. May 29, 2012 How would the detonation of a nuclear energy source afffect an incoming asteroid? Georgios Koutroulakis and H. Yasuoka in the condensed-matter NMR lab at Los Alamos National Laboratory after having observed the magnetic resonance signal of Pu 239 for the first time. Get Expertise Scientist Eric Bauer Condensed

  17. A=3Li (2010PU04)

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

    2010PU04) GENERAL: The previous A = 3 evaluations (1975FI08, 1987TI07) identified reactions 1 through 4 below as possible candidates for the observation of a bound or resonant state of three protons. An additional possibility would be the double charge exchange reaction 3H(π+, π-)3Li. There is a report of this reaction (2001PA47), but the pion energy was high, 500 MeV, and the focus of the experiment was on the role of the Δ component in the 3H ground state, not on the possible presence of a

  18. Fission fragment charge and mass distributions in Pu 239 ( n...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Fission fragment charge and mass distributions in Pu 239 ( n , f ) in the adiabatic nuclear energy density functional theory Citation Details In-Document Search ...

  19. Report on the Feasibility of Pu Photoelectron Spectroscopy with...

    Office of Scientific and Technical Information (OSTI)

    Report on the Feasibility of Pu Photoelectron Spectroscopy with Microscopic and Nanoscopic Samples at NSLSII Citation Details In-Document Search Title: Report on the Feasibility of ...

  20. Ground-state wave function of plutonium in PuSb as determined via x-ray magnetic circular dichroism

    SciTech Connect (OSTI)

    Janoschek, M.; Haskel, D.; Fernandez-Rodriguez, J.; van Veenendaal, M.; Rebizant, J.; Lander, G. H.; Zhu, J. -X.; Thompson, J. D.; Bauer, E. D.

    2015-01-01

    Measurements of x-ray magnetic circular dichroism (XMCD) and x-ray absorption near-edge structure (XANES) spectroscopy at the Pu M?,? edges of the ferromagnet PuSb are reported. Using bulk magnetization measurements and a sum rule analysis of the XMCD spectra, we determine the individual orbital [?L = 2.8(1)?B/Pu] and spin moments [?S = ?2.0(1)?B/Pu] of the Pu 5f electrons for the first time. Atomic multiplet calculations of the XMCD and XANES spectra reproduce well the experimental data and are consistent with the experimental value of the spin moment. These measurements of ?Lz? and ?Sz? are in excellent agreement with the values that have been extracted from neutron magnetic form factor measurements, and confirm the local character of the 5f electrons in PuSb. Finally, we demonstrate that a split M? as well as a narrow M? XMCD signal may serve as a signature of 5f electron localization in actinide compounds.

  1. Ground-state wave function of plutonium in PuSb as determined via x-ray magnetic circular dichroism

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

    Janoschek, M.; Haskel, D.; Fernandez-Rodriguez, J.; van Veenendaal, M.; Rebizant, J.; Lander, G. H.; Zhu, J. -X.; Thompson, J. D.; Bauer, E. D.

    2015-01-14

    Measurements of x-ray magnetic circular dichroism (XMCD) and x-ray absorption near-edge structure (XANES) spectroscopy at the Pu M₄,₅ edges of the ferromagnet PuSb are reported. Using bulk magnetization measurements and a sum rule analysis of the XMCD spectra, we determine the individual orbital [μL = 2.8(1)μB/Pu] and spin moments [μS = –2.0(1)μB/Pu] of the Pu 5f electrons for the first time. Atomic multiplet calculations of the XMCD and XANES spectra reproduce well the experimental data and are consistent with the experimental value of the spin moment. These measurements of Lz and Sz are in excellent agreement with the values thatmore » have been extracted from neutron magnetic form factor measurements, and confirm the local character of the 5f electrons in PuSb. We demonstrate that a split M₅ as well as a narrow M₄ XMCD signal may serve as a signature of 5f electron localization in actinide compounds.« less

  2. Procedure for plutonium determination using Pu(VI) spectra

    SciTech Connect (OSTI)

    Walker, L.F.; Temer, D.J.; Jackson, D.D.

    1996-09-01

    This document describes a simple spectrophotometric method for determining total plutonium in nitric acid solutions based on the spectrum of Pu(VI). Plutonium samples in nitric acid are oxidized to Pu(VI) with Ce(IV) and the net absorbance at the 830 nm peak is measured.

  3. Neutronics Simulations of 237Np Targets to Support Safety-Basis and 238Pu Production Assessment Efforts at the High Flux Isotope Reactor

    SciTech Connect (OSTI)

    Chandler, David; Ellis, Ronald James

    2015-01-01

    Fueled by two highly enriched uranium-bearing fuel elements surrounded by a large concentric ring of beryllium reflector, the High Flux Isotope Reactor (HFIR) provides one of the highest neutron fluxes in the world and is used to produce unique isotopes like plutonium-238. The National Aeronautics and Space Administration use radioisotope thermoelectric generators powered by 238Pu for deep-space missions. As part of the US Department of Energy s task to reestablish the domestic production of 238Pu, a technology demonstration sub-project has been initiated to establish a new 238Pu supply chain. HFIR safety-basis neutronics calculations are being performed to ensure the target irradiations have no adverse impacts on reactor performance and to calculate data required as input to follow-on thermal-structural, thermal-hydraulic and radionuclide/dose analyses. Plutonium-238 production assessments are being performed to estimate the amount of 238Pu that can be produced in HFIR s permanent beryllium reflector. It is estimated that a total of 0.96 1.12 kg 238Pu (~1.28 1.49 kg PuO2 at 85% 238Pu/Pu purity) could be produced per year in HFIR s permanent beryllium reflector irradiation facilities if they are all utilized.

  4. Performance of Cladding on MOX Fuel with Low 240Pu/239Pu Ratio

    SciTech Connect (OSTI)

    McCoy, Kevin; Blanpain, Patrick; Morris, Robert Noel

    2014-01-01

    The U.S. Department of Energy has decided to dispose of a portion of its surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. As part of fuel qualification, four lead assemblies were manufactured and irradiated to a maximum fuel rod average burnup of 47.3 MWd/kg heavy metal. This was the world s first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This paper discusses the results of those examinations with emphasis on cladding performance. Exams relevant to the cladding included visual and eddy current exams, profilometry, microscopy, hydrogen analysis, gallium analysis, and mechanical testing. There was no discernible effect of the type of MOX fuel on the performance of the cladding.

  5. Consistent Data Assimilation of Isotopes: 242Pu and 105Pd

    SciTech Connect (OSTI)

    G. Palmiotti; H. Hiruta; M. Salvatores

    2012-09-01

    In this annual report we illustrate the methodology of the consistent data assimilation that allows to use the information coming from integral experiments for improving the basic nuclear parameters used in cross section evaluation. A series of integral experiments are analyzed using the EMPIRE evaluated files for 242Pu and 105Pd. In particular irradiation experiments (PROFIL-1 and -2, TRAPU-1, -2 and -3) provide information about capture cross sections, and a critical configuration, COSMO, where fission spectral indexes were measured, provides information about fission cross section. The observed discrepancies between calculated and experimental results are used in conjunction with the computed sensitivity coefficients and covariance matrix for nuclear parameters in a consistent data assimilation. The results obtained by the consistent data assimilation indicate that not so large modifications on some key identified nuclear parameters allow to obtain reasonable C/E. However, for some parameters such variations are outside the range of 1 s of their initial standard deviation. This can indicate a possible conflict between differential measurements (used to calculate the initial standard deviations) and the integral measurements used in the statistical data adjustment. Moreover, an inconsistency between the C/E of two sets of irradiation experiments (PROFIL and TRAPU) is observed for 242Pu. This is the end of this project funded by the Nuclear Physics Program of the DOE Office of Science. We can indicate that a proof of principle has been demonstrated for a few isotopes for this innovative methodology. However, we are still far from having explored all the possibilities and made this methodology to be considered proved and robust. In particular many issues are worth further investigation: • Non-linear effects • Flexibility of nuclear parameters in describing cross sections • Multi-isotope consistent assimilation • Consistency between differential and integral

  6. Crystal Dynamics of (delta) fcc Pu-Ga by High Resolution Inelastic X-Ray Scattering

    SciTech Connect (OSTI)

    Wong, J; Krisch, M; Farber, D; Occelli, F; Xu, R; Chiang, T C; Clatterbuck, D; Schwartz, A J; Wall, M; Boro, C

    2004-09-28

    We have used a microbeam on large grain sample concept to carry out an inelastic x-ray scattering experiment to map the full phonon dispersion curves of an fcc {delta}-phase Pu-Ga alloy. This approach obviates experimental difficulties with conventional inelastic neutron scattering due to the high absorption cross section of the common {sup 239}Pu isotope and the non-availability of large (mm size) single crystal materials for Pu and its alloys. A classical Born von-Karman force constant model was used to model the experimental results, and no less than 4th nearest neighbor interactions had to be included to account for the observation. Several unusual features including, a large elastic anisotropy, a small shear elastic modulus, (C{sub 11}-C{sub 12})/2, a Kohn-like anomaly in the T{sub 1}[011] branch, and a pronounced softening of the T[111] branch towards the L point in the Brillouin are found. These features can be related to the phase transitions of plutonium and to strong coupling between the crystal structure and the 5f valence instabilities. Our results represent the first full phonon dispersions ever obtained for any Pu-bearing material, thus ending a 40-year quest for this fundamental data. The phonon data also provide a critical test for theoretical treatments of highly correlated 5f electron systems as exemplified by recent dynamical mean field theory (DMFT) calculations for {delta}-plutonium.

  7. Elastic properties of gamma-Pu by resonant ultrasound spectroscopy

    SciTech Connect (OSTI)

    Migliori, Albert; Betts, J; Trugman, A; Mielke, C H; Mitchell, J N; Ramos, M; Stroe, I

    2009-01-01

    Despite intense experimental and theoretical work on Pu, there is still little understanding of the strange properties of this metal. We used resonant ultrasound spectroscopy method to investigate the elastic properties of pure polycrystalline Pu at high temperatures. Shear and longitudinal elastic moduli of the {gamma}-phase of Pu were determined simultaneously and the bulk modulus was computed from them. A smooth linear and large decrease of all elastic moduli with increasing temperature was observed. We calculated the Poisson ratio and found that it increases from 0.242 at 519K to 0.252 at 571K.

  8. 239Pu Resonance Evaluation for Thermal Benchmark System Calculations

    SciTech Connect (OSTI)

    Leal, Luiz C; Noguere, G; De Saint Jean, C; Kahler, A.

    2013-01-01

    Analyses of thermal plutonium solution critical benchmark systems have indicated a deciency in the 239Pu resonance evaluation. To investigate possible solutions to this issue, the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) Working Party for Evaluation Cooperation (WPEC) established Subgroup 34 to focus on the reevaluation of the 239Pu resolved resonance parameters. In addition, the impacts of the prompt neutron multiplication (nubar) and the prompt neutron ssion spectrum (PFNS) have been investigated. The objective of this paper is to present the results of the 239Pu resolved resonance evaluation eort.

  9. The reduction of Np(VI) and Pu(VI) by organic chelating agents.

    SciTech Connect (OSTI)

    Reed, D.T.; Aase, S.B.; Banaszak, J.E.

    1998-03-19

    The reduction of NpO{sup 2+} and PuO{sub 2}{sup 2+} by oxalate. citrate, and ethylenediaminetetraacetic acid (EDTA) was investigated in low ionic strength media and brines. This was done to help establish the stability of the An(VI) oxidation state in the presence of organic complexants. The stability of the An(VI) oxidation state depended on the pH and relative strength of the various oxidation state-specific complexes. At low ionic strength and pH 6, NpO{sub 2}O{sup 2+} was rapidly reduced to form NpO{sub 2}{sup +} organic complexes. At longer times, Np(IV) organic complexes were observed in the presence of citrate. PuO{sub 2}{sup 2+} was predominantly reduced to Pu{sup 4+}, resulting in the formation of organic complexes or polymeric/hydrolytic precipitates. The relative rates of reduction to the An(V) complex were EDTA > citrate > oxalate. Subsequent reduction to An(IV) complexes, however, occurred in the following order: citrate > EDTA > oxalate because of the stability of the An(V)-EDTA complex. The presence of organic complexants led to the rapid reduction of NpO{sub 2}{sup 2+} and PuO{sub 2}P{sup 2+} in G-seep brine at pHs 5 and 7. At pHs 8 and 10 in ERDA-6 brine, carbonate and hydrolytic complexes predominated and slowed down or prevented the reduction of An(VI) by the organics present.

  10. Ferro- and antiferro-magnetism in (Np, Pu)BC

    SciTech Connect (OSTI)

    Klimczuk, T.; Kozub, A. L.; Griveau, J.-C.; Colineau, E.; Wastin, F.; Falmbigl, M.; Rogl, P.

    2015-04-01

    Two new transuranium metal boron carbides, NpBC and PuBC, have been synthesized. Rietveld refinements of powder XRD patterns of (Np,Pu)BC confirmed in both cases isotypism with the structure type of UBC. Temperature dependent magnetic susceptibility data reveal antiferromagnetic ordering for PuBC below T{sub N} = 44 K, whereas ferromagnetic ordering was found for NpBC below T{sub C} = 61 K. Heat capacity measurements prove the bulk character of the observed magnetic transition for both compounds. The total energy electronic band structure calculations support formation of the ferromagnetic ground state for NpBC and the antiferromagnetic ground state for PuBC.

  11. Probing Actinide Electronic Structure through Pu Cluster Calculations

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

    Ryzhkov, Mickhail V.; Mirmelstein, Alexei; Yu, Sung-Woo; Chung, Brandon W.; Tobin, James G.

    2013-02-26

    The calculations for the electronic structure of clusters of plutonium have been performed, within the framework of the relativistic discrete-variational method. Moreover, these theoretical results and those calculated earlier for related systems have been compared to spectroscopic data produced in the experimental investigations of bulk systems, including photoelectron spectroscopy. Observation of the changes in the Pu electronic structure as a function of size provides powerful insight for aspects of bulk Pu electronic structure.

  12. MGA++ Analysis of Low Quantity Samples of U and Pu on an Extended-rage Gamma-ray Detector

    SciTech Connect (OSTI)

    Wang, T; Russ, G P; Williams, R W

    2007-06-04

    The IAEA has expressed a need for improved determination of gamma emitting nuclides in environmental samples collected during inspections of nuclear facilities and to use the MGA++ to determine U and Pu concentrations and isotopic compositions when those elements are present in relatively high concentrations. We are addressing the IAEA needs by evaluating the applicability of extended-range germanium detectors (ERG). In this paper we used 1g U isotopic standards and 100ug Pu liquid standards (1) to determine the performance of MGA++ on this special detector and (2) to estimate the amount of U and Pu necessary in the sample for determination of the isotopics via MGA++ within reasonable accuracy for a week of counting time using this ERG detector.

  13. Transuranic concentrations in reef and pelagic fish from the Marshall Islands. [/sup 239/Pu, /sup 240/Pu

    SciTech Connect (OSTI)

    Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Jokela, T.A.

    1980-09-01

    Concentrations of /sup 239 + 240/Pu are reported in tissues of several species of reef and pelagic fish caught at 14 different atolls in the northern Marshall Islands. Several regularities that are species dependent are evident in the distribution of /sup 239 + 240/Pu among different body tissues. Concentrations in liver always exceeded those in bone and concentrations were lowest in the muscle of all fish analyzed. A progressive discrimination against /sup 239 + 240/Pu was observed at successive trophic levels at all atolls except Bikini and Enewetak, where it was difficult to conclude if any real difference exists between the average concentration factor for /sup 239 + 240/Pu among all fish, which include bottom feeding and grazing herbivores, bottom feeding carnivores, and pelagic carnivores from different atoll locations. The average concentration of /sup 239 + 240/Pu in the muscle of surgeonfish from Bikini and Enewetak was not significantly different from the average concentrations determined in these fish at the other, lesser contaminated atolls. Concentrations among all 3rd, 4th, and 5th trophic level species are highest at Bikini where higher environmental concentrations are found. The reasons for the anomalously low concentrations in herbivores from Bikini and Enewetak are not known.

  14. Phonon dispersion curves determination in (delta)-phase Pu-Ga alloys

    SciTech Connect (OSTI)

    Wong, J; Clatterbuck, D; Occelli, F; Farber, D; Schwartz, A; Wall, M; Boro, C; Krisch, M; Beraud, A; Chiang, T; Xu, R; Hong, H; Zschack, P; Tamura, N

    2006-02-07

    We have designed and successfully employed a novel microbeam on large grain sample concept to conduct high resolution inelastic x-ray scattering (HRIXS) experiments to map the full phonon dispersion curves of an fcc {delta}-phase Pu-Ga alloy. This approach obviates experimental difficulties with conventional inelastic neutron scattering due to the high absorption cross section of the common {sup 239}Pu isotope and the non-availability of large (mm size) single crystal materials for Pu and its alloys. A classical Born von-Karman force constant model was used to model the experimental results, and no less than 4th nearest neighbor interactions had to be included to account for the observation. Several unusual features including, a large elastic anisotropy, a small shear elastic modulus, (C{sub 11}-C{sub 12})/2, a Kohn-like anomaly in the T{sub 1}[011] branch, and a pronounced softening of the T[111] branch towards the L point in the Brillouin are found. These features may be related to the phase transitions of plutonium and to strong coupling between the crystal structure and the 5f valence instabilities. Our results represent the first full phonon dispersions ever obtained for any Pu-bearing material, thus ending a 40-year quest for this fundamental data. The phonon data also provide a critical test for theoretical treatments of highly correlated 5f electron systems as exemplified by recent dynamical mean field theory (DMFT) calculations for {delta}-plutonium. We also conducted thermal diffuse scattering experiments to study the T(111) dispersion at low temperatures with an attempt to gain insight into bending of the T(111) branch in relationship to the {delta} {yields} {alpha}{prime} transformation.

  15. NMIS With Gamma Spectrometry for Attributes of Pu and HEU, Explosives and Chemical Agents

    SciTech Connect (OSTI)

    Mihalczo, J. T.; Mattingly, J. K.; Mullens, J. A.; Neal, J. S.

    2002-05-10

    The concept for the system described herein is an active/passive Nuclear Materials Identification System{sup 2} (NMIS) that incorporates gamma ray spectrometry{sup 3}. This incorporation of gamma ray spectrometry would add existing capability into this system. This Multiple Attribute System can determine a wide variety of attributes for Pu and highly enriched uranium (HEU) of which a selected subset could be chosen. This system can be built using commercial off the shelf (COTS) components. NMIS systems are at All-Russian Scientific Research Institute of Experimental Physics (VNIIEF) and Russian Federal Nuclear Center Institute of Technical Physics, (VNIITF) and measurements with Pu have been performed at VNIIEF and analyzed successfully for mass and thickness of Pu. NMIS systems are being used successfully for HEU at the Y-12 National Security Complex. The use of active gamma ray spectrometry for high explosive HE and chemical agent detection is a well known activation analysis technique, and it is incorporated here. This report describes the system, explains the attribute determination methods for fissile materials, discusses technical issues to be resolved, discusses additional development needs, presents a schedule for building from COTS components, and assembly with existing components, and discusses implementation issues such as lack of need for facility modification and low radiation exposure.

  16. Radioecologycal study of {sup 239/240}Pu in Bangka Island and Muria Peninsula: Determination of {sup 239/240}Pu in marine sediment and seawater as part of baseline data collecting for sitting of candidates of first Indonesia NPP

    SciTech Connect (OSTI)

    Suseno, Heny; Wisnubroto, Djarot S.

    2014-03-24

    Radioisotope Pu-239/240 are alpha emitting nuclides important indicators of radioactive contamination of the marine environment. Global fallout is the main source of plutonium in the marine environment. There are very limited study on {sup 239/240}Pu in Indonesia coastal environments. The data of this radioisotopes is needed for baseline data of nuclear power plant (NPP) site candidates both in Bangka Island and Muria Peninsula. Bottom sediments play an important role in radioecological studies of the marine environment because a large proportion of radioactive substances entering the sea is adsorbed over time onto suspended particulate matter and deposited in sediments. Plutonium is particle reactive and deposited in marine sediment. Radioisotope {sup 239/240}Pu was determinated by alpha spectrometry after radiochemical procedure that was performed in both water and marine sediment from Bangka Island and Muria Peninsula. The sediment baseline of concentration {sup 239/240}Pu in Bangka Island and Muria Peninsula were range from 0.013 to 0.021 Bq.kg{sup ?1} and 0.018 to 0.024 Bq.kg{sup ?1} respectively. The water baseline concentration this isotope were range from 2.73 to 4.05 mBq.m{sup ?3} and 2.98 to 4.50 mBq.m{sup ?3}.

  17. Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 Citation Details In-Document Search Title: Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 ...

  18. Energy Dependence of Fission Product Yields for 239Pu, 235U,...

    Office of Scientific and Technical Information (OSTI)

    Energy Dependence of Fission Product Yields for 239Pu, 235U, and 238U Citation Details In-Document Search Title: Energy Dependence of Fission Product Yields for 239Pu, 235U, and ...

  19. (U) CIELO: Status of 239Pu Evaluation (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    (U) CIELO: Status of 239Pu Evaluation Citation Details In-Document Search Title: (U) CIELO: Status of 239Pu Evaluation Authors: Chadwick, Mark B. 1 ; Kahler, Albert C. III 1 ; ...

  20. Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 (Technical...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 Citation Details In-Document Search Title: Nuclear Design of Fissile Pu and HEU LIFE Engine - NA22 You ...

  1. (U) CIELO: Status of 239Pu Evaluation (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    (U) CIELO: Status of 239Pu Evaluation Citation Details In-Document Search Title: (U) CIELO: Status of 239Pu Evaluation You are accessing a document from the Department of ...

  2. Summary of Pu u O o - Kupaianaha Eruption, Kilauea Volcano, Hawaii...

    Open Energy Info (EERE)

    Pu u O o - Kupaianaha Eruption, Kilauea Volcano, Hawaii Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Summary of Pu u O o - Kupaianaha Eruption,...

  3. Atomic Structure and Phase Transformations in Pu Alloys

    SciTech Connect (OSTI)

    Schwartz, A J; Cynn, H; Blobaum, K M; Wall, M A; Moore, K T; Evans, W J; Farber, D L; Jeffries, J R; Massalski, T B

    2008-04-28

    Plutonium and plutonium-based alloys containing Al or Ga exhibit numerous phases with crystal structures ranging from simple monoclinic to face-centered cubic. Only recently, however, has there been increased convergence in the actinides community on the details of the equilibrium form of the phase diagrams. Practically speaking, while the phase diagrams that represent the stability of the fcc {delta}-phase field at room temperature are generally applicable, it is also recognized that Pu and its alloys are never truly in thermodynamic equilibrium because of self-irradiation effects, primarily from the alpha decay of Pu isotopes. This article covers past and current research on several properties of Pu and Pu-(Al or Ga) alloys and their connections to the crystal structure and the microstructure. We review the consequences of radioactive decay, the recent advances in understanding the electronic structure, the current research on phase transformations and their relations to phase diagrams and phase stability, the nature of the isothermal martensitic {delta} {yields} {alpha}{prime} transformation, and the pressure-induced transformations in the {delta}-phase alloys. New data are also presented on the structures and phase transformations observed in these materials following the application of pressure, including the formation of transition phases.

  4. Selection and Evaluation of a new Pu Density Measurement Fluid

    SciTech Connect (OSTI)

    Dziewinska, Krystyna; Peters, Michael A; Martinez, Patrick P; Dziewinski, Jacek J; Pugmire, David L; Trujillo, Stephen M; La Verne, Jake A; Rajesh, P

    2009-01-01

    This paper summarizes efforts leading to selection of a new fluid for the determination of the density of large Pu parts. Based on an extended literature search, perfluorotributylamine (FC-43) was chosen for an experimental study. Plutonium coupon corrosion studies were performed by exposing Pu to deaerated and aerated solutions and measuring corrosion gravimetrically. Corrosion rates were determined. Samples of deaerated and aerated perfuluorotributylamine (FC-43) were also irradiated with {sup 60}Co gamma rays (96 Gy/min) to various doses. The samples were extracted with NaOH and analyzed by IC and showed the presence of F and Cl{sup -}. The G-values were established. In surface study experiments Pu coupons were exposed to deaerated and aerated solutions of FC-43 and analyzed by X-ray photoelectron spectroscopy (XPS). The XPS data indicate that there is no detectable surface effect caused by the new fluid. In conclusion the FC-43 was determined to be a very effective and practical fluid for Pu density measurements.

  5. Bulk characterization of (U, Pu) mixed carbide fuel for distribution of plutonium

    SciTech Connect (OSTI)

    Devi, K. V. Vrinda Khan, K. B.; Biju, K.; Kumar, Arun

    2015-06-24

    Homogeneous distribution of plutonium in (U, Pu) mixed fuels is important from fuel performance as well as reprocessing point of view. Radiation imaging and assay techniques are employed for the detection of Pu rich agglomerates in the fuel. A simulation study of radiation transport was carried out to analyse the technique of autoradiography so as to estimate the minimum detectability of Pu agglomerates in MC fuel with nominal PuC content of 70% using Monte Carlo simulations.

  6. Possible experimental evidence for the presence of double octupole states in {sup 240}Pu

    SciTech Connect (OSTI)

    Pascu, S.; Spieker, M.; Bucurescu, D.; Faestermann, T.; Hertenberger, R.; Skalacki, S.; Weber, S.; Wirth, H. F.; Zamfir, N. V.; Zilges, A.

    2012-10-20

    Excited states in the {sup 240}Pu nucleus have been studied by means of the (p,t) reaction using the Q3D spectrometer and the focal plane detector from Munich. The comparison between experimental angular distributions and the DWBA calculations allowed the extraction of relative two-neutron transfer strengths. These observables may reveal important information about the structure of different states. The experimental two neutron strength for the 0{sup +}{sub 2} and 0{sup +}{sub 3} states is found in good agreement with the predictions of the IBA model, confirming the double octupole nature for the 0{sup +}{sub 2} state proposed in the previous studies.

  7. Post-Irradiation Examination of 237Np Targets for 238Pu Production

    SciTech Connect (OSTI)

    Morris, Robert Noel [ORNL; Baldwin, Charles A [ORNL; Hobbs, Randy W [ORNL; Schmidlin, Joshua E [ORNL

    2015-01-01

    Oak Ridge National Laboratory is recovering the US 238Pu production capability and the first step in the process has been to evaluate the performance of a 237Np target cermet pellet encased in an aluminum clad. The process proceeded in 3 steps; the first step was to irradiate capsules of single pellets composed of NpO2 and aluminum power to examine their shrinkage and gas release. These pellets were formed by compressing sintered NpO2 and aluminum powder in a die at high pressure followed by sintering in a vacuum furnace. Three temperatures were chosen for sintering the solution precipitated NpO2 power used for pellet fabrication. The second step was to irradiate partial targets composed of 8 pellets in a semi-prototypical arrangement at the two best performing sintering temperatures to determine which temperature gave a pellet that performed the best under the actual planned irradiation conditions. The third step was to irradiate ~50 pellets in an actual target configuration at design irradiation conditions to assess pellet shrinkage and gas release, target heat transfer, and dimensional stability. The higher sintering temperature appeared to offer the best performance after one cycle of irradiation by having the least shrinkage, thus keeping the heat transfer gap between the pellets and clad small minimizing the pellet operating temperature. The final result of the testing was a target that can meet the initial production goals, satisfy the reactor safety requirements, and can be fabricated in production quantities. The current focus of the program is to verify that the target can be remotely dissembled, the pellets dissolved, and the 238Pu recovered. Tests are being conducted to examine these concerns and to compare results to code predictions. Once the performance of the full length targets has been quantified, the pellet 237Np loading will be revisited to determine if it can be increased to increase 238Pu production.

  8. Np and Pu Sorption to Manganese Oxide Minerals

    SciTech Connect (OSTI)

    Zhao, P; Johnson, M R; Roberts, S K; Zavarin, M

    2005-08-30

    Manganese oxide minerals are a significant component of the fracture lining mineralogy at Yucca Mountain (Carlos et al., 1993) and within the tuff-confining unit at Yucca Flat (Prothro, 1998), Pahute Mesa (Drellack et al., 1997), and other locations at the Nevada Test Site (NTS). Radionuclide sorption to manganese oxide minerals was not included in recent Lawrence Livermore National Laboratory (LLNL) hydrologic source term (HST) models which attempt to predict the migration behavior of radionuclides away from underground nuclear tests. However, experiments performed for the Yucca Mountain Program suggest that these minerals may control much of the retardation of certain radionuclides, particularly Np and Pu (Triay et al., 1991; Duff et al., 1999). As a result, recent HST model results may significantly overpredict radionuclide transport away from underground nuclear tests. The sorption model used in HST calculations performed at LLNL includes sorption to iron oxide, calcite, zeolite, smectite, and mica minerals (Zavarin and Bruton 2004a; 2004b). For the majority of radiologic source term (RST) radionuclides, we believe that this accounts for the dominant sorption processes controlling transport. However, for the case of Np, sorption is rather weak to all but the iron and manganese oxides (Figure 1). Thus, we can expect to significantly reduce predicted Np transport by accounting for Np sorption to manganese oxides. Similarly, Pu has been shown to be predominantly associated with manganese oxides in Yucca Mountain fractured tuffs (Duff et al., 1999). Recent results on colloid-facilitated Pu transport (Kersting and Reimus, 2003) also suggest that manganese oxide coatings on fracture surfaces may compete with colloids for Pu, thus reducing the effects of colloid-facilitated Pu transport (Figure 1b). The available data suggest that it is important to incorporate Np and Pu sorption to manganese oxides in reactive transport models. However, few data are available for

  9. Slow Neutron Velocity Spectrometer Transmission Studies Of Pu

    DOE R&D Accomplishments [OSTI]

    Havens, W. W. Jr.; Melkonian, E.; Rainwater, L. J.; Levin, M.

    1951-05-28

    The slow neutron transmission of several samples of Pu has been investigated with the Columbia Neutron Velocity Spectrometer. Data are presented in two groups, those covering the energy region from 0 to 6 ev, and those covering the region above 6 ev. Below 6 ev the resolution was relatively good, and a detailed study of the cross section variation was made. Work above 6 ev consisted of merely locating levels and obtaining a rough idea of their strengths.

  10. NR Pu SEIS Advisory 07272012_Clean

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

    NPT Enters Into Force New York, United States The Treaty on the Non-Proliferation of Nuclear Weapons (NPT) goes into effect

    NPT NNSA Labs host U.S. and Nuclear Non-Proliferation Treaty (NPT) Non-Nuclear Weapon State Representatives NNSA Principal Deputy Administrator Madelyn Creedon with SNL Director and President Jill Hruby welcome Department of State Representatives and seven NPT Non-Nuclear Weapon State Representatives for 2nd NPT Transparency Visit. WASHINGTON - On October 26 and 27,

  11. QUALIFICATION OF THE SAVANNAH RIVER SITE 252CF SHUFFLER FOR RECEIPT VERIFICATION MEASUREMENTS OF MIXED U-PU OXIDES STORED IN 9975 SHIPPING CONTAINERS

    SciTech Connect (OSTI)

    Dubose, F.

    2011-05-26

    To extend their ability to perform accountability and verification measurements of {sup 235}U in a U-Pu oxide matrix, the K-Area Material Storage facility commissioned the development and construction of a Passive/Active {sup 252}Cf Shuffler. A series of {sup 252}Cf, PuO{sub 2}, and U-Pu oxide standards, in addition to a single U{sub 3}O{sub 8} standard, were measured to characterize and calibrate the shuffler. Accompanying these measurements were simulations using MCNP5/MCNPX, aimed at isolating the neutron countrate contributions for each of the isotopes present. Two calibration methods for determining the {sup 235}U content in mixed UPu oxide were then developed, yielding comparable results. The first determines the {sup 235}U mass by estimating the {sup 239}Pu/{sup 235}U ratio-dependent contributions from the primary delayed neutron contributors. The second defines an average linear response based on the {sup 235}U and {sup 239}Pu mass contents. In each case, it was observed that self-shielding due to {sup 235}U mass has a large influence on the observed rates, requiring bounds on the applicable limits of each calibration method.

  12. First-principles elastic properties of (alpha)-Pu

    SciTech Connect (OSTI)

    Soderlind, P; Klepeis, J E

    2008-11-04

    Density-functional electronic structure calculations have been used to investigate the ambient pressure and low temperature elastic properties of the ground-state {alpha} phase of plutonium metal. The electronic structure and correlation effects are modeled within a fully relativistic anti-ferromagnetic treatment with a generalized gradient approximation for the electron exchange and correlation functionals. The 13 independent elastic constants, for the monoclinic {alpha}-Pu system, are calculated for the observed geometry. A comparison of the results with measured data from resonant ultrasound spectroscopy for a cast sample is made.

  13. Analysis of Pu-Only Partitioning Strategies in LMFBR Fuel Cycles...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Analysis of Pu-Only Partitioning Strategies in LMFBR Fuel Cycles Sodium cooled Fast Reactors (SFR) have been under consideration for ...

  14. As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt.% minor actinides and 0-1.5 wt% rare-earth elements

    SciTech Connect (OSTI)

    Janney, Dawn E. Kennedy, J. Rory

    2010-11-15

    The Idaho National Laboratory (INL) is investigating U-Pu-Zr alloys with low concentrations of minor actinides (Np and Am) and rare-earth elements (La, Ce, Pr, and Nd) as possible nuclear fuels to be used to transmute minor actinides. Alloys with compositions 60U-20Pu-3Am-2Np-15Zr, 42U-30Pu-5Am-3Np-20Zr, 59U-20Pu-3Am-2Np-1RE-15Zr, 58.5U-20Pu-3Am-2Np-1.5RE-15Zr, 41U-30Pu-5Am-3Np-1RE-20Zr, and 40.5U-30Pu-5Am-3Np-1.5RE-20Zr (where numbers represent weight percents of each element and RE is a rare-earth alloy consisting of 6% La, 16% Pr, 25% Ce, and 53% Nd by weight) were arc-melted and vacuum cast as fuel pins approximately 4 mm in diameter. The as-cast pins were sectioned, polished, and examined by scanning electron microscopy. Each alloy contains high-Zr inclusions surrounded by a high-actinide matrix. Alloys with rare-earth elements also contain inclusions that are high in these elements. Within the matrix, concentrations of U and Zr vary inversely, while concentrations of Np and Pu appear approximately constant. Am occurs in the matrix and with some high-rare-earth inclusions, and occasionally as high-Am inclusions in samples without rare-earth elements. - Research Highlights: {yields}Microstructures consist of high-Zr inclusions surrounded by a high-actinide matrix. {yields}Alloys with rare-earth (RE) elements contain inclusions that are high in REs. {yields}Concentrations of U and Zr vary inversely in the matrix. {yields}Am occurs in the matrix and with high-RE inclusions.

  15. Thermal Analysis of ZPPR High Pu Content Stored Fuel

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

    Solbrig, Charles W.; Pope, Chad L.; Andrus, Jason P.

    2014-01-01

    The Zero Power Physics Reactor (ZPPR) operated from April 18, 1969, until 1990. ZPPR operated at low power for testing nuclear reactor designs. This paper examines the temperature of Pu content ZPPR fuel while it is in storage. Heat is generated in the fuel due to Pu and Am decay and is a concern for possible cladding damage. Damage to the cladding could lead to fuel hydriding and oxidizing. A series of computer simulations were made to determine the range of temperatures potentially occuring in the ZPPR fuel. The maximum calculated fuel temperature is 292°C (558°F). Conservative assumptions in themore » model intentionally overestimate temperatures. The stored fuel temperatures are dependent on the distribution of fuel in the surrounding storage compartments, the heat generation rate of the fuel, and the orientation of fuel. Direct fuel temperatures could not be measured but storage bin doors, storage sleeve doors, and storage canister temperatures were measured. Comparison of these three temperatures to the calculations indicates that the temperatures calculated with conservative assumptions are, as expected, higher than the actual temperatures. The maximum calculated fuel temperature with the most conservative assumptions is significantly below the fuel failure criterion of 600°C (1,112°F).« less

  16. Post-Irradiation Examination of 237Np Targets for 238Pu Production

    SciTech Connect (OSTI)

    Morris, Robert Noel; Baldwin, Charles A; Hobbs, Randy W; Schmidlin, Joshua E

    2015-01-01

    Oak Ridge National Laboratory is recovering the US 238Pu production capability and the first step in the process has been to evaluate the performance of a 237Np target cermet pellet encased in an aluminum clad. The process proceeded in 3 steps; the first step was to irradiate capsules of single pellets composed of NpO2 and aluminum power to examine their shrinkage and gas release. These pellets were formed by compressing sintered NpO2 and aluminum powder in a die at high pressure followed by sintering in a vacuum furnace. Three temperatures were chosen for sintering the solution precipitated NpO2 power used for pellet fabrication. The second step was to irradiate partial targets composed of 8 pellets in a semi-prototypical arrangement at the two best performing sintering temperatures to determine which temperature gave a pellet that performed the best under the actual planned irradiation conditions. The third step was to irradiate ~50 pellets in an actual target configuration at design irradiation conditions to assess pellet shrinkage and gas release, target heat transfer, and dimensional stability. The higher sintering temperature appeared to offer the best performance after one cycle of irradiation by having the least shrinkage, thus keeping the heat transfer gap between the pellets and clad small minimizing the pellet operating temperature. The final result of the testing was a target that can meet the initial production goals, satisfy the reactor safety requirements, and can be fabricated in production quantities. The current focus of the program is to verify that the target can be remotely dissembled, the pellets dissolved, and the 238Pu recovered. Tests are being conducted to examine these concerns and to compare results to code predictions. Once the performance of the full length targets has been quantified, the pellet 237Np loading will be revisited to determine if it can be

  17. LAKESHORE AVON BR ANT-EDEN ALD EN-LANC ASTER AU BURN W SH ELDON

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

    81 § ¨ ¦ 81 LAKESHORE AVON BR ANT-EDEN ALD EN-LANC ASTER AU BURN W SH ELDON CALEDONIA HURON C REEK LEIC EST ER COL DEN ASH FORD INDIAN FALLS LAWTONS SAR DINIA RPD-037 -2 GLENWOOD PU LASKI PAVILION CON CORD COL LINS N ELM A ORC HARD PARK-H AMBU RG DANLEY CORNERS ST ILLWAT ER CHAFF EE-ARCAD E FAYETT E-WATERLOO LAKEVIEW JAVA SEN EC A W ELLER Y AU RORA E ZOAR BU FFALO TIOGA SILVER LAKE AKR ON ROM E RAT HBON E ALM A BET HANY WYOMING ULYSSES BR ANCH W SAN DY CREEK COL LINS BLOOMFIELD E LEBANON

  18. ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.

    SciTech Connect (OSTI)

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

    2009-02-23

    ZPR-6 Assembly 7 (ZPR-6/7) encompasses a series of experiments performed at the ZPR-6 facility at Argonne National Laboratory in 1970 and 1971 as part of the Demonstration Reactor Benchmark Program (Reference 1). Assembly 7 simulated a large sodium-cooled LMFBR with mixed oxide fuel, depleted uranium radial and axial blankets, and a core H/D near unity. ZPR-6/7 was designed to test fast reactor physics data and methods, so configurations in the Assembly 7 program were as simple as possible in terms of geometry and composition. ZPR-6/7 had a very uniform core assembled from small plates of depleted uranium, sodium, iron oxide, U{sub 3}O{sub 8} and Pu-U-Mo alloy loaded into stainless steel drawers. The steel drawers were placed in square stainless steel tubes in the two halves of a split table machine. ZPR-6/7 had a simple, symmetric core unit cell whose neutronic characteristics were dominated by plutonium and {sup 238}U. The core was surrounded by thick radial and axial regions of depleted uranium to simulate radial and axial blankets and to isolate the core from the surrounding room. The ZPR-6/7 program encompassed 139 separate core loadings which include the initial approach to critical and all subsequent core loading changes required to perform specific experiments and measurements. In this context a loading refers to a particular configuration of fueled drawers, radial blanket drawers and experimental equipment (if present) in the matrix of steel tubes. Two principal core configurations were established. The uniform core (Loadings 1-84) had a relatively uniform core composition. The high {sup 240}Pu core (Loadings 85-139) was a variant on the uniform core. The plutonium in the Pu-U-Mo fuel plates in the uniform core contains 11% {sup 240}Pu. In the high {sup 240}Pu core, all Pu-U-Mo plates in the inner core region (central 61 matrix locations per half of the split table machine) were replaced by Pu-U-Mo plates containing 27% {sup 240}Pu in the plutonium

  19. Glenwood Springs, Colorado: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Springs, Colorado: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 39.5505376, -107.3247762 Show Map Loading map... "minzoom":false,"mappingser...

  20. Gamma-ray Output Spectra from 239 Pu Fission

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

    Ullmann, John

    2015-05-25

    Gamma-ray multiplicities, individual gamma-ray energy spectra, and total gamma energy spectra following neutron-induced fission of 239Pu were measured using the DANCE detector at Los Alamos. Corrections for detector response were made using a forward-modeling technique based on propagating sets of gamma rays generated from a paramaterized model through a GEANT model of the DANCE array and adjusting the parameters for best fit to the measured spectra. The results for the gamma-ray spectrum and multiplicity are in general agreement with previous results, but the measured total gamma-ray energy is about 10% higher. A dependence of the gamma-ray spectrum on the gamma-raymore » multplicity was also observed. Global model calculations of the multiplicity and gamma energy distributions are in good agreement with the data, but predict a slightly softer total-energy distribution.« less

  1. DOE Plutonium Disposition Study: Pu consumption in ALWRs. Volume 1, Final report

    SciTech Connect (OSTI)

    Not Available

    1993-05-15

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U0{sub 2} plant design is discussed here.

  2. ZPR-6 assembly 7 high {sup 240} PU core : a cylindrical assemby with mixed (PU, U)-oxide fuel and a central high {sup 240} PU zone.

    SciTech Connect (OSTI)

    Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Nuclear Engineering Division; Inst. of Physics and Power Engineering

    2007-10-01

    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 to form the basis for criticality safety 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. The term 'benchmark' in a ZPR program connotes a particularly simple loading aimed at gaining basic reactor physics insight, as opposed to studying a reactor design. In fact, the ZPR-6/7 Benchmark Assembly (Reference 1) had a very simple core unit cell assembled from plates of depleted uranium, sodium, iron oxide, U3O8, and plutonium. The ZPR-6/7 core cell-average composition is typical of the interior region of liquid-metal fast breeder reactors (LMFBRs) of the era. It was one part of the Demonstration Reactor Benchmark Program,a which provided integral experiments characterizing the important features of demonstration

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

    SciTech Connect (OSTI)

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

    2010-06-23

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

  4. Rational Ligand Design for U(VI) and Pu(IV)

    SciTech Connect (OSTI)

    Szigethy, Geza

    2009-08-12

    , these ligands exhibited increased uranyl affinity compared to bis-Me-3,2-HOPO ligands. This result is due in part to their increased denticity, but is primarily the result of the presence of the TAM moiety. In an effort to explore the relatively unexplored coordination chemistry of Pu(IV) with bidentate moieties, a series of Pu(IV) complexes were also crystallized using bidentate hydroxypyridinone and hydroxypyrone ligands. The geometries of these complexes are compared to that of the analogous Ce(IV) complexes. While in some cases these showed the expected structural similarities, some ligand systems led to significant coordination changes. A series of crystal structure analyses with Ce(IV) indicated that these differences are most likely the result of crystallization condition differences and solvent inclusion effects.

  5. Summary of EXAFS results on Cd-doped PuRhIn5 (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Summary of EXAFS results on Cd-doped PuRhIn5 Authors: Booth, C H ; Bauer, E D ; Tobin, J G Publication Date: 2014-06-12 OSTI Identifier: ...

  6. Detection and Quantification of Pu(III, IV, V, and VI) Using...

    Office of Scientific and Technical Information (OSTI)

    a1.0-meter Liquid Core Waveguide Citation Details In-Document Search Title: Detection and Quantification of Pu(III, IV, V, and VI) Using a1.0-meter Liquid Core Waveguide ...

  7. Detection and Quantification of Pu(III, IV, V, and VI) Using...

    Office of Scientific and Technical Information (OSTI)

    a1.0-meter Liquid Core Waveguide Citation Details In-Document Search Title: Detection and Quantification of Pu(III, IV, V, and VI) Using a1.0-meter Liquid Core Waveguide You ...

  8. First-principles study of the Kondo physics of a single Pu impurity...

    Office of Scientific and Technical Information (OSTI)

    As a foundational study to probe the role of local electronic correlations in Pu, we use the local-density approximation together with a continuous-time quantum Monte Carlo ...

  9. High- and low-Am RE inclusion phases in a U-Np-Pu-Am-Zr alloy

    SciTech Connect (OSTI)

    Janney, Dawn E.; Madden, James W.; O'Holleran, Thomas P.; Kennedy, J. Rory

    2015-03-01

    Structural, microstructural, and microchemical data were collected from rare-earth inclusions in an as-cast U-Pu-Zr alloy with ~3 at% Am, 2% Np, and 9% rare-earth elements (La, Ce, Pr, and Nd). Two RE phases with different concentrations of Am were identified. The composition of high-Am RE inclusions is ~2-5 at% La, 15-20 % Ce, 5-10% Pr, 25-45% Nd, 1% Np, 5-10% Pu, and 10-20% Am. Some areas also have O, although this does not appear to be an essential part of the high-Am RE phase. The inclusions have a face-centered cubic structure with a lattice parameter a ~ 0.54 nm. The composition of the only low-Am RE inclusion studied in detail is ~~35-40 at% O, 40-45 % Nd, 1-2% Zr, 4-5% La, 9-10% Ce, and 6-7% Pr. This inclusion is an oxide with a crystal structure similar to the room-temperature structure of Nd2O3. Microstructural features suggest that oxidation occurred during casting, and that early crystallization of high-temperature oxides led to formation of two distinct RE phases.

  10. Mass transport properties of Pu/DT mixtures from orbital free molecular dynamics simulations

    SciTech Connect (OSTI)

    Kress, Joel David; Ticknor, Christopher; Collins, Lee A.

    2015-09-16

    Mass transport properties (shear viscosity and diffusion coefficients) for Pu/DT mixtures were calculated with Orbital Free Molecular Dynamics (OFMD). The results were fitted to simple functions of mass density (for ρ=10.4 to 62.4 g/cm3) and temperature (for T=100 up to 3,000 eV) for Pu/DT mixtures consisting of 100/0, 25/75, 50/50, and 75/25 by number.

  11. Discovery of Pu-based superconductors and relation to other classes of

    Office of Scientific and Technical Information (OSTI)

    unconventional superconductors (Conference) | SciTech Connect Discovery of Pu-based superconductors and relation to other classes of unconventional superconductors Citation Details In-Document Search Title: Discovery of Pu-based superconductors and relation to other classes of unconventional superconductors No abstract prepared. Authors: Bauer, Eric D. [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2012-08-20 OSTI Identifier: 1049339 Report Number(s):

  12. Physics of sup 238 Pu production in the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Rawlins, J.A.; Schmittroth, F.A.; Mann, F.M.; Schenter, R.E.; Lu, A.H.; Carter, L.L.; Wootan, D.W.; Schwarz, R.A.; Brager, H.R.; Matsumoto, W.Y.

    1989-11-01

    Westinghouse Hanford Company conducted an assessment of producing {sup 238}Pu in the Fast Flux Test Facility (FFTF), a U.S. Department of Energy (DOE) reactor located near Richland, Washington. The goal of the assessment was to determine whether the FFTF can produce at least 15 kg/yr of {sup 238}Pu to support the needs of the U.S. space program. Plutonium-238, with its 87.7-yr half-life and relatively pure alpha-particle decay mode, is an ideal power source for deep-space missions. The DOE is evaluating options for future {sup 238}Pu production, and the FFTF is a preferred candidate. The key technical issue for FFTF production is the isotopic purity of the product plutonium. FFTF production of at least 15 kg/yr of {sup 238}Pu is feasible. An FFTF physics test was completed and will reduce the large calculational uncertainties in {sup 236}Pu content, and the final test results will allow final production assembly design optimization. Use of the FFTF for {sup 238}Pu production can satisfy the needs of the U.S. space program for many years with a modern reactor that has an outstanding operational record.

  13. PU/SS EUTECTIC ASSESSMENT IN 9975 PACKAGINGS IN A STORAGE FACILITY DURING EXTENDED FIRE

    SciTech Connect (OSTI)

    Gupta, N.

    2012-03-26

    In a radioactive material (RAM) packaging, the formation of eutectic at the Pu/SS (plutonium/stainless steel) interface is a serious concern and must be avoided to prevent of leakage of fissile material to the environment. The eutectic temperature for the Pu/SS is rather low (410 C) and could seriously impact the structural integrity of the containment vessel under accident conditions involving fire. The 9975 packaging is used for long term storage of Pu bearing materials in the DOE complex where the Pu comes in contact with the stainless steel containment vessel. Due to the serious consequences of the containment breach at the eutectic site, the Pu/SS interface temperature is kept well below the eutectic formation temperature of 410 C. This paper discusses the thermal models and the results for the extended fire conditions (1500 F for 86 minutes) that exist in a long term storage facility and concludes that the 9975 packaging Pu/SS interface temperature is well below the eutectic temperature.

  14. Stress and Diffusion in Stored Pu ZPPR Fuel from Alpha Generation

    SciTech Connect (OSTI)

    Charles W. Solbrig; Chad L. Pope; Jason P. Andrus

    2014-07-01

    ZPPR (Zero Power Physics Reactor) is a research reactor that has been used to investigate breeder reactor fuel designs. The reactor has been dismantled but its fuel is still stored there. Of concern are its plutonium containing metal fuel elements which are enclosed in stainless steel cladding with gas space filled with helium–argon gas and welded air tight. The fuel elements which are 5.08 cm by 0.508 cm up to 20.32 cm long (2 in × 0.2 in × 8 in) were manufactured in 1968. A few of these fuel elements have failed releasing contamination raising concern about the general state of the large number of other fuel elements. Inspection of the large number of fuel elements could lead to contamination release so analytical studies have been conducted to estimate the probability of failed fuel elements. This paper investigates the possible fuel failures due to generation of helium in the metal fuel from the decay of Pu and its possible damage to the fuel cladding from metal fuel expansion or from diffusion of helium into the fuel gas space. This paper (1) calculates the initial gas loading in a fuel element and its internal free volume after it has been brought into the atmosphere at ZPPR, (2) shows that the amount of helium generated by decay of Pu over 46 years since manufacture is significantly greater than this initial loading, (3) determines the amount of fuel swelling if the helium stays fixed in the fuel plate and estimates the amount of helium which diffuses out of the fuel plate into the fuel plenum assuming the helium does not remain fixed in the fuel plate but can diffuse to the plenum and possibly through the cladding. Since the literature is not clear as to which possibility occurs, as with Schroedinger’s cat, both possibilities are analyzed. The paper concludes that (1) if the gas generated is fixed in the fuel, then the fuel swelling it can cause would not cause any fuel failure and (2) if the helium does diffuse out of the fuel (in accordance

  15. Thermal Analysis of ZPPR High Pu Content Stored Fuel

    SciTech Connect (OSTI)

    Charles W. Solbrig; Chad Pope; Jason Andrus

    2014-09-01

    This paper estimates the temperature of high Pu content ZPPR fuel while in storage to determine the probablilty of fuel damage during storage. The Zero Power Physics Reactor (ZPPR) is an experimental reactor which has been decomissioned. It ran only at extremely low power, for testing nuclear reactor designs and was operated as a criticality facility from April 18, 1969 until decommissioned in 1990. Its fuel was manufactured in 1967 and has been in storage since the reactor was decomissioned. Heat is generated in the fuel due to Pu and Am decay and is a concern for possible fuel damage. Any damage to the cladding would be expected to lead to the fuel hydriding and oxidizing over a long period of storage as was described in the analysis of the damage to the ZPPR uranium fuel resulting in the fuel becoming unuseable and a large potential source of contamination. (Ref. Solbrig, 1994). A series of computer runs were made to scope out the range of temperatures that can occur in the ZPPR fuel in storage. The maximum calculated conservative fuel temperature is high (292 degrees C [558 degrees F]) in spite of the fact that the fuel element heat generation rates seem quite low, between 35 and 10 W for containers (called clamshells) full of fuel. However, the ZPPR storage bins, built for safeguards, are very effective insulators. The calculated clamshells and the cavity doors temperatures are also high. No record exists of people receiving skin burns by touching the cavity doors or clamshells, which indicates the computed temperatures may be higher than actual. (Note, gloves are worn when handling hotter clamshells.) Given the high calculated temperatures, a cursory measurement program was conducted to calibrate the calculated results. The measurement of bin doors, cavity doors, and clamshell temperatures would be easy to make if it were not for regulations resulting from security and potential contamination. Due to conservative assumptions in the model like high heat

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

    SciTech Connect (OSTI)

    Maxwell, S.

    2010-07-26

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

  17. Isothermal Martensitic and Pressure-Induced Delta to Alpha-Prime Phase Transformations in a Pu-Ga Alloy

    SciTech Connect (OSTI)

    Schwartz, A J; Wall, M A; Farber, D L; Moore, K T; Blobaum, K M

    2008-01-18

    A well-homogenized Pu-2 at.% Ga alloy can be retained in the metastable face-centered cubic {delta} phase at room temperature. Ultimately, this metastable {delta} phase will decompose via a eutectoid transformation to the thermodynamically stable monoclinic {alpha} phase and the intermetallic compound Pu{sub 3}Ga over a period of approximately 10,000 years [1]. In addition, these low solute-containing {delta}-phase Pu alloys are metastable with respect to an isothermal martensitic phase transformation to the {alpha}{prime} phase during low temperature excursions [2, 3] and are also metastable with respect to a {delta} {yields} {alpha}{prime} phase transformation with increases in pressure [3-5]. The low temperature {delta} {yields} {alpha}{prime} isothermal martensitic phase transformation in the Pu-2 at.% Ga alloy only goes to {approx}25% completion with the resultant {approx}20 {micro}m long by 2 {micro}m wide lath-shaped {alpha}{prime} particles dispersed within the {delta} matrix. In recently reported studies, Faure et al. [4] have observed a {delta} {yields} {gamma} {yields} {alpha}{prime} pressure-induced phase transformation sequence during a diamond anvil cell investigation and, based on x-ray diffraction and density and compressibility experiments, Harbur [5] has concluded that both {alpha}{prime} and an amorphous phase are present in samples that were pressurized and recovered. In this work, a large volume moissanite anvil cell is constructed to permit the pressurization and recovery of specimens of a size suitable for TEM and electron diffraction studies. The cell, shown in Fig. 1, has an overall diameter of 101.6 mm, a moissanite anvil diameter of 9.00 mm, a culet size of 3 mm, and a spring steel gasket 0.5 mm thick with a hole diameter of 2.5 mm. A 2.3 mm diameter by 100 {micro}m thick sample of {delta}-phase Pu-2 at.% Ga is compressed at a rate of approximately 0.05 GPa/minute to {approx}1 GPa to induce the phase transformation to {alpha

  18. Measurement of the 240Pu/239Pu mass ratio using a transition-edge-sensor microcalorimeter for total decay energy spectroscopy

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

    Hoover, Andrew S.; Bond, Evelyn M.; Croce, Mark P.; Holesinger, Terry G.; Kunde, Gerd J.; Rabin, Michael W.; Wolfsberg, Laura E.; Bennett, Douglas A.; Hays-Wehle, James P.; Schmidt, Dan R.; et al

    2015-02-27

    In this study, we have developed a new category of sensor for measurement of the 240Pu/239Pu mass ratio from aqueous solution samples with advantages over existing methods. Aqueous solution plutonium samples were evaporated and encapsulated inside of a gold foil absorber, and a superconducting transition-edge-sensor microcalorimeter detector was used to measure the total reaction energy (Q-value) of nuclear decays via heat generated when the energy is thermalized. Since all of the decay energy is contained in the absorber, we measure a single spectral peak for each isotope, resulting in a simple spectral analysis problem with minimal peak overlap. We foundmore » that mechanical kneading of the absorber dramatically improves spectral quality by reducing the size of radioactive inclusions within the absorber to scales below 50 nm such that decay products primarily interact with atoms of the host material. Due to the low noise performance of the microcalorimeter detector, energy resolution values of 1 keV fwhm (full width at half-maximum) at 5.5 MeV have been achieved, an order of magnitude improvement over α-spectroscopy with conventional silicon detectors. We measured the 240Pu/239Pu mass ratio of two samples and confirmed the results by comparison to mass spectrometry values. These results have implications for future measurements of trace samples of nuclear material.« less

  19. Measurement of the 240Pu/239Pu mass ratio using a transition-edge-sensor microcalorimeter for total decay energy spectroscopy

    SciTech Connect (OSTI)

    Hoover, Andrew S.; Bond, Evelyn M.; Croce, Mark P.; Holesinger, Terry G.; Kunde, Gerd J.; Rabin, Michael W.; Wolfsberg, Laura E.; Bennett, Douglas A.; Hays-Wehle, James P.; Schmidt, Dan R.; Swetz, Daniel; Ullom, Joel N.

    2015-02-27

    In this study, we have developed a new category of sensor for measurement of the 240Pu/239Pu mass ratio from aqueous solution samples with advantages over existing methods. Aqueous solution plutonium samples were evaporated and encapsulated inside of a gold foil absorber, and a superconducting transition-edge-sensor microcalorimeter detector was used to measure the total reaction energy (Q-value) of nuclear decays via heat generated when the energy is thermalized. Since all of the decay energy is contained in the absorber, we measure a single spectral peak for each isotope, resulting in a simple spectral analysis problem with minimal peak overlap. We found that mechanical kneading of the absorber dramatically improves spectral quality by reducing the size of radioactive inclusions within the absorber to scales below 50 nm such that decay products primarily interact with atoms of the host material. Due to the low noise performance of the microcalorimeter detector, energy resolution values of 1 keV fwhm (full width at half-maximum) at 5.5 MeV have been achieved, an order of magnitude improvement over α-spectroscopy with conventional silicon detectors. We measured the 240Pu/239Pu mass ratio of two samples and confirmed the results by comparison to mass spectrometry values. These results have implications for future measurements of trace samples of nuclear material.

  20. Rapid fusion method for the determination of Pu, Np, and Am in large soil samples

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

    Maxwell, Sherrod L.; Culligan, Brian; Hutchison, Jay B.; McAlister, Daniel R.

    2015-02-14

    A new rapid sodium hydroxide fusion method for the preparation of 10-20 g soil samples has been developed by the Savannah River National Laboratory (SRNL). The method enables lower detection limits for plutonium, neptunium, and americium in environmental soil samples. The method also significantly reduces sample processing time and acid fume generation compared to traditional soil digestion techniques using hydrofluoric acid. Ten gram soil aliquots can be ashed and fused using the new method in 1-2 hours, completely dissolving samples, including refractory particles. Pu, Np and Am are separated using stacked 2mL cartridges of TEVA and DGA Resin and measuredmore » using alpha spectrometry. The method can be adapted for measurement by inductively-coupled plasma mass spectrometry (ICP-MS). Two 10 g soil aliquots of fused soil may be combined prior to chromatographic separations to further improve detection limits. Total sample preparation time, including chromatographic separations and alpha spectrometry source preparation, is less than 8 hours.« less

  1. Rapid fusion method for the determination of Pu, Np, and Am in large soil samples

    SciTech Connect (OSTI)

    Maxwell, Sherrod L.; Culligan, Brian; Hutchison, Jay B.; McAlister, Daniel R.

    2015-02-14

    A new rapid sodium hydroxide fusion method for the preparation of 10-20 g soil samples has been developed by the Savannah River National Laboratory (SRNL). The method enables lower detection limits for plutonium, neptunium, and americium in environmental soil samples. The method also significantly reduces sample processing time and acid fume generation compared to traditional soil digestion techniques using hydrofluoric acid. Ten gram soil aliquots can be ashed and fused using the new method in 1-2 hours, completely dissolving samples, including refractory particles. Pu, Np and Am are separated using stacked 2mL cartridges of TEVA and DGA Resin and measured using alpha spectrometry. The method can be adapted for measurement by inductively-coupled plasma mass spectrometry (ICP-MS). Two 10 g soil aliquots of fused soil may be combined prior to chromatographic separations to further improve detection limits. Total sample preparation time, including chromatographic separations and alpha spectrometry source preparation, is less than 8 hours.

  2. Study of Pu consumption in light water reactors: Evaluation of GE advanced boiling water reactor plants, compilation of Phase 1C task reports

    SciTech Connect (OSTI)

    Not Available

    1994-01-15

    This report summarizes the evaluations conducted during Phase 1C of the Pu Disposition Study have provided further results which reinforce the conclusions reached during Phase 1A & 1B: These conclusions clearly establish the benefits of the fission option and the use of the ABWR as a reliable, proven, well-defined and cost-effective means available to disposition the weapons Pu. This project could be implemented in the near-term at a cost and on a schedule being validated by reactor plants currently under construction in Japan and by cost and schedule history and validated plans for MOX plants in Europe. Evaluations conducted during this phase have established that (1) the MOX fuel is licensable based on existing criteria for new fuel with limited lead fuel rod testing, (2) that the applicable requirements for transport, handling and repository storage can be met, and (3) that all the applicable safeguards criteria can be met.

  3. EIS-0299: Proposed Production of Plutonium-238 (Pu-238) for Use in Advanced Radioisotope Power Systems (RPS) for Space Missions

    Broader source: Energy.gov [DOE]

    This EIS is for the proposed production of plutonium-238 (Pu-238) using one or more DOE research reactors and facilities.

  4. Comprehensive appraisal of {sup 239+240}Pu in soils around Rocky Flats, Colorado

    SciTech Connect (OSTI)

    Litaor, M.I.; Allen, L.; Ellerbroek, D.

    1995-12-01

    Plutonium contamination of soils around Rocky Flats Environmental & Technology Site, near Golden, Colorado, resulted from past outdoor storage practices and subsequent remobilization due to inadequate cleanup practices. Until now human-health risk assessment has not been performed because of a lack of sufficient information regarding the spatial extent of {sup 239+240}Pu in soils. The purpose of this work was to elucidate the extent of plutonium contamination in surface soils, and to assess the uncertainty associated with the spatial distribution of {sup 239+240}Pu around Rocky Flats Environmental & Technology Site.

  5. Hidden disorder in the α'→δ transformation of Pu-1.9 at.% Ga

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

    Jeffries, J. R.; Manley, M. E.; Wall, M. A.; Blobaum, K. J. M.; Schwartz, A. J.

    2012-06-06

    Enthalpy and entropy are thermodynamic quantities critical to determining how and at what temperature a phase transition occurs. At a phase transition, the enthalpy and temperature-weighted entropy differences between two phases are equal (ΔH=TΔS), but there are materials where this balance has not been experimentally or theoretically realized, leading to the idea of hidden order and disorder. In a Pu-1.9 at. % Ga alloy, the δ phase is retained as a metastable state at room temperature, but at low temperatures, the δ phase yields to a mixed-phase microstructure of δ- and α'-Pu. The previously measured sources of entropy associated withmore » the α'→δ transformation fail to sum to the entropy predicted theoretically. We report an experimental measurement of the entropy of the α'→δ transformation that corroborates the theoretical prediction, and implies that only about 65% of the entropy stabilizing the δ phase is accounted for, leaving a missing entropy of about 0.5 kB/atom. Some previously proposed mechanisms for generating entropy are discussed, but none seem capable of providing the necessary disorder to stabilize the δ phase. This hidden disorder represents multiple accessible states per atom within the δ phase of Pu that may not be included in our current understanding of the properties and phase stability of δ-Pu.« less

  6. Relativistic energy density functionals: Low-energy collective states of {sup 240}Pu and {sup 166}Er

    SciTech Connect (OSTI)

    Li, Z. P.; Niksic, T.; Vretenar, D.; Ring, P.; Meng, J.

    2010-06-15

    The empirical relativistic density-dependent, point-coupling energy density functional, adjusted exclusively to experimental binding energies of a large set of deformed nuclei with Aapprox =150-180 and Aapprox =230-250, is tested with spectroscopic data for {sup 166}Er and {sup 240}Pu. Starting from constrained self-consistent triaxial relativistic Hartree-Bogoliubov calculations of binding energy maps as functions of the quadrupole deformation in the beta-gamma plane, excitation spectra and E2 transition probabilities are calculated as solutions of the corresponding microscopic collective Hamiltonian in five dimensions for quadrupole vibrational and rotational degrees of freedom and compared with available data on low-energy collective states.

  7. Use of PuBe source to simulate neutron-induced single event upsets in static RAMS

    SciTech Connect (OSTI)

    Normand, E.; Wert, J.L.; Doherty, W.R.; Oberg, D.L.; Measel, P.R.; Criswell, T.L.

    1988-12-01

    Neutron induced single event upsets were measured in static memory devices using a 10 curie PuBe source. The PuBe source conservatively overestimates the spectrum of fast neutrons emitted by a radioisotope thermoelectric generator (RTG). For the 93L422, the neutron-induced upset rate compared favorably with calculated values derived using the burst generation concept. By accounting for the production of the ionizing particles by the PuBe and RTG neutron spectra, convenient upper bound SEU upset rates for memory devices near an RTG can be derived.

  8. Multiscale Speciation of U and Pu at Chernobyl, Hanford, Los...

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

    at McGuire AFB in 1960, measured with the two micron focused x-ray beam at SSRL. EST June 2, 2015: Vol. 49, Iss. 11 The chemical speciation of potentially hazardous ...

  9. Savannah River Site: Plutonium Preparation Project (PuPP) at...

    Office of Environmental Management (EM)

    ... fuel rods will be de-clad and fuel pellets repackaged for on-site shipment to H-Canyon. ... the LANL design. 2. FIWF Fuel Disassembly, Download of Pellets, and Pellet Dissolution. ...

  10. TRISO-Fuel Element Performance Modeling for the Hybrid LIFE Engine with Pu Fuel Blanket

    SciTech Connect (OSTI)

    DeMange, P; Marian, J; Caro, M; Caro, A

    2010-02-18

    A TRISO-coated fuel thermo-mechanical performance study is performed for the hybrid LIFE engine to test the viability of TRISO particles to achieve ultra-high burnup of a weapons-grade Pu blanket. Our methodology includes full elastic anisotropy, time and temperature varying material properties for all TRISO layers, and a procedure to remap the elastic solutions in order to achieve fast fluences up to 30 x 10{sup 25} n {center_dot} m{sup -2} (E > 0.18 MeV). In order to model fast fluences in the range of {approx} 7 {approx} 30 x 10{sup 25} n {center_dot} m{sup -2}, for which no data exist, careful scalings and extrapolations of the known TRISO material properties are carried out under a number of potential scenarios. A number of findings can be extracted from our study. First, failure of the internal pyrolytic carbon (PyC) layer occurs within the first two months of operation. Then, the particles behave as BISO-coated particles, with the internal pressure being withstood directly by the SiC layer. Later, after 1.6 years, the remaining PyC crumbles due to void swelling and the fuel particle becomes a single-SiC-layer particle. Unrestrained by the PyC layers, and at the temperatures and fluences in the LIFE engine, the SiC layer maintains reasonably-low tensile stresses until the end-of-life. Second, the PyC creep constant, K, has a striking influence on the fuel performance of TRISO-coated particles, whose stresses scale almost inversely proportional to K. Obtaining more reliable measurements, especially at higher fluences, is an imperative for the fidelity of our models. Finally, varying the geometry of the TRISO-coated fuel particles results in little differences in the scope of fuel performance. The mechanical integrity of 2-cm graphite pebbles that act as fuel matrix has also been studied and it is concluded that they can reliable serve the entire LIFE burnup cycle without failure.

  11. Chemical speciation of U, Fe, and Pu in melt glass from nuclear weapons testing

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

    Pacold, J. I.; Lukens, W. W.; Booth, C. H.; Shuh, D. K.; Knight, K. B.; Eppich, G. R.; Holliday, K. S.

    2016-05-18

    We report that nuclear weapons testing generates large volumes of glassy materials that influence the transport of dispersed actinides in the environment and may carry information on the composition of the detonated device. We determine the oxidation state of U and Fe (which is known to buffer the oxidation state of actinide elements and to affect the redox state of groundwater) in samples of melt glass collected from three U.S. nuclear weapons tests. For selected samples, we also determine the coordination geometry of U and Fe, and we report the oxidation state of Pu from one melt glass sample. Wemore » find significant variations among the melt glass samples and, in particular, find a clear deviation in one sample from the expected buffering effect of Fe(II)/Fe(III) on the oxidation state of uranium. In the first direct measurement of Pu oxidation state in a nuclear test melt glass, we obtain a result consistent with existing literature that proposes Pu is primarily present as Pu(IV) in post-detonation material. In addition, our measurements imply that highly mobile U(VI) may be produced in significant quantities when melt glass is quenched rapidly following a nuclear detonation, though these products may remain immobile in the vitrified matrices. The observed differences in chemical state among the three samples show that redox conditions can vary dramatically across different nuclear test conditions. The local soil composition, associated device materials, and the rate of quenching are all likely to affect the final redox state of the glass. Lastly, the resulting variations in glass chemistry are significant for understanding and interpreting debris chemistry and the later environmental mobility of dispersed material.« less

  12. Microsoft Word - Template_SLAC Proprietary Use Agreement_PU 11_14_13

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

    PU 11/14/2013 1 The Department of Energy has opted to utilize the following agreement for Designated Proprietary User Facilities transactions. Because these transactions are widespread across Departmental facilities, uniformity in agreement terms is desirable. Except for the *** provisions, minor modifications to the terms of this agreement may be made by CONTRACTOR, but any changes to the *** provisions or substantive changes to the non *** provisons will require approval by the DOE Contracting

  13. Separate effects identification via casting process modeling for experimental measurement of UPuZr alloys

    SciTech Connect (OSTI)

    J. Crapps; D. S. DeCroix; J. D. Galloway; D. A. Korzekwa; R. Aikin; R. Fielding; R. Kennedy; C. Unal

    2013-11-01

    Computational simulations of gravity casting processes for metallic UPuZr nuclear fuel rods have been performed using a design-of-experiments technique to determine the fluid flow, liquid heat transfer, and solid heat transfer parameters which most strongly influence the process solidification speed and fuel rod porosity. The results are used to make recommendations for the best investment of experimental time and effort to measure process parameters.

  14. Ceramicrete stabilization of U-and Pu-bearing materials

    DOE Patents [OSTI]

    Wagh, Arun S.; Maloney, M. David; Thompson, Gary H.

    2007-11-13

    A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated by adjusting the pH of the nuclear material to not less than about 5 and adding sufficient MgO to convert fluorides present to MgF.sub.2; alumina is added in an amount sufficient to absorb substantially all hydrocarbon liquid present, after which a binder including MgO and KH.sub.2PO.sub.4 is added to the treated nuclear material to form a slurry. Additional MgO may be added. A crystalline radioactive material is also disclosed having a binder of the reaction product of calcined MgO and KH.sub.2PO.sub.4 and a radioactive material of the oxides and/or halides of actinides and/or transuranics (TRUs). Acids contaminated with actinides and/or TRUs, and/or actinides and/or TRUs with or without oils and/or greases may be encapsulated and stabilized by the binder.

  15. First-principles study of the Kondo physics of a single Pu impurity in a Th host

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

    Zhu, Jian -Xin; Albers, R. C.; Haule, K.; Wills, J. M.

    2015-04-23

    Based on its condensed-matter properties, crystal structure, and metallurgy, which includes a phase diagram with six allotropic phases, plutonium is one of the most complicated pure elements in its solid state. Its anomalous properties, which are indicative of a very strongly correlated state, are related to its special position in the periodic table, which is at the boundary between the light actinides that have itinerant 5f electrons and the heavy actinides that have localized 5f electrons. As a foundational study to probe the role of local electronic correlations in Pu, we use the local-density approximation together with a continuous-time quantummore » Monte Carlo simulation to investigate the electronic structure of a single Pu atom that is either substitutionally embedded in the bulk and or adsorbed on the surface of a Th host. This is a simpler case than the solid phases of Pu metal. With the Pu impurity atom we have found a Kondo resonance peak, which is an important signature of electronic correlations, in the local density of states around the Fermi energy. We show that the peak width of this resonance is narrower for Pu atoms at the surface of Th than for those in the bulk due to a weakened Pu - 5f hybridization with the ligands at the surface.« less

  16. Validation of MCNP6.1 for Criticality Safety of Pu-Metal, -Solution, and -Oxide Systems

    SciTech Connect (OSTI)

    Kiedrowski, Brian C.; Conlin, Jeremy Lloyd; Favorite, Jeffrey A.; Kahler, III, Albert C.; Kersting, Alyssa R.; Parsons, Donald K.; Walker, Jessie L.

    2014-05-13

    Guidance is offered to the Los Alamos National Laboratory Nuclear Criticality Safety division towards developing an Upper Subcritical Limit (USL) for MCNP6.1 calculations with ENDF/B-VII.1 nuclear data for three classes of problems: Pu-metal, -solution, and -oxide systems. A benchmark suite containing 1,086 benchmarks is prepared, and a sensitivity/uncertainty (S/U) method with a generalized linear least squares (GLLS) data adjustment is used to reject outliers, bringing the total to 959 usable benchmarks. For each class of problem, S/U methods are used to select relevant experimental benchmarks, and the calculational margin is computed using extreme value theory. A portion of the margin of sub criticality is defined considering both a detection limit for errors in codes and data and uncertainty/variability in the nuclear data library. The latter employs S/U methods with a GLLS data adjustment to find representative nuclear data covariances constrained by integral experiments, which are then used to compute uncertainties in keff from nuclear data. The USLs for the classes of problems are as follows: Pu metal, 0.980; Pu solutions, 0.973; dry Pu oxides, 0.978; dilute Pu oxide-water mixes, 0.970; and intermediate-spectrum Pu oxide-water mixes, 0.953.

  17. First-principles study of the Kondo physics of a single Pu impurity in a Th host

    SciTech Connect (OSTI)

    Zhu, Jian -Xin; Albers, R. C.; Haule, K.; Wills, J. M.

    2015-04-23

    Based on its condensed-matter properties, crystal structure, and metallurgy, which includes a phase diagram with six allotropic phases, plutonium is one of the most complicated pure elements in its solid state. Its anomalous properties, which are indicative of a very strongly correlated state, are related to its special position in the periodic table, which is at the boundary between the light actinides that have itinerant 5f electrons and the heavy actinides that have localized 5f electrons. As a foundational study to probe the role of local electronic correlations in Pu, we use the local-density approximation together with a continuous-time quantum Monte Carlo simulation to investigate the electronic structure of a single Pu atom that is either substitutionally embedded in the bulk and or adsorbed on the surface of a Th host. This is a simpler case than the solid phases of Pu metal. With the Pu impurity atom we have found a Kondo resonance peak, which is an important signature of electronic correlations, in the local density of states around the Fermi energy. We show that the peak width of this resonance is narrower for Pu atoms at the surface of Th than for those in the bulk due to a weakened Pu - 5f hybridization with the ligands at the surface.

  18. /sup 235/U(n,f), /sup 238/U(n,gamma), /sup 238/U(n,f) and /sup 239/Pu(n,f) reaction rate measurement calibrations at ZPPR

    SciTech Connect (OSTI)

    Poenitz, W.P.; Maddison, D.W.; Gasidlo, J.M.; Carpenter, S.G.; Armani, R.J.

    1987-01-01

    New reference deposits for /sup 235/U, /sup 239/Pu and /sup 238/U have been established with mass uncertainties of <0.2%. These new deposits replace the older reference deposits which were used during the last 17 years and improve the uncertainty of reaction rate measurements due to reference mass uncertainties by about a factor of 6. Measurements of the fission fragment absorption in 2..pi.. and low-geometry count rates. Two measurements of the /sup 238/U capture rate in depleted uranium samples based upon the thermal cross sections of /sup 238/U(n,..gamma..), /sup 235/U(n,f) and /sup 239/Pu(n,f) and based upon the /sup 243/Am calibration technique confirm the ZPPR measurement technique within the quoted uncertainty of +-0.5%.

  19. Improved laboratory assays of Pu and U for SRP purification and finishing processes

    SciTech Connect (OSTI)

    Holland, M K; Dorsett, R S

    1986-01-01

    Significant improvements have been made in routine assay techniques for uranium and plutonium as part of an effort to improve accountability at the Savannah River Plant (SRP). Emphasis was placed on input/output accountability points and key physical inventory tanks associated with purification and finishing processes. Improvements were made in existing assay methods; new methods were implemented; and the application of these methods was greatly expanded. Prior to assays, samples were validated via density measurements. Digital density meters precise to four, five, and six decimal places were used to meet specific requirements. Improved plutonium assay techniques are now in routine use: controlled-potential coulometry, ion-exchange coulometry, and Pu(III) diode-array spectrophotometry. A new state-of-the-art coulometer was fabricated and used to ensure maximum accuracy in verifying standards and in measuring plutonium in product streams. The diode-array spectrophotometer for Pu(III) measurements was modified with fiber optics to facilitate remote measurements; rapid, precise measurements made the technique ideally suited for high-throughput assays. For uranium assays, the isotope-dilution mass spectrometric (IDMS) method was converted to a gravimetric basis. The IDMS method and the existing Davies-Gray titration (gravimetric basis) have met accountability requirements for uranium. More recently, a Pu(VI) diode-array spectrophotometric method was used on a test basis to measure plutonium in shielded-cell input accountability samples. In addition, tests to measure uranium via diode-array spectrophotometry were initiated. This rapid, precise method will replace IDMS for certain key sample points.

  20. PLUTONIUM LOADING CAPACITY OF REILLEX HPQ ANION EXCHANGE COLUMN - AFS-2 PLUTONIUM FLOWSHEET FOR MOX

    SciTech Connect (OSTI)

    Kyser, E.; King, W.; O'Rourke, P.

    2012-07-26

    Radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the dependence of column loading performance on the feed composition in the H-Canyon dissolution process for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). These loading experiments show that a representative feed solution containing {approx}5 g Pu/L can be loaded onto Reillex{trademark} HPQ resin from solutions containing 8 M total nitrate and 0.1 M KF provided that the F is complexed with Al to an [Al]/[F] molar ratio range of 1.5-2.0. Lower concentrations of total nitrate and [Al]/[F] molar ratios may still have acceptable performance but were not tested in this study. Loading and washing Pu losses should be relatively low (<1%) for resin loading of up to 60 g Pu/L. Loading above 60 g Pu/L resin is possible, but Pu wash losses will increase such that 10-20% of the additional Pu fed may not be retained by the resin as the resin loading approaches 80 g Pu/L resin.

  1. Attempt to produce element 120 in the 244Pu + 58Fe reaction

    SciTech Connect (OSTI)

    Oganessian, Y T; Utyonkov, V K; Lobanov, Y V; Abdullin, F S; Polyakov, A N; Sagaidak, R N; Shorokovsky, I V; Tsyganov, Y S; Voinov, A A; Mezentsev, A N; Subbotin, V G; Sukhov, A M; Subotic, K; Zagrebaev, V I; Dmitriev, S N; Henderson, R A; Moody, K J; Kenneally, J M; Landrum, J H; Shaughnessy, D A; Stoyer, M A; Stoyer, N J; Wilk, P A

    2008-10-24

    An experiment aimed at the synthesis of isotopes of element 120 has been performed using the {sup 244}Pu({sup 58}Fe,xn){sup 302-x} 120 reaction. No decay chains consistent with fusion-evaporation reaction products were observed during an irradiation with a beam dose of 7.1 x 10{sup 18} 330-MeV {sup 58}Fe projectiles. The sensitivity of the experiment corresponds to a cross section of 0.4 pb for the detection of one decay.

  2. Modeling of constituent redistribution in U-Pu-Zr metallic fuel.

    SciTech Connect (OSTI)

    Kim, Y. S.; Hofman, G. L.; Hayes, S. L.; Yacout, A. M.; Nuclear Engineering Division; INL

    2006-12-01

    A computer model was developed to analyze constituent redistribution in U-Pu-Zr metallic nuclear fuels. Diffusion and thermochemical properties were parametrically determined to fit the postirradiation data from a fuel test performed in the Experimental Breeder Reactor II (EBR-II). The computer model was used to estimate redistribution profiles of fuels proposed for the conceptual designs of small modular fast reactors. The model results showed that the level of redistribution of the fuel constituents of the designs was similar to the measured data from EBR-II.

  3. RAPID SEPARATION METHOD FOR 237NP AND PU ISOTOPES IN LARGE SOIL SAMPLES

    SciTech Connect (OSTI)

    Maxwell, S.; Culligan, B.; Noyes, G.

    2010-07-26

    A new rapid method for the determination of {sup 237}Np and Pu isotopes in soil and sediment samples has been developed at the Savannah River Site Environmental Lab (Aiken, SC, USA) that can be used for large soil samples. The new soil method utilizes an acid leaching method, iron/titanium hydroxide precipitation, a lanthanum fluoride soil matrix removal step, and a rapid column separation process with TEVA Resin. The large soil matrix is removed easily and rapidly using this two simple precipitations with high chemical recoveries and effective removal of interferences. Vacuum box technology and rapid flow rates are used to reduce analytical time.

  4. Study on reduction and back extraction of Pu(IV) by urea derivatives in nitric acid conditions

    SciTech Connect (OSTI)

    Ye, G.A.; Xiao, S.T.; Yan, T.H.; Lin, R.S.; Zhu, Z.W.

    2013-07-01

    The reduction kinetics of Pu(IV) by hydroxyl-semicarbazide (HSC), hydroxyurea (HU) and di-hydroxyurea (DHU) in nitric acid solutions were investigated separately with adequate kinetic equations. In addition, counter-current cascade experiments were conducted for Pu split from U in nitric acid media using three kinds of reductant, respectively. The results show that urea derivatives as a kind of novel salt-free reductant can reduce Pu(IV) to Pu(III) rapidly in the nitric acid solutions. The stripping experimental results showed that Pu(IV) in the organic phase can be stripped rapidly to the aqueous phase by the urea derivatives, and the separation factors of plutonium /uranium can reach more than 10{sup 4}. This indicates that urea derivatives is a kind of promising salt-free agent for uranium/plutonium separation. In addition, the complexing effect of HSC with Np(IV) was revealed, and Np(IV) can be back-extracted by HSC with a separation factor of about 20.

  5. LITERATURE REVIEW OF PUO2 CALCINATION TIME AND TEMPERATURE DATA FOR SPECIFIC SURFACE AREA

    SciTech Connect (OSTI)

    Daniel, G.

    2012-03-06

    The literature has been reviewed in December 2011 for calcination data of plutonium oxide (PuO{sub 2}) from plutonium oxalate Pu(C{sub 2}O{sub 4}){sub 2} precipitation with respect to the PuO{sub 2} specific surface area (SSA). A summary of the literature is presented for what are believed to be the dominant factors influencing SSA, the calcination temperature and time. The PuO{sub 2} from Pu(C{sub 2}O{sub 4}){sub 2} calcination data from this review has been regressed to better understand the influence of calcination temperature and time on SSA. Based on this literature review data set, calcination temperature has a bigger impact on SSA versus time. However, there is still some variance in this data set that may be reflecting differences in the plutonium oxalate preparation or different calcination techniques. It is evident from this review that additional calcination temperature and time data for PuO{sub 2} from Pu(C{sub 2}O{sub 4}){sub 2} needs to be collected and evaluated to better define the relationship. The existing data set has a lot of calcination times that are about 2 hours and therefore may be underestimating the impact of heating time on SSA. SRNL recommends that more calcination temperature and time data for PuO{sub 2} from Pu(C{sub 2}O{sub 4}){sub 2} be collected and this literature review data set be augmented to better refine the relationship between PuO{sub 2} SSA and its calcination parameters.

  6. Irradiation performance of U-Pu-Zr metal fuels for liquid-metal-cooled reactors

    SciTech Connect (OSTI)

    Tsai, H.; Cohen, A.B.; Billone, M.C.; Neimark, L.A.

    1994-10-01

    This report discusses a fuel system utilizing metallic U-Pu-Zr alloys which has been developed for advanced liquid metal-cooled reactors (LMRs). Result`s from extensive irradiation testing conducted in EBR-II show a design having the following key features can achieve both high reliability and high burnup capability: a cast nominally U-20wt %Pu-10wt %Zr slug with the diameter sized to yield a fuel smear density of {approx}75% theoretical density, low-swelling tempered martensitic stainless steel cladding, sodium bond filling the initial fuel/cladding gap, and an as-built plenum/fuel volume ratio of {approx}1.5. The robust performance capability of this design stems primarily from the negligible loading on the cladding from either fuel/cladding mechanical interaction or fission-gas pressure during the irradiation. The effects of these individual design parameters, e.g., fuel smear density, zirconium content in fuel, plenum volume, and cladding types, on fuel element performance were investigated in a systematic irradiation experiment in EBR-II. The results show that, at the discharge burnup of {approx}11 at. %, variations on zirconium content or plenum volume in the ranges tested have no substantial effects on performance. Fuel smear density, on the other hand, has pronounced but countervailing effects: increased density results in greater cladding strain, but lesser cladding wastage from fuel/cladding chemical interaction.

  7. IMPORTANCE OF FULL COULOMB INTERACTIONS FOR UNDERSTANDING THE ELECTRONIC STRUCTURE OF DELTA-Pu

    SciTech Connect (OSTI)

    Gorelov, E; Kolorenc, J; Wehling, T; Hafermann, H; Lichtenstein, A I; Shick, A B; Rubtsov, A N; Katsnelson, M I; Landa, A; McMahan, A K

    2010-04-01

    The solid-state properties of most elements are now well understood on the basis of quantum physics - with few exceptions, notably the element number 94, plutonium. Plutonium has six crystalline phases at ambient pressure, some of which are separated by unusual phase transitions with large discontinuities in volume, exhibit negative thermal expansion coefficients, or form exotic low-symmetry structures. The main challenge to explain these anomalous properties is that the characteristic ingredient of actinides, the 5f electronic states, are in the cross-over regime between the localized and delocalized (itinerant) behaviour in Pu. The early part of the actinide series with the 5f states being itinerant, i.e. part of the metallic bond, culminates with Pu; starting with Am (Z = 95), the 5f states are localized, nonbonding, and resemble the 4f states in lanthanides. Both itinerant and localized regimes are well covered by existing theories, but they cannot be simply interpolated due to the importance of dynamical electron-electron correlations. Here we present accurate quantum Monte Carlo calculations achieving previously inaccessible resolution. Obtained results demonstrate that interplay of the full Coulomb interaction vertex with spin-orbital coupling is crucial for understanding the experimentally observed spectral properties of plutonium near the Fermi level.

  8. PLANTS AS BIO-MONITORS FOR 137CS, 238PU, 239, 240PU AND 40K AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Caldwell, E.; Duff, M.; Ferguson, C.

    2010-12-16

    The nuclear fuel cycle generates a considerable amount of radioactive waste, which often includes nuclear fission products, such as strontium-90 ({sup 90}Sr) and cesium-137 ({sup 137}Cs), and actinides such as uranium (U) and plutonium (Pu). When released into the environment, large quantities of these radionuclides can present considerable problems to man and biota due to their radioactive nature and, in some cases as with the actinides, their chemical toxicity. Radionuclides are expected to decay at a known rate. Yet, research has shown the rate of elimination from an ecosystem to differ from the decay rate due to physical, chemical and biological processes that remove the contaminant or reduce its biological availability. Knowledge regarding the rate by which a contaminant is eliminated from an ecosystem (ecological half-life) is important for evaluating the duration and potential severity of risk. To better understand a contaminants impact on an environment, consideration should be given to plants. As primary producers, they represent an important mode of contamination transfer from sediments and soils into the food chain. Contaminants that are chemically and/or physically sequestered in a media are less likely to be bio-available to plants and therefore an ecosystem.

  9. LAMMPS | Argonne Leadership Computing Facility

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

    BOE Reserve Class No 2001 reserves 0.1 - 10 MBOE 10.1 - 100 MBOE 100.1 - 1000 MBOE 1000.1 - 10,000 MBOE 10,000.1 - 100,000 MBOE > 100,000 MBOE Appalachian Basin Boundary C a n a d a N Y P A N Y U S A Appalachian Basin, NY Area (Panel 1 of 7) Oil and Gas Fields By 2001 BOE

    81 § ¨ ¦ 81 LAKESHORE AVON BR ANT-EDEN ALD EN-LANC ASTER AU BURN W SH ELDON CALEDONIA HURON C REEK LEIC EST ER COL DEN ASH FORD INDIAN FALLS LAWTONS SAR DINIA RPD-037 -2 GLENWOOD PU LASKI PAVILION CON CORD COL LINS N

  10. 2016 Middle School Science Bowl Participating Teams | The Ames...

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

    Adel-DeSoto-Minburn (Adel) Ames - Team 1 Ames - Team 2 Boone Clarion-Goldfield Eleanor Roosevelt (Dubuque) Glenwood Le Mars Lenox Lynnville-Sully Madrid Melcher-Dallas New ...

  11. Materials Data on Pu2O3 (SG:164) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-02-09

    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

  12. Materials Data on PuIr2 (SG:227) by Materials Project

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

    Kristin Persson

    2015-03-09

    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

  13. Imminent: Irradiation Testing of (Th,Pu)O{sub 2} Fuel - 13560

    SciTech Connect (OSTI)

    Kelly, Julian F.; Franceschini, Fausto

    2013-07-01

    Commercial-prototype thorium-plutonium oxide (Th-MOX) fuel pellets have been loaded into the material test reactor in Halden, Norway. The fuel is being operated at full power - with instrumentation - in simulated LWR / PHWR conditions and its behaviour is measured 'on-line' as it operates to high burn-up. This is a vital test on the commercialization pathway for this robust new thoria-based fuel. The performance data that is collected will support a fuel modeling effort to support its safety qualification. Several different samples of Th-MOX fuel will be tested, thereby collecting information on ceramic behaviours and their microstructure dependency. The fuel-cycle reasoning underpinning the test campaign is that commercial Th- MOX fuels are an achievable intermediate / near-term SNF management strategy that integrates well with a fast reactor future. (authors)

  14. Materials Data on PuGe2 (SG:141) by Materials Project

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

    Kristin Persson

    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

  15. Materials Data on Pu2Co (SG:189) by Materials Project

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

    Kristin Persson

    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

  16. Materials Data on PuNi2 (SG:227) by Materials Project

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

    Kristin Persson

    2015-03-19

    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. Materials Data on PuH8(SO6)2 (SG:62) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-04-24

    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

  18. Materials Data on Pu2Co (SG:189) 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

  19. Materials Data on PuGe2 (SG:141) 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

  20. Materials Data on PuOs2 (SG:227) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-03-19

    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

  1. Materials Data on Pu(SiOs)2 (SG:139) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-02-09

    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

  2. Upper concentration limits for {sup 239}Pu traces in some {open_quotes}KTB{close_quotes}-samples and in one Hawaiian lava

    SciTech Connect (OSTI)

    Barth, H.; Ganz, M.; Brandt, R.

    1994-11-01

    Trace quantities of plutonium are observed in the environment all over the world, and include both man-made {sup 238-242}Pu and natural {sup 239}Pu in uranium ores. Typical concentrations range from 10{sup {minus}14} g Pu/g sample up to 10{sup {minus}12} g Pu/g in pitchblende. We have determined some upper concentration limits for the plutonium in samples from KTB (Kontinentales Tiefbohrprogramm, Germany) which are in the range of 10{sup {minus}15} down to 3{center_dot}10{sup {minus}17} g Pu/g sample. In addition, we have investigated one sample of Hawaiian lava, with a limit of 5{center_dot}10{sup {minus}15}. We could not confirm previous reports on the observation of plutonium in some Pacific Lavas, nor do our results show any evidence for cold fusion neutrons producing plutonium in fluids of great depth in the crust.

  3. Induced fission of Pu240 within a real-time microscopic framework

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

    Bulgac, Aurel; Magierski, Piotr; Roche, Kenneth J.; Stetcu, Ionel

    2016-03-25

    Here, we describe the fissioning dynamics of 240Pu from a configuration in the proximity of the outer fission barrier to full scission and the formation of the fragments within an implementation of density functional theory extended to superfluid systems and real-time dynamics. The fission fragments emerge with properties similar to those determined experimentally, while the fission dynamics appears to be quite complex, with many excited shape and pairing modes. The evolution is found to be much slower than previously expected, and the ultimate role of the collective inertia is found to be negligible in this fully nonadiabatic treatment of nuclearmore » dynamics, where all collective degrees of freedom (CDOF) are included (unlike adiabatic treatments with a small number of CDOF).« less

  4. An evaluation of alternate production methods for Pu-238 general purpose heat source pellets

    SciTech Connect (OSTI)

    Mark Borland; Steve Frank

    2009-06-01

    For the past half century, the National Aeronautics and Space Administration (NASA) has used Radioisotope Thermoelectric Generators (RTG) to power deep space satellites. Fabricating heat sources for RTGs, specifically General Purpose Heat Sources (GPHSs), has remained essentially unchanged since their development in the 1970s. Meanwhile, 30 years of technological advancements have been made in the applicable fields of chemistry, manufacturing and control systems. This paper evaluates alternative processes that could be used to produce Pu 238 fueled heat sources. Specifically, this paper discusses the production of the plutonium-oxide granules, which are the input stream to the ceramic pressing and sintering processes. Alternate chemical processes are compared to current methods to determine if alternative fabrication processes could reduce the hazards, especially the production of respirable fines, while producing an equivalent GPHS product.

  5. Microscopic modeling of mass and charge distributions in the spontaneous fission of 240Pu

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

    Sandhukhan, Jhilam; Nazarewicz, Witold; Schunck, Nicolas

    2016-01-20

    We propose a methodology to calculate microscopically the mass and charge distributions of spontaneous fission yields. We combine the multidimensional minimization of collective action for fission with stochastic Langevin dynamics to track the relevant fission paths from the ground-state configuration up to scission. The nuclear potential energy and collective inertia governing the tunneling motion are obtained with nuclear density functional theory in the collective space of shape deformations and pairing. As a result, we obtain a quantitative agreement with experimental data and find that both the charge and mass distributions in the spontaneous fission of 240Pu are sensitive both tomore » the dissipation in collective motion and to adiabatic fission characteristics.« less

  6. Gamma-ray Output Spectra from 239 Pu Fission

    SciTech Connect (OSTI)

    Ullmann, John

    2015-05-25

    Gamma-ray multiplicities, individual gamma-ray energy spectra, and total gamma energy spectra following neutron-induced fission of 239Pu were measured using the DANCE detector at Los Alamos. Corrections for detector response were made using a forward-modeling technique based on propagating sets of gamma rays generated from a paramaterized model through a GEANT model of the DANCE array and adjusting the parameters for best fit to the measured spectra. The results for the gamma-ray spectrum and multiplicity are in general agreement with previous results, but the measured total gamma-ray energy is about 10% higher. A dependence of the gamma-ray spectrum on the gamma-ray multplicity was also observed. Global model calculations of the multiplicity and gamma energy distributions are in good agreement with the data, but predict a slightly softer total-energy distribution.

  7. Review of Calculations on Point Defect Properties in Delta-Pu

    SciTech Connect (OSTI)

    Allen, P. G.; Wolfer, W. G.

    2015-09-08

    The results of theoretical predictions of properties for vacancies and self-interstitial atoms (SIA) in δ-Pu are presented and reviewed. Three methods have been used for these predictions, namely the modified embedded atom method (MEAM), density functional theory (DFT) with and without spin polarization, and continuum mechanics (CM) models adapted to plutonium. The properties considered are formation and migration energies, and relaxation volumes of vacancies and SIA. Predicted values vary considerably. Nevertheless, all three methods predict that the activation energy for self-diffusion by vacancies is of similar magnitude as the SIA formation energy. Furthermore, the absolute magnitudes of relaxation volumes for vacancies and SIA are also similar, indicating that there exist no large bias for radiation-induced void swelling.

  8. Applications of pulsed neutron powder diffraction to actinide elements. [Pu-Al

    SciTech Connect (OSTI)

    Lawson, A.C.; Richardson, J.W.; Mueller, M.H.; Lander, G.H.; Goldstone, J.A.; Williams, A.; Kwei, G.H.; Von Dreele, R.B.; Faber, J. Jr.; Hitterman, R.L.

    1987-11-01

    We have been using the technique of pulsed neutron powder diffraction to study several problems in the physics and chemistry of the actinide elements. In these elements one often encounters very complex structures resulting from polymorphic transformations presumably induced by the presence of 5f-electrons. For example, at least five distinct structures of plutonium metal are found between room temperature and its melting point of 640/sup 0/C, and two of the structures are monoclinc. The determination of the crystal structure of beta-uranium (tetragonal, 30 atoms per unit cell) which has finnaly been shown to be centrosymmetric, after decades of uncertainty is discussed. Some preliminary results on the structure of alpha-plutonium (which confirm Zachariasen's original determination of the monoclinic structure) are presented. Pu-Al alloys were also studied. 12 refs., 18 figs.

  9. Hidden disorder in the α'→δ transformation of Pu-1.9 at.% Ga

    SciTech Connect (OSTI)

    Jeffries, J. R.; Manley, M. E.; Wall, M. A.; Blobaum, K. J. M.; Schwartz, A. J.

    2012-06-06

    Enthalpy and entropy are thermodynamic quantities critical to determining how and at what temperature a phase transition occurs. At a phase transition, the enthalpy and temperature-weighted entropy differences between two phases are equal (ΔH=TΔS), but there are materials where this balance has not been experimentally or theoretically realized, leading to the idea of hidden order and disorder. In a Pu-1.9 at. % Ga alloy, the δ phase is retained as a metastable state at room temperature, but at low temperatures, the δ phase yields to a mixed-phase microstructure of δ- and α'-Pu. The previously measured sources of entropy associated with the α'→δ transformation fail to sum to the entropy predicted theoretically. We report an experimental measurement of the entropy of the α'→δ transformation that corroborates the theoretical prediction, and implies that only about 65% of the entropy stabilizing the δ phase is accounted for, leaving a missing entropy of about 0.5 kB/atom. Some previously proposed mechanisms for generating entropy are discussed, but none seem capable of providing the necessary disorder to stabilize the δ phase. This hidden disorder represents multiple accessible states per atom within the δ phase of Pu that may not be included in our current understanding of the properties and phase stability of δ-Pu.

  10. MD simulations of phase stability of PuGa alloys: Effects of primary radiation defects and helium bubbles

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

    Dremov, V. V.; Sapozhnikov, F. A.; Ionov, G. V.; Karavaev, A. V.; Vorobyova, M. A.; Chung, B. W.

    2013-05-14

    We present classical molecular dynamics (MD) with Modified Embedded Atom Model (MEAM) simulations to investigate the role of primary radiation defects and radiogenic helium as factors affecting the phase stability of PuGa alloys in cooling–heating cycles at ambient pressure. The models of PuGa alloys equilibrated at ambient conditions were subjected to cooling–heating cycles in which they were initially cooled down to 100 K and then heated up to 500 K at ambient pressure. The rate of temperature change in the cycles was 10 K/ns. The simulations showed that the initial FCC phase of PuGa alloys undergo polymorphous transition in coolingmore » to a lower symmetry α'-phase. All the alloys undergo direct and reverse polymorphous transitions in the cooling–heating cycles. The alloys containing vacancies shift in both transitions to lower temperatures relative to the defect-free alloys. The radiogenic helium has much less effect on the phase stability compared to that of primary radiation defects (in spite of the fact that helium concentration is twice of that for the primary radiation defects). Lastly, this computational result agrees with experimental data on unconventional stabilization mechanism of PuGa alloys.« less

  11. Production of new superheavy Z=108-114 nuclei with {sup 238}U, {sup 244}Pu, and {sup 248,250}Cm targets

    SciTech Connect (OSTI)

    Feng Zhaoqing; Jin Genming; Li Junqing

    2009-11-15

    Within the framework of the dinuclear system (DNS) model, production cross sections of new superheavy nuclei with charged numbers Z=108-114 are analyzed systematically. Possible combinations based on the actinide nuclides {sup 238}U, {sup 244}Pu, and {sup 248,250}Cm with the optimal excitation energies and evaporation channels are pointed out to synthesize new isotopes that lie between the nuclides produced in the cold fusion reactions and the {sup 48}Ca-induced fusion reactions experimentally, which are feasible to be constructed experimentally. It is found that the production cross sections of superheavy nuclei decrease drastically with the charged numbers of compound nuclei. Larger mass asymmetries of the entrance channels enhance the cross sections in 2n-5n channels.

  12. NMIS with Imaging and Gamma Ray Spectrometry for Pu, HEU, HE and Other Materials

    SciTech Connect (OSTI)

    Mihalczo, John T; Mullens, James Allen

    2012-03-01

    The Nuclear Material Identification System (NMIS) has been under development at ORNL and the National Nuclear Security Administration (NNSA) Y-12 National Security Complex since 1984. In the mid-1990s, what is now the US Department of Energy (DOE) Office of Nuclear Verification (ONV) realized that it was a useful technology for future arms control treaty applications and supported further development of the system. In 2004, fast-neutron imaging was incorporated into the system. In 2007, the ONV decided to develop a fieldable version of the system, designated as FNMIS, for potential use in future treaties. The FNMIS is being developed to be compatible with the eventual incorporation of gamma-ray spectrometry and an information barrier. This report addresses how and what attributes could be determined by the FNMIS system with gamma-ray spectrometry. The NMIS is a time-dependent coincidence system that incorporates tomographic imaging (including mapping of the fission sites) and gamma-ray spectrometry. It utilizes a small, lightweight (30 lb), portable deuterium-tritium (DT) neutron (14.1 MeV) generator (4 x 10{sup 7} neutrons/second) for active interrogation and can also perform passive interrogation. A high-purity germanium (HPGe) gamma-ray detector with multichannel analysis can be utilized in conjunction with the source for active interrogation or passively. The system uses proton recoil scintillators: 32 small 2.5 x 2.5 x 10.2-cm-thick plastic scintillators for imaging and at least two 2 x 2 arrays of 27 x 27 x 10-cm-thick plastic scintillators that detect induced fission radiation. The DT generator contains an alpha detector that time and directionally tags a fan beam of some of the neutrons emitted and subdivides it into pixels. A fast (1 GHz) time correlation processor measures the time-dependent coincidence among all detectors in the system. A computer-controlled scanner moves the small detectors and the source appropriately for scanning a target object for

  13. The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor

    SciTech Connect (OSTI)

    Syarifah, Ratna Dewi Suud, Zaki

    2015-09-30

    Design study of small Pressurized Water Reactors (PWRs) core loaded with uranium nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as burnable poison, and Americium has been performed. Pa-231 known as actinide material, have large capture cross section and can be converted into fissile material that can be utilized to reduce excess reactivity. Americium is one of minor actinides with long half life. The objective of adding americium is to decrease nuclear spent fuel in the world. The neutronic analysis results show that mixed nitride fuel have k-inf greater than uranium nitride fuel. It is caused by the addition of Pu-239 in mixed nitride fuel. In fuel fraction analysis, for uranium nitride fuel, the optimum volume fractions are 45% fuel fraction, 10% cladding and 45% moderator. In case of UN-PuN fuel, the optimum volume fractions are 30% fuel fraction, 10% cladding and 60% coolant/ moderator. The addition of Pa-231 as burnable poison for UN fuel, enrichment U-235 5%, with Pa-231 1.6% has k-inf more than one and excess reactivity of 14.45%. And for mixed nitride fuel, the lowest value of reactivity swing is when enrichment (U-235+Pu) 8% with Pa-231 0.4%, the excess reactivity value 13,76%. The fuel pin analyze for the addition of Americium, the excess reactivity value is lower than before, because Americium absorb the neutron. For UN fuel, enrichment U-235 8%, Pa-231 1.6% and Am 0.5%, the excess reactivity is 4.86%. And for mixed nitride fuel, when enrichment (U-235+Pu) 13%, Pa-231 0.4% and Am 0.1%, the excess reactivity is 11.94%. For core configuration, it is better to use heterogeneous than homogeneous core configuration, because the radial power distribution is better.

  14. Delayed Fission Gamma-ray Characteristics of Th-232 U-233 U-235 U-238 and Pu-239

    SciTech Connect (OSTI)

    Lane, Taylor; Parma, Edward J.

    2015-08-01

    Delayed fission gamma-rays play an important role in determining the time dependent ioniz- ing dose for experiments in the central irradiation cavity of the Annular Core Research Reactor (ACRR). Delayed gamma-rays are produced from both fission product decay and from acti- vation of materials in the core, such as cladding and support structures. Knowing both the delayed gamma-ray emission rate and the time-dependent gamma-ray energy spectrum is nec- essary in order to properly determine the dose contributions from delayed fission gamma-rays. This information is especially important when attempting to deconvolute the time-dependent neutron, prompt gamma-ray, and delayed gamma-ray contribution to the response of a diamond photo-conducting diode (PCD) or fission chamber in time frames of milliseconds to seconds following a reactor pulse. This work focused on investigating delayed gamma-ray character- istics produced from fission products from thermal, fast, and high energy fission of Th-232, U-233, U-235, U-238, and Pu-239. This work uses a modified version of CINDER2008, a transmutation code developed at Los Alamos National Laboratory, to model time and energy dependent photon characteristics due to fission. This modified code adds the capability to track photon-induced transmutations, photo-fission, and the subsequent radiation caused by fission products due to photo-fission. The data is compared against previous work done with SNL- modified CINDER2008 [ 1 ] and experimental data [ 2 , 3 ] and other published literature, includ- ing ENDF/B-VII.1 [ 4 ]. The ability to produce a high-fidelity (7,428 group) energy-dependent photon fluence at various times post-fission can improve the delayed photon characterization for radiation effects tests at research reactors, as well as other applications.

  15. Burnup estimation of fuel sourcing radioactive material based on monitored Cs and Pu isotopic activity ratios in Fukushima N. P. S. accident

    SciTech Connect (OSTI)

    Yamamoto, T.; Suzuki, M.; Ando, Y.

    2012-07-01

    After the severe core damage of Fukushima Dai-Ichi Nuclear Power Station, radioactive material leaked from the reactor buildings. As part of monitoring of radioactivity in the site, measurements of radioactivity in soils at three fixed points have been performed for {sup 134}Cs and {sup 137}Cs with gamma-ray spectrometry and for Pu, Pu, and {sup 240}Pu with {alpha}-ray spectrometry. Correlations of radioactivity ratios of {sup 134}Cs to {sup 137}Cs, and {sup 238}Pu to the sum of {sup 239}Pu and {sup 240}Pu with fuel burnup were studied by using theoretical burnup calculations and measurements on isotopic inventories, and compared with the Cs and Pu radioactivity rations in the soils. The comparison indicated that the burnup of the fuel sourcing the radioactivity was from 18 to 38 GWd/t, which corresponded to that of the fuel in the highest power and, therefore, the highest decay heat in operating high-burnup fueled BWR cores. (authors)

  16. Estimation of 240Pu Mass in a Waste Tank Using Ultra-Sensitive Detection of Radioactive Xenon Isotopes from Spontaneous Fission

    SciTech Connect (OSTI)

    Bowyer, Ted W.; Gesh, Christopher J.; Haas, Derek A.; Hayes, James C.; Mahoney, Lenna A.; Meacham, Joseph E.; Mendoza, Donaldo P.; Olsen, Khris B.; Prinke, Amanda M.; Reid, Bruce D.; Woods, Vincent T.

    2014-12-01

    We report on a technique to detect and quantify the amount of 240Pu in a large tank used to store nuclear waste from plutonium production at the Hanford nuclear site. While the contents of this waste tank are known from previous grab sample measurements, our technique could allow for determination of the amount of 240Pu in the tank without costly sample retrieval and analysis of this highly radioactive material. This technique makes an assumption, which was confirmed, that 240Pu dominates the spontaneous fissions occurring in the tank.

  17. Evaluation of Aqueous and Powder Processing Techniques for Production of Pu-238-Fueled General Purpose Heat Sources

    SciTech Connect (OSTI)

    Not Available

    2008-06-01

    This report evaluates alternative processes that could be used to produce Pu-238 fueled General Purpose Heat Sources (GPHS) for radioisotope thermoelectric generators (RTG). Fabricating GPHSs with the current process has remained essentially unchanged since its development in the 1970s. Meanwhile, 30 years of technological advancements have been made in the fields of chemistry, manufacturing, ceramics, and control systems. At the Department of Energy’s request, alternate manufacturing methods were compared to current methods to determine if alternative fabrication processes could reduce the hazards, especially the production of respirable fines, while producing an equivalent GPHS product. An expert committee performed the evaluation with input from four national laboratories experienced in Pu-238 handling.

  18. Code System to Determine Pu Isotope Abundances from Multichannel Analyzer Gamma Spectra.

    Energy Science and Technology Software Center (OSTI)

    2008-09-26

    Version 00 The MGA (Multiple Group Analysis) program determines the relative abundances of plutonium and other actinide isotopes in different materials. The program analyzes spectra taken of such samples using a 4096-channel germanium (Ge) gamma-ray spectrometer. The code can be run in a one or two detector mode. The first spectrum, which is required and must be taken at a gain of 0.075 Kev/channel with a high resolution planar detector, contains the 0-300Kev energy region.more » The second spectrum, which is optional, must be taken at a gain of 0.25 Kev/channel; it becomes important when analyzing high burnup samples (concentration of Pu241 greater than one percent). Isotopic analysis precisions of one percent or better can be obtained, and no calibrations are required. The system also measures the abundances of U235, U238, Np237, and Am241. A special calibration option is available to perform a one-time peak-shape characterization when first using a new detector system.« less

  19. Assessment of a mechanistic model in U-Pu-Zr metallic alloy fuel fission-gas behavior simulations

    SciTech Connect (OSTI)

    Yun, D.; Rest, J.; Yacout, A. M.

    2012-07-01

    A mechanistic kinetic rate theory model originally developed for the prediction of fission gas behavior in oxide nuclear fuels under steady-state and transient conditions has been assessed to look at its applicability to model fission gas behavior in U-Pu-Zr metallic alloy fuel. In order to capture and validate the underlying physics for irradiated U-Pu-Zr fuels, the mechanistic model was applied to the simulation of fission gas release, fission gas and fission product induced swelling, and the evolution of the gas bubble size distribution in three different fuel zones: the outer {alpha}-U, the intermediate, and the inner {gamma}-U zones. Due to its special microstructural features, the {alpha}-U zone in U-Pu-Zr fuels is believed to contribute the largest fraction of fission gas release among the different fuel zones. It is shown that with the use of small effective grain sizes, the mechanistic model can predict fission gas release that is consistent with (though slightly lower than) experimentally measured data. These simulation results are comparable to the experimentally measured fission gas release since the mechanism of fission gas transport through the densely distributed laminar porosity in the {alpha}-U zone is analogous to the mechanism of fission gas transport through the interconnected gas bubble porosity utilized in the mechanistic model. Detailed gas bubble size distributions predicted with the mechanistic model in both the intermediate zone and the high temperature {gamma}-U zone of U-Pu-Zr fuel are also compared to experimental measurements from available SEM micrographs. These comparisons show good agreements between the simulation results and experimental measurements, and therefore provide crucial guidelines for the selection of key physical parameters required for modeling these two zones. In addition, the results of parametric studies for several key parameters are presented for both the intermediate zone and the {gamma}-U zone simulations

  20. Data Testing Revised 235U, 239Pu and 63,65Cu Files with ICSBEP Benchmarks

    SciTech Connect (OSTI)

    Kahler, III, Albert C.; Leal, Luiz C.

    2014-03-13

    We review recent critical benchmark calculations with revised 235U, 239Pu and 63,65Cu evaluated data files.

  1. Quantifying the importance of orbital over spin correlations in delta-Pu within density-functional theory

    SciTech Connect (OSTI)

    Soderlind, P; Wolfer, W

    2007-07-27

    Spin and orbital and electron correlations are known to be important when treating the high-temperature {delta} phase of plutonium within the framework of density-functional theory (DFT). One of the more successful attempts to model {delta}-Pu within this approach has included condensed-matter generalizations of Hund's three rules for atoms, i.e., spin polarization, orbital polarization, and spin-orbit coupling. Here they perform a quantitative analysis of these interactions relative rank for the bonding and electronic structure in {delta}-Pu within the DFT model. The result is somewhat surprising in that spin-orbit coupling and orbital polarization are far more important than spin polarization for a realistic description of {delta}-Pu. They show that these orbital correlations on their own, without any formation of magnetic spin moments, can account for the low atomic density of the {delta} phase with a reasonable equation-of-state. In addition, this unambiguously non-magnetic (NM) treatment produces a one-electron spectra with resonances close to the Fermi level consistent with experimental valence band photoemission spectra.

  2. Effect of 1-hydroxyethane-1,1-diphosphonic acid (HEDPA) on Partitioning of Np and Pu to Synthetic Boehmite

    SciTech Connect (OSTI)

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

    2009-05-01

    The effect of 1-hydroxyethane-1,1-diphosphonic acid (HEDPA) on sorption of Np(V) and Pu(V) to synthetic boehmite ({gamma}-AlOOH) was examined a function of time and pH (between 4 to 11). Sorption of both elements in boehmite suspensions (1 M NaCl, 600 mg L{sup -1} boehmite) increased with increasing pH. Sorption edges for neptunium and plutonium occurred at approximately pH 8.0 and 6.6, respectively. After steady state partitioning was reached, HEDPA was added to the neptunium-boehmite and plutonium-boehmite suspensions. Neptunium and plutonium partitioning appears to be primarily affected by the formation of soluble Np:HEDPA and Pu:HEDPA complexes, the dissolution of boehmite promoted by HEDPA, and the precipitation of Np:HEDPA and Pu:HEDPA colloids. The results are discussed in terms of applicability of HEDPA-promoted dissolution as a waste reduction method in the treatment of sludge phases contained within high-level nuclear waste storage tanks.

  3. Is Tritium Over-regulated, Part 2: Should the TFG Support Higher...

    Office of Environmental Management (EM)

    ... a lower release fraction * Gaseous oxide (steam) release would have thermal buoyancy * ... Rem 0.2 Rem* 12000 particle * Pu-239 Injection dose conversion factor 2.5 E9 CEDECi ...

  4. Comparison of {sup 241}Am, {sup 239,240}Pu, and {sup 137}Cs concentrations in soil around Rocky Flats

    SciTech Connect (OSTI)

    Hulse, S.E.; Ibrahim, S.A.; Whicker, F.W.; Chapman, P.L.

    1999-03-01

    Gamma spectroscopy measurements were used to estimate concentrations of {sup 241}Am and {sup 137}Cs in soil profiles to depths of 21 cm at on-site and off-site locations around the Rocky Flats Environmental Technology Site and at regional background locations east of the Front Range between Colorado`s borders with New Mexico and Wyoming. Concentrations of these radionuclides were compared with concentrations of {sup 239,240}Pu in the same samples. Concentrations of {sup 241}Am in soil from depths of 0 to 3 cm decreased in an easterly direction from more than 5.3 kBq kg{sup {minus}1} 5 to 7 km away at a rate that was nearly proportional to the inverse square of distance. Deposits of {sup 137}Cs were ubiquitous, averaging 0.12 kBq kg{sup {minus}1} in soil from depths of 0 to 3 cm, but were unevenly distributed around Rocky Flats and the regional background locations. Deviations from the uniform exponential rate at which soil concentrations of {sup 137}Cs typically decreased with depth, {minus}0.25 cm{sup {minus}1} at undisturbed sites, enabled the authors to determine that about 10% of their sampling sites had been disturbed by erosion, tillage, or other factors. The mean rate at which {sup 239,240}Pu decreased with depth was about the same, {minus}0.23 cm{sup {minus}1}, throughout the study area. Soil concentrations of {sup 241}Am decreased with depth at a similar mean rate of {minus}0.22 cm{sup {minus}1} at locations close to the 903 pad where measurements were robust. Ratios between {sup 241}Am or {sup 239,240}Pu and {sup 137}Cs proved more useful for delineating the extent and pattern of contamination from Rocky Flats than did activity concentrations in soil.

  5. Full-length U-xPu-10Zr (x=0, 8, 19 wt%) Fast Reactor Fuel Test in FFTF

    SciTech Connect (OSTI)

    D. L. Porter; H.C. Tsai

    2012-08-01

    The Integral Fast Reactor-1 (IFR-1) experiment performed in the Fast Flux Test Facility (FFTF) was the only U-Pu-10Zr (Pu-0, 8 and 19 wt%) metallic fast reactor test with commercial-length (91.4 cm active fuel column length) conducted to date. With few remaining test reactors there is little opportunity for performing another test with a long active fuel column. The assembly was irradiated to the goal burnup of 10 at.%. The beginning of life (BOL) peak cladding temperature of the hottest pin was 608?C, cooling to 522?C at end of life (EOL). Selected fuel pins were examined non destructively using neutron radiography, precision axial gamma scanning, and both laser and spiral contact cladding profilometry. Destructive exams included plenum gas pressure, volume, and gas composition determinations on a number of pins followed by optical metallography, electron probe microanalysis (EPMA), and alpha and beta gamma autoradiography on a single U-19Pu-10Zr pin. The post-irradiation examinations (PIEs) showed very few differences compared to the short-pin (34.3 cm fuel column) testing performed on fuels of similar composition in Experimental Breeder Reactor-II (EBR-II). The fuel column grew axially slightly less than observed in the short pins, but with the same pattern of decreasing growth with increasing Pu content. There was a difference in the fuel-cladding chemical interaction (FCCI) in that the maximum cladding penetration by interdiffusion with fuel/fission products did not occur at the top of the fuel column where the cladding temperature is highest, as observed in EBR-II tests. Instead, the more exaggerated fission-rate profile of the FFTF pins resulted in a peak FCCI at ~0.7 X/L axial location along the fuel column. This resulted from a lower production of rare earth fission products higher in the fuel column as well as a much smaller delta-T between fuel center and cladding, and therefore less FCCI, despite the higher cladding temperature. This behavior could

  6. Plutonium in human urine: Normal levels in the US public. 1991 Annual report, Volume 2

    SciTech Connect (OSTI)

    Wrenn, M.E.; Singh, N.P.; Xue, Ying-Hua

    1997-03-01

    A neutron induced fission track method was successfully developed for assaying {sup 239}Pu in human urine with a detection limit below 20 aCi/sample. The technique involves the co-precipitation of {sup 239}Pu with rhodizonic acid, separation of {sup 239}Pu from potentially interfering natural uranium and other inorganic materials by ion-exchange techniques, collection of the sample onto lexan detectors, irradiation of sample in MIT reactor at a fluence of 1.1 x 10{sup 17} n/cm{sup 2}, etching of the lexan slide and counting the track either manually or by some automated counting system.

  7. Theory of the compactness of the hot fusion reaction {sup 48}Ca+{sup 244}Pu{yields}{sup 292}114*

    SciTech Connect (OSTI)

    Gupta, Raj K.; Manhas, Monika; Muenzenberg, G.; Greiner, Walter

    2005-07-01

    Within the fragmentation theory, extended to include the orientations degrees of freedom and hexadecupole deformations, for optimized orientations, the {sup 48}Ca+{sup 244}Pu{yields}{sup 292}114* reaction is shown to be a 'compact' hot fusion reaction. The barrier is highest (hot fusion) and interaction radius smallest (compact), which occur for the collisions in the direction of the minor axis of the deformed reaction partner (i.e. for 90 deg. orientation of {sup 244}Pu). In addition to the {sup 48}Ca+{sup 244}Pu reaction valley, a number of other new reaction valleys (target-projectile combinations) are shown to arise for the 'optimally oriented hot' fusion process, the {sup 48}Ca+{sup 244}Pu being the best (lowest barrier) and {sup 54}Ti+{sup 238}U as the next possible best reaction for forming the cold compound nucleus {sup 292}114*. A similar reaction valley for {sup 48}Ca+{sup 244}Pu is found absent in the 'optimally oriented cold' fusion process.

  8. Measurement/Evaluation Techniques and Nuclear Data Associated with Fission of 239Pu by Fission Spectrum Neutrons

    SciTech Connect (OSTI)

    Baisden, P; Bauge, E; Ferguson, J; Gilliam, D; Granier, T; Jeanloz, R; McMillan, C; Robertson, D; Thompson, P; Verdon, C; Wilkerson, C; Young, P

    2010-03-16

    This Panel was chartered to review and assess new evaluations of work on fission product data, as well as the evaluation process used by the two U.S. nuclear weapons physics laboratories. The work focuses on fission product yields resulting from fission spectrum neutrons incident on plutonium, and includes data from measurements that had not been previously published as well as new or revised fission product cumulative yield data, and related quantities such as Q values and R values. This report documents the Panel's assessment of the work presented by Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). Based on the work presented we have seven key observations: (1) Experiments conducted in the 1970s at LANL, some of which were performed in association with a larger, NIST-led, program, have recently been documented. A preliminary assessment of this work, which will be referred to in this document as ILRR-LANL, shows it to be technically sound. (2) LLNL has done a thorough, unbiased review and evaluation of the available literature and is in the process of incorporating the previously unavailable LANL data into its evaluation of key fission product yields. The results of the LLNL effort, which includes a preliminary evaluation of the ILRR-LANL data, have been documented. (3) LANL has also conducted an evaluation of fission product yields for fission spectrum neutrons on plutonium including a meta-analysis of benchmark data as part of a planned upgrade to the ENDF/B compilation. We found that the approach of using meta-analysis provides valuable additional insight for evaluating the sparse data sets involved in this assessment. (4) Both laboratories have provided convincing evidence for energy dependence in the fission product yield of {sup 147}Nd produced from the bombardment of {sup 239}Pu with fission spectrum neutrons over an incident neutron energy range of 0.2 to 1.9 MeV. (5) Consistent, complete, and explicit treatment of

  9. U and Pu Gamma-Ray Measurements of Spent Fuel Using a Gamma-Ray Mirror Band-Pass Filter

    SciTech Connect (OSTI)

    Ziock, Klaus-Peter; Alameda, J.B.; Brejnholt, N.F.; Decker, T.A.; Descalle, M.A.; Fernandez-Perea, M.; Hill, R.M.; Kisner, R.A.; Melin, A.M.; Patton, B.W.; Ruz, J.; Soufli, R.; Pivovaroff, M.J.

    2014-01-01

    Abstract. We report on the use of grazing incidence gamma-ray mirrors to serve as a narrow band-pass filter for advanced non-destructive analysis (NDA) of spent nuclear fuel. The purpose of the mirrors is to limit the radiation reaching a HPGe detector to narrow spectral bands around characteristic emission lines from fissile isotopes in the fuel. This overcomes the normal rate issues when performing gamma-ray NDA measurements. In a proof-of-concept experiment, a set of simple flat gamma-ray mirrors were used to directly observe the atomic florescence lines from U and Pu from spent fuel pins with the detector located in a shirt-sleeve environment. The mirrors, consisting of highly polished silicon substrates deposited with WC/SiC multilayer coatings, successfully deflected the lines of interest while the intense primary radiation beam from the fuel was blocked by a lead beam stop. The gamma-ray multilayer coatings that make the mirrors work at the gamma-ray energies used here (~ 100 keV) have been experimentally tested at energies as high as 645 keV, indicating that direct observation of nuclear emission lines from 239Pu should be possible with an appropriately designed optic and shielding configuration.

  10. A generalized method for characterization of 235U and 239Pu content using short-lived fission product gamma spectroscopy

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

    Knowles, Justin R.; Skutnik, Steven E.; Glasgow, David C.; Kapsimalis, Roger J.

    2016-06-23

    Rapid non-destructive assay methods for trace fissile material analysis are needed in both nuclear forensics and safeguards communities. To address these needs, research at the High Flux Isotope Reactor Neutron Activation Analysis laboratory has developed a generalized non-destructive assay method to characterize materials containing fissile isotopes. This method relies on gamma-ray emissions from short-lived fission products and capitalizes off of differences in fission product yields to identify fissile compositions of trace material samples. Although prior work has explored the use of short-lived fission product gamma-ray measurements, the proposed method is the first to provide a holistic characterization of isotopic identification,more » mass ratios, and absolute mass determination. Successful single fissile isotope mass recoveries of less than 6% error have been conducted on standards of 235U and 239Pu as low as 12 nanograms in less than 10 minutes. Additionally, mixtures of fissile isotope standards containing 235U and 239Pu have been characterized as low as 229 nanograms of fissile mass with less than 12% error. The generalizability of this method is illustrated by evaluating different fissile isotopes, mixtures of fissile isotopes, and two different irradiation positions in the reactor. Furthermore, it is anticipated that this method will be expanded to characterize additional fissile nuclides, utilize various irradiation sources, and account for increasingly complex sample matrices.« less

  11. Measurements of /sup 239/Pu and /sup 235/U fission cross sections and their ratio for neutron energies from 100 ev to 50 kev

    SciTech Connect (OSTI)

    Bergman, A.A.; Kolosovskii, A.G.; Kuznetsov, S.P.; Medvedev, A.N.; Samsonov, A.E.; Tolstikov, V.A.

    1980-07-01

    Values for the ratio of the /sup 239/Pu and /sup 235/U fission cross sections over the energy intervals are in good agreement with Carlson's data. Carlson's data were normalized by the threshold method and also to Lemmel's data, which in turn were normalized to the thermal region. The totality of the data listed on the /sup 235/U fission cross section, Carlson's data, and our results for the ratio of the fission cross sections are inconsistent with the average energy dependence of /sigma/sub //f (/sup 239/Pu) reported in recent papers by Gwin, Gayther, and Ryabov.

  12. Radiochemical procedures for analysis of Pu, Am, Cs and Sr in water, soil, sediments and biota samples

    SciTech Connect (OSTI)

    Wong, K.M.; Jokela, T.A.; Noshkin, V.E.

    1994-02-01

    The Environmental Radioactivity Analysis Laboratory (ERAL) was established as an analytical facility. The primary function of ERAL is to provide fast and accurate radiological data of environmental samples. Over the years, many radiochemical procedures have been developed by the staffs of ERAL. As result, we have found that our procedures exist in many different formats and in many different notebooks, documents and files. Therefore, in order to provide for more complete and orderly documentation of the radiochemical procedures that are being used by ERAL, we have decided to standardize the format and compile them into a series of reports. This first report covers procedures we have developed and are using for the radiochemical analysis of Pu, Am, Cs, and Sr in various matrices. Additional analytical procedures and/or revisions for other elements will be reported as they become available through continuation of these compilation efforts.

  13. CONTAINMENT VESSEL TEMPERATURE FOR PU-238 HEAT SOURCE CONTAINER UNDER AMBIENT, FREE CONVECTION AND LOW EMISSIVITY COOLING CONDITIONS

    SciTech Connect (OSTI)

    Gupta, N.; Smith, A.

    2011-02-14

    The EP-61 primary containment vessel of the 5320 shipping package has been used for storage and transportation of Pu-238 plutonium oxide heat source material. For storage, the material in its convenience canister called EP-60 is placed in the EP-61 and sealed by two threaded caps with elastomer O-ring seals. When the package is shipped, the outer cap is seal welded to the body. While stored, the EP-61s are placed in a cooling water bath. In preparation for welding, several containers are removed from storage and staged to the welding booth. The significant heat generation of the contents, and resulting rapid rise in component temperature necessitates special handling practices. The test described here was performed to determine the temperature rise with time and peak temperature attained for an EP-61 with 203 watts of internal heat generation, upon its removal from the cooling water bath.

  14. Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements.

    SciTech Connect (OSTI)

    Keiser, D. D.

    2006-01-23

    Argonne National Laboratory is developing an electrometallurgical treatment for spent nuclear fuels. The initial demonstration of this process is being conducted on U-Zr and U-Pu-Zr alloy fuel elements irradiated in the Experimental Breeder Reactor-II (EBR-II). The electrometallurgical treatment process extracts usable uranium from irradiated fuel elements and places residual fission products, actinides, process Zr, and cladding hulls (small segments of tubing) into two waste forms--a ceramic and a metal alloy. The metal waste form will contain the cladding hulls, Zr, and noble metal fission products, and it will be disposed of in a geologic repository. As a result, the expected composition of the waste form will need to be well understood. This report deals with the condition of the cladding, which will make up a large fraction of the metal waste form, after irradiation in EBR-II and before insertion into the electrorefiner. Specifically, it looks at layers that can be found on the inner surface of the cladding due to in-reactor interactions between the alloy fuel and the stainless steel cladding that occurs after the fuel has swelled and contacted the cladding. Many detailed examinations of fuel elements irradiated in EBR-II have been completed and are discussed in the context of interaction layer formation in irradiated cladding. The composition and thickness of the developed interaction layers are identified, along with the irradiation conditions, cladding type, and axial location on fuel elements where the thickest interaction layers can be expected to develop. It has been found that the largest interaction zones are observed at combined high power and high temperature regions of fuel elements and for fuel elements with U-Pu-Zr alloy fuel and D9 stainless steel cladding. The most prevalent, non-cladding constituent observed in the developed interaction layers are the lanthanide fission products.

  15. LWR spent fuel reduction by the removal of U and the compact storage of Pu with FP for long-term nuclear sustainability

    SciTech Connect (OSTI)

    Fukasawa, T.; Hoshino, K.; Takano, M.; Sato, S.; Shimazu, Y.

    2013-07-01

    Fast breeder reactors (FBR) nuclear fuel cycle is needed for long-term nuclear sustainability while preventing global warming and maximum utilizing the limited uranium (U) resources. The 'Framework for Nuclear Energy Policy' by the Japanese government on October 2005 stated that commercial FBR deployment will start around 2050 under its suitable conditions by the successive replacement of light water reactors (LWR) to FBR. Even after Fukushima Daiichi Nuclear Power Plant accident which made Japanese tendency slow down the nuclear power generation activities, Japan should have various options for energy resources including nuclear, and also consider the delay of FBR deployment and increase of LWR spent fuel (LWR-SF) storage amounts. As plutonium (Pu) for FBR deployment will be supplied from LWR-SF reprocessing and Japan will not possess surplus Pu, the authors have developed the flexible fuel cycle initiative (FFCI) for the transition from LWR to FBR. The FFCI system is based on the possibility to stored recycled materials (U, Pu)temporarily for a suitable period according to the FBR deployment rate to control the Pu demand/supply balance. This FFCI system is also effective after the Fukushima accident for the reduction of LWR-SF and future LWR-to-FBR transition. (authors)

  16. Melting temperatures of the ZrO{sub 2}-MOX system

    SciTech Connect (OSTI)

    Uchida, T.; Hirooka, S.; Kato, M.; Morimoto, K.; Sugata, H.; Shibata, K.; Sato, D.

    2013-07-01

    Severe accidents occurred at the Fukushima Daiichi Nuclear Power Plant Units 1-3 on March 11, 2011. MOX fuels were loaded in the Unit 3. For the thermal analysis of the severe accident, melting temperature and phase state of MOX corium were investigated. The simulated coriums were prepared from 4%Pu-containing MOX, 8%Pu-containing MOX and ZrO{sub 2}. Then X-ray diffraction, density and melting temperature measurements were carried out as a function of zirconium and plutonium contents. The cubic phase was observed in the 25%Zr-containing corium and the tetragonal phase was observed in the 50% and 75%Zr-containing coria. The lattice parameter and density monotonically changed with Pu content. Melting temperature increased with increasing Pu content; melting temperature were estimated to be 2932 K for 4%Pu MOX corium and 3012 K for 8%Pu MOX corium in the 25%ZrO{sub 2}-MOX system. The lowest melting temperature was observed for 50%Zr-containing corium. (authors)

  17. Evaluation of the ²³⁹Pu prompt fission neutron spectrum induced by neutrons of 500 keV and associated covariances

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

    Neudecker, D.; Talou, P.; Kawano, T.; Smith, D. L.; Capote, R.; Rising, M. E.; Kahler, A. C.

    2015-08-01

    We present evaluations of the prompt fission neutron spectrum (PFNS) of ²³⁹Pu induced by 500 keV neutrons, and associated covariances. In a previous evaluation by Talou et al. 2010, surprisingly low evaluated uncertainties were obtained, partly due to simplifying assumptions in the quantification of uncertainties from experiment and model. Therefore, special emphasis is placed here on a thorough uncertainty quantification of experimental data and of the Los Alamos model predicted values entering the evaluation. In addition, the Los Alamos model was extended and an evaluation technique was employed that takes into account the qualitative differences between normalized model predicted valuesmore » and experimental shape data. These improvements lead to changes in the evaluated PFNS and overall larger evaluated uncertainties than in the previous work. However, these evaluated uncertainties are still smaller than those obtained in a statistical analysis using experimental information only, due to strong model correlations. Hence, suggestions to estimate model defect uncertainties are presented, which lead to more reasonable evaluated uncertainties. The calculated keff of selected criticality benchmarks obtained with these new evaluations agree with each other within their uncertainties despite the different approaches to estimate model defect uncertainties. The keff one standard deviations overlap with some of those obtained using ENDF/B-VII.1, albeit their mean values are further away from unity. Spectral indexes for the Jezebel critical assembly calculated with the newly evaluated PFNS agree with the experimental data for selected (n,γ) and (n,f) reactions, and show improvements for high-energy threshold (n,2n) reactions compared to ENDF/B-VII.1.« less

  18. Evaluation of the ²³⁹Pu prompt fission neutron spectrum induced by neutrons of 500 keV and associated covariances

    SciTech Connect (OSTI)

    Neudecker, D.; Talou, P.; Kawano, T.; Smith, D. L.; Capote, R.; Rising, M. E.; Kahler, A. C.

    2015-08-01

    We present evaluations of the prompt fission neutron spectrum (PFNS) of ²³⁹Pu induced by 500 keV neutrons, and associated covariances. In a previous evaluation by Talou et al. 2010, surprisingly low evaluated uncertainties were obtained, partly due to simplifying assumptions in the quantification of uncertainties from experiment and model. Therefore, special emphasis is placed here on a thorough uncertainty quantification of experimental data and of the Los Alamos model predicted values entering the evaluation. In addition, the Los Alamos model was extended and an evaluation technique was employed that takes into account the qualitative differences between normalized model predicted values and experimental shape data. These improvements lead to changes in the evaluated PFNS and overall larger evaluated uncertainties than in the previous work. However, these evaluated uncertainties are still smaller than those obtained in a statistical analysis using experimental information only, due to strong model correlations. Hence, suggestions to estimate model defect uncertainties are presented, which lead to more reasonable evaluated uncertainties. The calculated keff of selected criticality benchmarks obtained with these new evaluations agree with each other within their uncertainties despite the different approaches to estimate model defect uncertainties. The keff one standard deviations overlap with some of those obtained using ENDF/B-VII.1, albeit their mean values are further away from unity. Spectral indexes for the Jezebel critical assembly calculated with the newly evaluated PFNS agree with the experimental data for selected (n,γ) and (n,f) reactions, and show improvements for high-energy threshold (n,2n) reactions compared to ENDF/B-VII.1.

  19. INTERPRETATION OF AT-LINE SPECTRA FROM AFS-2 BATCH #3 FERROUS SULFAMATE TREATMENT

    SciTech Connect (OSTI)

    Kyser, E.; O'Rourke, P.

    2013-12-10

    Spectra from the at-line spectrometer were obtained during the ferrous sulfamate (FS) valence adjustment step of AFS-2 Batch #3 on 9/18/2013. These spectra were analyzed by mathematical principal component regression (PCR) techniques to evaluate the effectiveness of this treatment. Despite the complications from Pu(IV), we conclude that all Pu(VI) was consumed during the FS treatment, and that by the end of the treatment, about 85% was as Pu(IV) and about 15% was as Pu(III). Due to the concerns about the odd shape of the Pu(IV) peak and the possibility of this behavior being observed in the future, a follow-up sample was sent to SRNL to investigate this further. Analysis of this sample confirmed the previous results and concluded that it odd shape was due to an intermediate acid concentration. Since the spectral evidence shows complete reduction of Pu(VI) we conclude that it is appropriate to proceed with processing of this the batch of feed solution for HB-Line including the complexation of the fluoride with aluminum nitrate.

  20. The CIELO Collaboration:Neutron Reactions on 1H, 16O, 56Fe, 235,238U, and 239Pu

    SciTech Connect (OSTI)

    Palmiotti, Giuseppe; Chadwick, M. B.

    2014-05-29

    CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. The focus will initially be on a small number of the highest-priority isotopes, namely 1H, 16O, 56Fe, 235,238U, and 239Pu. This paper identifies discrepancies between various evaluations of the highest priority isotopes, and was commissioned by the OECD's Nuclear Energy Agency WPEC (Working Party on International Nuclear Data Evaluation Co-operation) during a meeting held in May 2012. The evaluated data for these materials in the existing nuclear data libraries — ENDF/B-VII.1, JEFF-3.1, JENDL-4.0, CENDL-3.1, ROSFOND, IRDFF 1.0 — are reviewed, discrepancies are identified, and some integral properties are given. The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations.

  1. Neutron emission effects on fragment mass and kinetic energy distribution from fission of 239{sup Pu} induced by thermal neutrons

    SciTech Connect (OSTI)

    Montoya, M.; Rojas, J.; Lobato, I.

    2010-08-04

    The average of fragment kinetic energy (E-bar sign*) and the multiplicity of prompt neutrons ({nu}(bar sign)) as a function of fragment mass (m*), as well as the fragment mass yield (Y(m*)) from thermal neutron-induced fission of {sup 239}Pu have been measured by Tsuchiya et al.. In that work the mass and kinetic energy are calculated from the measured kinetic energy of one fragment and the difference of time of flight of the two complementary fragments. However they do not present their results about the standard deviation {sigma}{sub E}*(m*). In this work we have made a numerical simulation of that experiment which reproduces its results, assuming an initial distribution of the primary fragment kinetic energy (E(A)) with a constant value of the standard deviation as function of fragment mass ({sigma}{sub E}(A)). As a result of the simulation we obtain the dependence {sigma}{sub E}*(m*) which presents an enhancement between m* = 92 and m* = 110, and a peak at m* = 121.

  2. International Workshop on Gamma Spectrometry Analysis Codes for U and Pu Isotopics: Workshop Results and Next Steps

    SciTech Connect (OSTI)

    McGinnis, Brent R; Solodov, Alexander A; Shipwash, Jacqueline L; Zhernosek, Alena V; McKinney, Teressa L; Pickett, Chris A; Peerani, Paolo

    2009-01-01

    In November 2008, the Institute of Nuclear Materials Management (INMM) and the European Safeguards Research and Development Association (ESARDA) co-hosted the International Workshop on Gamma Spectrometry Analysis Codes for U and Pu Isotopics at the Oak Ridge National Laboratory (ORNL). This workshop was conducted in response to needs expressed by the international safeguards community to understand better the capabilities and limitations of the codes; to ensure these codes are sustained; and to ensure updates or revisions are performed in a controlled manner. The workshop was attended by approximately 100 participants. The participants included code developers, code suppliers, safeguards specialists, domestic and international inspectors, process operators, regulators, and programme sponsors from various government agencies. The workshop provided a unique opportunity for code developers, commercial distributors and end users to interact in a hands-on laboratory environment to develop solutions for programmatic and technical issues associated with the various codes. The workshop also provided an international forum for discussing development of an internationally accepted standard test method. This paper discusses the organization of the workshop, its goals and objectives and feedback received from the participants. The paper also describes the significance of the working group's contribution to improving codes that are commonly used during inspections to verify that nuclear facilities are compliant with treaty obligations that ensure nuclear fuel cycle facilities are used for peaceful purposes.

  3. On the Potential for Vacancy Annihilation as a Mechanism for Conditioning in Pu-1.9 at.% Ga

    SciTech Connect (OSTI)

    Jeffries, J R; Blobaum, K M; Schwartz, A J

    2009-03-09

    The {delta} {yields} {alpha}{prime} martensitic transformation in Pu-1.9 at.% Ga occurs when the alloy is cooled below about -100 C. This transformation exhibits anomalous behavior, where the isothermal transformation proceeds atypically with double-C kinetics. Recent work has revealed that an ambient temperature isothermal hold (referred to as conditioning) prior to the transformation has different effects depending on whether transformation proceeds in the upper- or lower-C of the double-C: the amount of transformation is increased with conditioning in the upper-C, while the transformation in the lower-C seems to be engendered by conditioning. The mechanism by which conditioning affects the low-temperature {delta} {yields} {alpha}{prime} transformation is thus of great importance to understanding the transformation itself as well as the general circumstances that can affect a martensitic phase transformation. Using differential scanning calorimetry measurements, vacancy annihilation as a mechanism for the conditioning effect has been examined. While there are some characteristics of the conditioning effect that are reminiscent of vacancy annihilation, the results of these experiments suggest that vacancy annihilation is not a likely candidate description for the conditioning effect.

  4. Evaluated Mean Values and Covariances for the Prompt Fission Neutron Spectrum of 239Pu induced by neutrons of 500 keV

    SciTech Connect (OSTI)

    Neudecker, Denise

    2014-07-10

    This document provides the numerical values of the evaluated prompt fission neutron spectrum for 239Pu induced by neutrons of 500 keV as well as relative uncertainties and correlations. This document also contains a short description how these data were obtained and shows plots comparing the evaluated results to experimental information as well as the corresponding ENDF/B-VII.1 evaluation.

  5. REDUCTION OF PLUTONIUM TO Pu$sup +3$ BY SODIUM DITHIONITE IN POTASSIUM CARBONATE

    DOE Patents [OSTI]

    Miller, D.R.; Hoekstra, H.R.

    1958-12-16

    Plutonium values are reduced in an alkaline aqueous medlum to the trlvalent state by means of sodium dlthionite. Plutonlum values are also separated from normally assoclated contaminants by metathesizing a lanthanum fluoride carrier precipitate containing plutonium with a hydroxide solution, performing the metathesis in the presence of about 0.2 M sodium dithionite at a temperature of between 40 and 90 icient laborato C.

  6. Reaction kinetics for the high temperature oxidation of Pu--1wt%Ga in water vapor

    SciTech Connect (OSTI)

    Stakebake, J L; Saba, M A

    1988-01-01

    Oxidation of plutonium metal is greatly accelerated by the presence of water vapor. The magnitude of the effect of water vapor on oxidation kinetics is determined by temperature, water concentration, and oxygen concentration. Most of the previous work has been directed toward evaluating the effect of moisture on the atmospheric oxidation of plutonium. Work on the isolation and characterization of the water reaction with plutonium has been very limited. The present work was undertaken to determine the kinetics of the plutonium--water reaction over a wide range of temperature and pressure. Reaction kinetics were measured using a vacuum microbalance system. The temperature range investigated was 100--500/degree/C. The effect of water vapor pressure on reaction kinetics was determined at 300/degree/C by varying the water pressure from 0.1 to 15 Torr. 2 figs.

  7. Spin-orbit holds the heavyweight title for Pu and Am: Exchange regains it for Cm

    SciTech Connect (OSTI)

    Moore, K; der Laan, G v; Soderlind, P

    2008-01-10

    The conclusions of this paper are: (1) The 5f electrons in Cm are near an LS coupling scheme. (2) This coupling scheme allows for a large spin polarization of the 5f electrons, which in turn stabilizes the Cm III crystal structure. (3) Results for Cm show us the recipe for magnetic stabilization of the crystal structure of metals: (A) The metal must be near the itinerant-localized transition where multiple crystal structures have close energies; (B) The metal is just on the magnetic side of the transition; and (C) There must be a magnetic moment large enough to overcome the energy difference between crystal structures, thus dictating the atomic geometry. (4) These results solidify our understanding of magnetically-stabilized metals, showing us where to look for engineered materials with magnetic applications.

  8. Noble gas component organization in Apollo 14 breccia 14318: /sup 129/I and /sup 244/Pu regolith chronology

    SciTech Connect (OSTI)

    Swindle, T.D.; Caffee, M.W.; Hohenberg, C.M.; Hudson, G.B.; Laul, J.C.; Simon, S.B.; Papike, J.J.

    1985-02-15

    Noble gas, petrological, and chemical studies made on grain-size separates from lunar regolith breccia 14318 demonstrate that the noble gases are organized into two functional components, volume-correlated and surface-correlated. As in regolith breccia 14301, volume-correlated xenon in 14318 is primarily spallation-derived and the surface-correlated component contains not only solar wind xenon but also significant amounts of ''parentless' xenon from the fission of now extinct /sup 244/Pu and the decay of now extinct /sup 129/I (''parentless'' means the daughter products were incorporated onto grain surfaces following decay of the parent nuclide elsewhere). The ratio of /sup 129/Xe//sup 136/Xe in the total surface-correlated parentless component, as identified in grain-size analysis, is substantially higher than in the least tightly bound parentless component identified in stepwise heating analyses, confirming the trend seen in 14301. If the order of release of gases in stepwise heating is related to the order of incorporation in the simplest way (first in, last out), incorporation of these grain-surface components was probably time-ordered. The /sup 129/Xe//sup 136/Xe ratio in each identifiable parentless component would then be characteristic of the xenon available for surface adsorption at the particular time of acquisition. Continuous variations in this ratio further suggest that incorporation of the parentless xenon was closely coupled with production. Such observations provide the basis for a new chronometer from which we conclude that acquisition of parentless xenon was an ongoing process spanning at least 90 m.y., beginning no more than 44 +- 34 m.y. after the formation of the most meteorites and possibly predating xenon acquisition for the earth.

  9. As-cast microstructures in U-Pu-Zr alloy fuel pins with 5-8 wt% minor actinides and 0-1.5 wt% rare-earth elements

    SciTech Connect (OSTI)

    Dawn E. Janney; J. Rory Kennedy

    2010-11-01

    The Idaho National Laboratory (INL) is investigating U–Pu–Zr alloys with low concentrations of minor actinides (Np and Am) and rare-earth elements (La, Ce, Pr, and Nd) as possible nuclear fuels to be used to transmute minor actinides. Alloys with compositions 60U–20Pu– 3Am–2Np–15Zr, 42U–30Pu–5Am–3Np–20Zr, 59U–20Pu–3Am–2Np–1RE–15Zr, 58.5U–20Pu– 3Am–2Np–1.5RE–15Zr, 41U–30Pu–5Am–3Np–1RE–20Zr, and 40.5U–30Pu–5Am–3Np–1.5RE– 20Zr (where numbers represent weight percents of each element and RE is a rare-earth alloy consisting of 6% La, 16% Pr, 25% Ce, and 53% Nd by weight) were arc-melted and vacuum cast as fuel pins approximately 4 mmin diameter. The as-cast pins were sectioned, polished, and examined by scanning electron microscopy. Each alloy contains high-Zr inclusions surrounded by a high-actinide matrix. Alloys with rare-earth elements also contain inclusions that are high in these elements. Within the matrix, concentrations of U and Zr vary inversely, while concentrations of Np and Pu appear approximately constant. Am occurs in the matrix and with some high-rare-earth inclusions, and occasionally as high-Am inclusions in samples without rare-earth elements.

  10. St. Croix County, Wisconsin: Energy Resources | Open Energy Informatio...

    Open Energy Info (EERE)

    Wisconsin Cady, Wisconsin Cylon, Wisconsin Deer Park, Wisconsin Eau Galle, Wisconsin Emerald, Wisconsin Erin Prairie, Wisconsin Glenwood City, Wisconsin Glenwood, Wisconsin...

  11. The need for precise and well-documented experimental data on prompt fission neutron spectra from neutron-induced fission of 239Pu

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

    Neudecker, Denise; Taddeucci, Terry Nicholas; Haight, Robert Cameron; Lee, Hye Young; White, Morgan Curtis; Rising, Michael Evans

    2016-01-06

    The spectrum of neutrons emitted promptly after 239Pu(n,f)—a so-called prompt fission neutron spectrum (PFNS)—is a quantity of high interest, for instance, for reactor physics and global security. However, there are only few experimental data sets available that are suitable for evaluations. In addition, some of those data sets differ by more than their 1-σ uncertainty boundaries. We present the results of MCNP studies indicating that these differences are partly caused by underestimated multiple scattering contributions, over-corrected background, and inconsistent deconvolution methods. A detailed uncertainty quantification for suitable experimental data was undertaken including these effects, and test-evaluations were performed with themore » improved uncertainty information. The test-evaluations illustrate that the inadequately estimated effects and detailed uncertainty quantification have an impact on the evaluated PFNS and associated uncertainties as well as the neutron multiplicity of selected critical assemblies. A summary of data and documentation needs to improve the quality of the experimental database is provided based on the results of simulations and test-evaluations. Furthermore, given the possibly substantial distortion of the PFNS by multiple scattering and background effects, special care should be taken to reduce these effects in future measurements, e.g., by measuring the 239Pu PFNS as a ratio to either the 235U or 252Cf PFNS.« less

  12. Fission Product Yields of {sup 233}U, {sup 235}U, {sup 238}U and {sup 239}Pu in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons

    SciTech Connect (OSTI)

    Laurec, J.; Adam, A.; Bruyne, T. de [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Bauge, E., E-mail: eric.bauge@cea.f [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Granier, T.; Aupiais, J.; Bersillon, O.; Le Petit, G. [Commissariat a l'Energie Atomique, Centre DAM-Ile de France (CEA DAM DIF), 91297 Arpajon (France); Authier, N.; Casoli, P. [Commissariat a l'Energie Atomique, Centre de Valduc, 21120 Is-sur-Tille (France)

    2010-12-15

    The yields of more than fifteen fission products have been carefully measured using radiochemical techniques, for {sup 235}U(n,f), {sup 239}Pu(n,f) in a thermal spectrum, for {sup 233}U(n,f), {sup 235}U(n,f), and {sup 239}Pu(n,f) reactions in a fission neutron spectrum, and for {sup 233}U(n,f), {sup 235}U(n,f), {sup 238}U(n,f), and {sup 239}Pu(n,f) for 14.7 MeV monoenergetic neutrons. Irradiations were performed at the EL3 reactor, at the Caliban and Prospero critical assemblies, and at the Lancelot electrostatic accelerator in CEA-Valduc. Fissions were counted in thin deposits using fission ionization chambers. The number of fission products of each species were measured by gamma spectrometry of co-located thick deposits.

  13. 2

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

    2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 Points labeled are part of next coarser grid Points labeled 1 are part of next coarser grid 7 by 7 grid of unknowns 3 by 3 grid of unknowns 1 by 1 grid of unknowns P : 9 by 9 grid of points P : 5 by 5 grid of points P : 3 by 3 grid of points (2) (1) (3) 2 2 2 2 2 FEAP FEAP FEAP FEAP FEAP FEAP FEAP FEAP FEAP Prometheus ParMetis METIS METIS METIS METIS METIS METIS METIS METIS Prometheus . . . . PETSc FEAP input file METIS 50 100 150

  14. Crystal structure of high-Zr inclusions in an alloy containing U, Pu, Np, Am, Zr and rare-earth elements

    SciTech Connect (OSTI)

    Dawn E. Janney; James W. Madden; J. Rory Kennedy; Thomas P. O'Holleran

    2014-05-01

    Researchers commonly observe high-Zr inclusions in actinide-Zr alloys. As there is very little published data on the crystal structures of these inclusions, it has generally been assumed that the inclusions were impurity-stabilized a-Zr. However, new electron-diffraction data from two high-Zr inclusions in an alloy containing U, Pu, Np, Am, Zr, and rare-earth elements show that these inclusions are not a-Zr (which has a hexagonal structure) but instead have a face-centered cubic structure. This data is unique in that it combines single-crystal diffraction patterns and microchemical analyses from individual inclusions. More data on other high-Zr inclusions is clearly required. However, the present results suggest that caution is needed in assuming that all high-Zr inclusions in actinide-Zr alloys are a-Zr.

  15. Determination of total Pu content in a Spent Fuel Assembly by Measuring Passive Neutron Count rate and Multiplication with the Differential Die-Away Instrument

    SciTech Connect (OSTI)

    Henzl, Vladimir; Croft, Stephen; Swinhoe, Martyn T.; Tobin, Stephen J.

    2012-07-18

    A key objective of the Next Generation Safeguards Initiative (NGSI) is to evaluate and develop non-destructive assay (NDA) techniques to determine the elemental plutonium content in a commercial-grade nuclear spent fuel assembly (SFA) [1]. Within this framework, we investigate by simulation a novel analytical approach based on combined information from passive measurement of the total neutron count rate of a SFA and its multiplication determined by the active interrogation using an instrument based on a Differential Die-Away technique (DDA). We use detailed MCNPX simulations across an extensive set of SFA characteristics to establish the approach and demonstrate its robustness. It is predicted that Pu content can be determined by the proposed method to a few %.

  16. Cerium(IV), Neptunium(IV), and Plutonium(IV) 1,2-phenyldiphosphonates: Correlations and Differences between Early Transuranium Elements and Their Proposed Surrogates

    SciTech Connect (OSTI)

    Diwu, Juan; Wang, Shuao; Liao, Zuolei; Burns, Peter C.; Albrecht-Schmitt, Thomas E.

    2010-10-04

    The in situ hydrothermal reduction of Np(VI) to Np(IV) and Pu(VI) to Pu(IV) in the presence of 1,2-phenylenediphosphonic acid (PhP2) results in the crystallization of Np[C6H4(PO3H)2]22H2O (NpPhP2) and Pu[C6H4(PO3H)(PO3H2)][C6H4(PO3H)(PO3)]2H2O (PuPhP2), respectively. Similar reactions have been explored with Ce(IV) resulting in the isolation of the Ce(IV) phenylenediphosphonate Ce[C6H4(PO3H)(PO3H2)][C6H4(PO3H)(PO3)]2H2O (CePhP2). Single crystal diffraction studies reveal that although all these three compounds all crystallize in the triclinic space group P1-, only PuPhP2 and CePhP2 are isotypic, whereas NpPhP2 adopts a distinct structure. In the cerium and plutonium compounds edge-sharing dimers of MO8 polyhedra are bridged by the diphosphonate ligand to create one-dimensional chains. NpPhP2 also forms chains. However, the NpO8 units are monomeric. The protonation of the ligands is also different in the two structure types. Furthermore, the NpO8 polyhedra are best described as square antiprisms (D4d), whereas the CeO8 and PuO8 units are trigonal dodecahedra (D2d). Bond-valence parameters of Ro = 1.972 and b = 0.538 have been derived for Np4+ using a combination of the data reported in this work with that available in crystallographic databases. The UV-vis-NIR absorption spectra of NpPhP2 and PuPhP2 are also reported and used to confirm the tetravalent oxidation states.

  17. Fission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on {sup 239}Pu, {sup 235}U, {sup 238}U

    SciTech Connect (OSTI)

    Selby, H.D.; Mac Innes, M.R.; Barr, D.W.; Keksis, A.L.; Meade, R.A.; Burns, C.J.; Chadwick, M.B.; Wallstrom, T.C.

    2010-12-15

    We describe measurements of fission product data at Los Alamos that are important for determining the number of fissions that have occurred when neutrons are incident on plutonium and uranium isotopes. The fission-spectrum measurements were made using a fission chamber designed by the National Institute for Standards and Technology (NIST) in the BIG TEN critical assembly, as part of the Inter-laboratory Liquid Metal Fast Breeder Reactor (LMFBR) Reaction Rate (ILRR) collaboration. The thermal measurements were made at Los Alamos' Omega West Reactor. A related set of measurements were made of fission-product ratios (so-called R-values) in neutron environments provided by a number of Los Alamos critical assemblies that range from having average energies causing fission of 400-600 keV (BIG TEN and the outer regions of the Flattop-25 assembly) to higher energies (1.4-1.9 MeV) in the Jezebel, and in the central regions of the Flattop-25 and Flattop-Pu, critical assemblies. From these data we determine ratios of fission product yields in different fuel and neutron environments (Q-values) and fission product yields in fission spectrum neutron environments for {sup 99}Mo, {sup 95}Zr, {sup 137}Cs, {sup 140}Ba, {sup 141,143}Ce, and {sup 147}Nd. Modest incident-energy dependence exists for the {sup 147}Nd fission product yield; this is discussed in the context of models for fission that include thermal and dynamical effects. The fission product data agree with measurements by Maeck and other authors using mass-spectrometry methods, and with the ILRR collaboration results that used gamma spectroscopy for quantifying fission products. We note that the measurements also contradict earlier 1950s historical Los Alamos estimates by {approx}5-7%, most likely owing to self-shielding corrections not made in the early thermal measurements. Our experimental results provide a confirmation of the England-Rider ENDF/B-VI evaluated fission-spectrum fission product yields that were carried

  18. Energy dependence of fission product yields from 235U, 238U and 239Pu for incident neutron energies between 0.5 and 14.8 MeV

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

    Gooden, M. E.; Arnold, C. W.; Becker, J. A.; Bhatia, C.; Bhike, M.; Bond, E. M.; Bredeweg, T. A.; Fallin, B.; Fowler, M. M.; Howell, C. R.; et al

    2016-01-06

    In this study, Fission Product Yields (FPY) have historically been one of the most observable features of the fission process. They are known to have strong variations that are dependent on the fissioning species, the excitation energy, and the angular momentum of the compound system. However, consistent and systematic studies of the variation of these FPY with energy have proved challenging. This is caused primarily by the nature of the experiments that have traditionally relied on radiochemical procedures to isolate specific fission products. Although radiochemical procedures exist that can isolate all products, each element presents specific challenges and introduces varyingmore » degrees of systematic errors that can make inter-comparison of FPY uncertain. Although of high importance in fields such as nuclear forensics and Stockpile Stewardship, accurate information about the energy dependence of neutron induced FPY are sparse, due primarily to the lack of suitable monoenergetic neutron sources. There is a clear need for improved data, and to address this issue, a collaboration was formed between Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL) and the Triangle Universities Nuclear Laboratory (TUNL) to measure the energy dependence of FPY for 235U, 238U and 239Pu. The measurements have been performed at TUNL, using a 10 MV Tandem Van de Graaff accelerator to produce monoenergetic neutrons at energies between 0.6 MeV to 14.8 MeV through a variety of reactions. The measurements have utilized a dual-fission chamber, with thin (10-100 μg/cm2) reference foils of similar material to a thick (100-400 mg) activation target held in the center between the chambers. This method allows for the accurate determination of the number of fissions that occurred in the thick target without requiring knowledge of the fission cross section or neutron fluence on target. Following activation, the thick target was removed from the dual

  19. Microdistribution and Long-Term Retention of 239Pu (NO3)4 in the Respiratory Tracts of an Acutely Exposed Plutonium Worker and Experimental Beagle Dogs

    SciTech Connect (OSTI)

    Nielsen, Christopher E.; Wilson, Dulaney A.; Brooks, Antone L.; McCord, Stacey; Dagle, Gerald E.; James, Anthony C.; Tolmachev, Sergei Y.; Thrall, Brian D.; Morgan, William F.

    2012-11-01

    The long-term retention of inhaled soluble forms of plutonium raises concerns as to the potential health effects in persons working in nuclear energy or the nuclear weapons program. The distributions of long-term retained inhaled plutonium-nitrate [239Pu (NO3)4] deposited in the lungs of an accidentally exposed nuclear worker (Human Case 0269) and in the lungs of experimentally exposed beagle dogs with varying initial lung depositions were determined via autoradiographs of selected histological lung, lymph node, trachea, and nasal turbinate tissue sections. These studies showed that both the human and dogs had a non-uniform distribution of plutonium throughout the lung tissue. Fibrotic scar tissue effectively encapsulated a portion of the plutonium and prevented its clearance from the body or translocation to other tissues and diminished dose to organ parenchyma. Alpha radiation activity from deposited plutonium in Human Case 0269 was observed primarily along the sub-pleural regions while no alpha activity was seen in the tracheobronchial lymph nodes of this individual. However, relatively high activity levels in the tracheobronchial lymph nodes of the beagles indicated the lymphatic system was effective in clearing deposited plutonium from the lung tissues. In both the human case and beagle dogs, the appearance of retained plutonium within the respiratory tract was inconsistent with current biokinetic models of clearance for soluble forms of plutonium. Bound plutonium can have a marked effect on the dose to the lungs and subsequent radiation exposure has the potential increase in cancer risk.

  20. Environmental considerations associated with siting, constructing, and operating a special isotope separation plant at INEL: Volume 2, Proceedings: Report of public hearings. [AVLIS; Pu isotopes

    SciTech Connect (OSTI)

    Not Available

    1987-03-01

    This report documents the two public hearings conducted for the purpose of determining the scope of issues to be addressed in relation to the siting, constructing, and operating of a special isotope separation plant at INEL. The report includes transcripts of the public hearings held in Idaho Falls, Idaho, February 24, 1987, and in Boise, Idaho, February 26, 1987, and includes the exhibits of record relating to those hearings. The review and hearing process meets pertinent National Environmental Policy Act (NEPA) requirements, Council on Environmental Quality (CEQ) regulations, and DOE guidelines.

  1. JOINT STUDY OF IMPROVED SAFEGUARDS METHODOLOGY USING NO-NOTICE RANDOMIZED INSPECTION AT JNC'S Pu HANDLING FACILITIES

    SciTech Connect (OSTI)

    LU,M.S.; SANBORN,J.B.

    2000-04-01

    After the Iraq war, the International Atomic Energy Agency (IAEA) 93+2 Program was developed to strengthen and improve the cost-effectiveness of the existing safeguards system. In particular, the Program aims to enhance the IAEA ability to detect undeclared nuclear activities and materials. The IAEA 93+2 Program includes: (1) Increased access to information and its effective use; (2) Increased physical access; (3) Optimum use of the existing system. The measures considered are divided in two parts: measures in Part 1 are those, which may be implemented within the existing IAEA authority; Part 2 measures require complementary legal authority, in the form of an additional Protocol, INFCIRC/540. A description of the status of its implementation can be found in ``Implementation of the Additional Protocol'' (Cooley, 1999). In particular, increased physical access includes access beyond locations requiring additional authorities derived from the INFCIRC/540 and no-notice randomized inspections. No-notice randomized inspections could enhance the inspection effectiveness and efficiency by increasing the coverage of the material involved, providing better confirmation of the operational status of the facilities and higher degree of confidence that no undeclared activities or materials existed at the facilities--including the detection of possible measures to conceal diversions.

  2. Analysis Of 2H-Evaporator Scale Wall [HTF-13-82] And Pot Bottom [HTF-13-77] Samples

    SciTech Connect (OSTI)

    Oji, L. N.

    2013-09-11

    Savannah River Remediation (SRR) is planning to remove a buildup of sodium aluminosilicate scale from the 2H-evaporator pot by loading and soaking the pot with heated 1.5 M nitric acid solution. Sampling and analysis of the scale material has been performed so that uranium and plutonium isotopic analysis can be input into a Nuclear Criticality Safety Assessment (NCSA) for scale removal by chemical cleaning. Historically, since the operation of the Defense Waste Processing Facility (DWPF), silicon in the DWPF recycle stream combines with aluminum in the typical tank farm supernate to form sodium aluminosilicate scale mineral deposits in the 2H-evaporator pot and gravity drain line. The 2H-evaporator scale samples analyzed by Savannah River National Laboratory (SRNL) came from two different locations within the evaporator pot; the bottom cone sections of the 2H-evaporator pot [Sample HTF-13-77] and the wall 2H-evaporator [sample HTF-13-82]. X-ray diffraction analysis (XRD) confirmed that both the 2H-evaporator pot scale and the wall samples consist of nitrated cancrinite (a crystalline sodium aluminosilicate solid) and clarkeite (a uranium oxyhydroxide mineral). On ''as received'' basis, the bottom pot section scale sample contained an average of 2.59E+00 {+-} 1.40E-01 wt % total uranium with a U-235 enrichment of 6.12E-01 {+-} 1.48E-02 %, while the wall sample contained an average of 4.03E+00 {+-} 9.79E-01 wt % total uranium with a U-235 enrichment of 6.03E-01% {+-} 1.66E-02 wt %. The bottom pot section scale sample analyses results for Pu-238, Pu-239, and Pu-241 are 3.16E-05 {+-} 5.40E-06 wt %, 3.28E-04 {+-} 1.45E-05 wt %, and <8.80E-07 wt %, respectively. The evaporator wall scale samples analysis values for Pu-238, Pu-239, and Pu-241 averages 3.74E-05 {+-} 6.01E-06 wt %, 4.38E-04 {+-} 5.08E-05 wt %, and <1.38E-06 wt %, respectively. The Pu-241 analyses results, as presented, are upper limit values. For these two evaporator scale samples obtained at two different

  3. Potential health risks from postulated accidents involving the Pu-238 RTG (radioisotope thermoelectric generator) on the Ulysses solar exploration mission

    SciTech Connect (OSTI)

    Goldman, M. ); Nelson, R.C. ); Bollinger, L. ); Hoover, M.D. . Inhalation Toxicology Research Inst.); Templeton, W. ); Anspaugh, L. (Lawren

    1990-11-02

    Potential radiation impacts from launch of the Ulysses solar exploration experiment were evaluated using eight postulated accident scenarios. Lifetime individual dose estimates rarely exceeded 1 mrem. Most of the potential health effects would come from inhalation exposures immediately after an accident, rather than from ingestion of contaminated food or water, or from inhalation of resuspended plutonium from contaminated ground. For local Florida accidents (that is, during the first minute after launch), an average source term accident was estimated to cause a total added cancer risk of up to 0.2 deaths. For accidents at later times after launch, a worldwide cancer risk of up to three cases was calculated (with a four in a million probability). Upper bound estimates were calculated to be about 10 times higher. 83 refs.

  4. Potential health risks from postulated accidents involving the Pu-238 RTG on the Ulysses solar exploration mission

    SciTech Connect (OSTI)

    Goldman, M. ); Nelson, R.C. ); Bollinger, L. ); Hoover, M.D. ); Templeton, W. ); Anspaugh, L. )

    1991-01-01

    Potential radiation impacts from launch of the Ulysses solar exploration experiment were evaluated using eight postulated accident scenarios. Lifetime individual dose estimates rarely exceeded 1 mrem. Most of the potential health effects would come from inhalation exposures immediately after an accident, rather than from ingestion of contaminated food or water, or from inhalation of resuspended plutonium from contaminated ground. For local Florida accidents (that is, during the first minute after launch), an average source term accident was estimated to cause a total added cancer risk of up to 0.2 deaths. For accidents at later times after launch, a worldwide cancer risk of up to three cases was calculated (with a four in a million probability). Upper bound estimates were calculated to be about 10 times higher.

  5. 2Q08Web.doc

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

    ... Pr-144 <1.34E+02 Pm-147 <1.47E+03 Eu-154 3.62E+02 Np-237 (a) (t12 )>5yr <3.16E+01 Pu-238 (a) (t12 ) > 5 yr 3.18E+04 Pu-239 (a) (t 12 ) >5 yr 1.05E+03 Pu-240 (a) (t 1...

  6. Theoretical analyses of (n,xn) reactions on sup 235 U, sup 238 U, sup 237 Np, and sup 239 Pu for ENDF/B-VI

    SciTech Connect (OSTI)

    Young, P.G.; Arthur, E.D.

    1991-01-01

    Theoretical analyses were performed of neutron-induced reactions on {sup 235}U, {sup 238}U, {sup 237}Np, and {sup 239}Pu between 0.01 and 20 MeV in order to calculate neutron emission cross sections and spectra for ENDF/B-VI evaluations. Coupled-channel optical model potentials were obtained for each target nucleus by fitting total, elastic, and inelastic scattering cross section data, as well as low-energy average resonance data. The resulting deformed optical model potentials were used to calculate direct (n,n{prime}) cross sections and transmission coefficients for use in Hauser-Feshbach statistical theory analyses. A fission model with multiple barrier representation, width fluctuation corrections, and preequilibrium corrections were included in the analyses. Direct cross sections for higher-lying vibrational states were calculated using DWBA theory, normalized using B(E{ell}) values determined from (d,d{prime}) and Coulomb excitation data, where available, and from systematics otherwise. Initial fission barrier parameters and transition state density enhancements appropriate to the compound systems involved were obtained from previous analyses, especially fits to charged-particle fission probability data. The parameters for the fission model were adjusted for each target system to obtain optimum agreement with direct (n,f) cross section measurements, taking account of the various multichance fission channels, that is, the different compound systems involved. The results from these analyses were used to calculate most of the neutron (n,n), (n,n{prime}), and (n,xn) cross section data in the ENDF/B/VI evaluations for the above nuclei, and all of the energy-angle correlated spectra. The deformed optical model and fission model parameterizations are described. Comparisons are given between the results of these analyses and the previous ENDF/B-V evaluations as well as with the available experimental data. 14 refs., 3 figs., 1 tab.

  7. Anaerobic Biotransformation and Mobility of Pu and PuEDTA

    SciTech Connect (OSTI)

    Xun, Luying

    2005-06-01

    Although our goal is to isolate anaerobic EDTA degraders, we initiated the experiments to include nitrilotriacetate (NTA), which is a structure homologue of EDTA. All the aerobic EDTA degraders can degrade NTA, but the isolated NTA degraders cannot degrade EDTA. Since NTA is a simpler structure homologue, it is likely that EDTA-degrading ability is evolved from NTA degradation. This hypothesis is further supported from our characterization of EDTA and NTA-degrading enzymes and genes (J. Bact. 179:1112-1116; and Appl. Environ. Microbiol. 67:688-695). The EDTA monooxygenase and NTA monooxygenase are highly homologous. EDTA monooxygenase can use both EDTA and NTA as substrates, but NTA monooxygenase can only use NTA as a substrate. Thus, we put our effort to isolate both NTA and EDTA degraders. In case, an anaerobic EDTA degrader is not immediately enriched, we will try to evolve the NTA degraders to use EDTA. Both aerobic and anaerobic enrichment cultures were set.

  8. Anaerobic Biotransformation and Mobility of Pu and PuEDTA

    SciTech Connect (OSTI)

    Xun, Luying

    2005-06-01

    The objective of this report is to isolate anaerobic EDTA-degrading bacteria. Although our goal is to isolate anaerobic EDTA degraders, we initiated the experiments to include nitrilotriacetate (NTA), which is a structure homologue of EDTA. All the aerobic EDTA degraders can degrade NTA, but the isolated NTA degraders cannot degrade EDTA. Since NTA is a simpler structure homologue, it is likely that EDTA-degrading ability is evolved from NTA degradation. This hypothesis is further supported from our characterization of EDTA and NTA-degrading enzymes and genes (J. Bact. 179:1112-1116; and Appl. Environ. Microbiol. 67:688-695). The EDTA monooxygenase and NTA monooxygenase are highly homologous. EDTA monooxygenase can use both EDTA and NTA as substrates, but NTA monooxygenase can only use NTA as a substrate. Thus, we put our effort to isolate both NTA and EDTA degraders. In case, an anaerobic EDTA degrader is not immediately enriched, we will try to evolve the NTA degraders to use EDTA. Both aerobic and anaerobic enrichment cultures were set.

  9. ANALYSIS OF 2H-EVAPORATOR SCALE WALL [HTF-13-82] AND POT BOTTOM [HTF-13-77] SAMPLES

    SciTech Connect (OSTI)

    Oji, L.

    2013-06-21

    Savannah River Remediation (SRR) is planning to remove a buildup of sodium aluminosilicate scale from the 2H-evaporator pot by loading and soaking the pot with heated 1.5 M nitric acid solution. Sampling and analysis of the scale material has been performed so that uranium and plutonium isotopic analysis can be input into a Nuclear Criticality Safety Assessment (NCSA) for scale removal by chemical cleaning. Historically, since the operation of the Defense Waste Processing Facility (DWPF), silicon in the DWPF recycle stream combines with aluminum in the typical tank farm supernate to form sodium aluminosilicate scale mineral deposits in the 2Hevaporator pot and gravity drain line. The 2H-evaporator scale samples analyzed by Savannah River National Laboratory (SRNL) came from the bottom cone sections of the 2H-evaporator pot [Sample HTF-13-77] and the wall 2H-evaporator [sample HTF-13-82]. X-ray diffraction analysis (XRD) confirmed that both the 2H-evaporator pot scale and the wall samples consist of nitrated cancrinite (a crystalline sodium aluminosilicate solid) and clarkeite (a uranium oxy-hydroxide mineral). On “as received” basis, the bottom pot section scale sample contained an average of 2.59E+00 ± 1.40E-01 wt % total uranium with a U-235 enrichment of 6.12E-01 ± 1.48E-02 %, while the wall sample contained an average of 4.03E+00 ± 9.79E-01 wt % total uranium with a U-235 enrichment of 6.03E-01% ± 1.66E-02 wt %. The bottom pot section scale sample analyses results for Pu-238, Pu-239, and Pu-241 are 3.16E- 05 ± 5.40E-06 wt %, 3.28E-04 ± 1.45E-05 wt %, and <8.80E-07 wt %, respectively. The evaporator wall scale samples analysis values for Pu-238, Pu-239, and Pu-241 averages 3.74E-05 ± 6.01E-06 wt %, 4.38E-04 ± 5.08E-05 wt %, and <1.38E-06 wt %, respectively. The Pu-241 analyses results, as presented, are upper limit values. These results are provided so that SRR can calculate the equivalent uranium-235 concentrations for the NCSA. Results confirm that

  10. Preliminary Neutronics Design and Analysis of D2O Cooled High Conversion PWRs

    SciTech Connect (OSTI)

    Hikaru Hiruta; Gilles Youinou

    2012-09-01

    This report presents a neutronics analysis of tight-pitch D2O-cooled PWRs loaded with MOX fuel and focuses essentially on the Pu breeding potential of such reactors as well as on an important safety parameter, the void coefficient, which has to be negative. It is well known that fast reactors have a better neutron economy and are better suited than thermal reactors to breed fissile material from neutron capture in fertile material. Such fast reactors (e.g. sodium-cooled reactors) usually rely on technologies that are very different from those of existing water-cooled reactors and are probably more expensive. This report investigates another possibility to obtain a fast neutron reactor while still relying mostly on a PWR technology by: (1) Tightening the lattice pitch to reduce the water-to-fuel volume ratio compared to that of a standard PWR. Water-to-fuel volume ratios of between 0.45 and 1 have been considered in this study while a value of about 2 is typical of standard PWRs, (2) Using D2O instead of H2O as a coolant. Indeed, because of its different neutron physics properties, the use of D2O hardens the neutron spectrum to an extent impossible with H2O when used in a tight-pitch lattice. The neutron spectra thus obtained are not as fast as those in sodium-cooled reactor but they can still be characterized as fast compared to that of standard PWR neutron spectra. In the phase space investigated in this study we did not find any configurations that would have, at the same time, a positive Pu mass balance (more Pu at the end than at the beginning of the irradiation) and a negative void coefficient. At this stage, the use of radial blankets has only been briefly addressed whereas the impact of axial blankets has been well defined. For example, with a D2O-to-fuel volume ratio of 0.45 and a core driver height of about 60 cm, the fissile Pu mass balance between the fresh fuel and the irradiated fuel (50 GWd/t) would be about -7.5% (i.e. there are 7.5% fewer fissile Pu

  11. Pope County, Minnesota: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Minnesota Brooten, Minnesota Cyrus, Minnesota Farwell, Minnesota Glenwood, Minnesota Long Beach, Minnesota Lowry, Minnesota Sedan, Minnesota Starbuck, Minnesota Villard,...

  12. Sediment studies at Bikini Atoll part 2. inventories of transuranium elements in surface sediments

    SciTech Connect (OSTI)

    Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Robison, W.L.

    1997-10-01

    This is the second of three reports on Bikini sediment studies, which discusses the concentrations and inventories of {sup 241}Am and {sup 239+240}Pu in sediments from the lagoon. Surface sediment samples were collected from 87 locations over the entire lagoon at Bikini Atoll during 1979. The collections were made to map the distribution of long-lived radionuclides associated with the bottom material and to show what modifications occurred in the composition of the sediment as a result of the testing program. Present inventories for {sup 241}Am and {sup 239+240}Pu in the surface 2 cm of sediment are estimated to be 14 and 17 TBq, respectively. These values are estimated to represent only 14% of the total inventory in the sediment column. Sediment inventories of {sup 239+240}Pu and {sup 241}Am are changing only slowly with time through chemical- physical processes that continuously mobilize small amounts of the transuranics to the water column. The lowest concentrations and inventories are associated with deposits logoonward of the eastern reef.

  13. Comparison of Gas Puff Imaging Data in NSTX with the DEGAS 2 Simulation

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Comparison of Gas Puff Imaging Data in NSTX with the DEGAS 2 Simulation Citation Details In-Document Search Title: Comparison of Gas Puff Imaging Data in NSTX with the DEGAS 2 Simulation Gas-Pu -Imaging (GPI) is a two dimensional diagnostic which measures the edge Dα light emission from a neutral Dα gas puff near the outer mid- plane of the National Spherical Torus Experiment (NSTX). DEGAS 2 is a 3-D Monte Carlo code used to model neutral transport and

  14. Materials compatibility during the chlorination of molten CaCl/sub 2/. CaO salts. [CaCl/sub 2/. CaO salt

    SciTech Connect (OSTI)

    Rense, C.E.C.; Fife, K.W.; Bowersox, D.F.; Ferran, M.D.

    1987-01-01

    As part of our effort to develop a semicontinuous PuO/sub 2/ reduction process, we are investigating promising materials for containing a 900/sup 0/C molten CaCl/sub 2/ . CaO chlorination reaction. We want the material to contain this reaction and to be reusable. We tested candidate materials in a simulated salt (no plutonium) using anhydrous HCl as the chlorinating agent. Data are presented on the performance of 36 metals and alloys, 9 ceramics, and 3 coatings.

  15. PAT-2 (Plutonium Air-Transportable Model 2) safety analysis report

    SciTech Connect (OSTI)

    Andersen, J.A.; Davis, E.J.; Duffey, T.A.; Dupree, S.A.; George, O.L. Jr.; Ortiz, Z.

    1981-07-01

    The PAT-2 package is designed for the safe transport of plutonium and/or uranium in small quantities. The PAT-2 package is resistant to severe accidents, including that of a high-speed jet aircraft crash, and is designed to withstand such environments as extreme impact, crushing, puncturing and slashing loads, severe hydrocarbon-fueled fires, and deep underwater immersion, with no escape of contents. The package meets the requirements of 10 CFR 71 for Fissile Class I packages with a cargo of 15 grams of Pu-239, or other isotopic forms described herein, not to exceed 2 watts of thermal activity. This SAR presents design and oprational information including evaluations and analyses, test results, operating procedures, maintenance, and quality assurance information.

  16. Design and Nuclear-Safety Related Simulations of Bare-Pellet Test Irradiations for the Production of Pu-238 in the High Flux Isotope Reactor using COMSOL

    SciTech Connect (OSTI)

    Freels, James D; Jain, Prashant K; Hobbs, Randy W

    2012-01-01

    The Oak Ridge National Laboratory (ORNL)is developing technology to produce plutonium-238 for the National Aeronautics and Space Administration (NASA) as a power source material for powering vehicles while in deep-space[1]. The High Flux Isotope Reactor (HFIR) of ORNL has been utilized to perform test irradiations of incapsulated neptunium oxide (NpO2) and aluminum powder bare pellets for purposes of understanding the performance of the pellets during irradiation[2]. Post irradiation examinations (PIE) are currently underway to assess the effect of temperature, thermal expansion, swelling due to gas production, fission products, and other phenomena

  17. Preliminary Assessment for CAU 485: Cactus Spring Ranch Pu and Du Site, CAS No. TA-39-001-TAGR: Soil Contamination, Tonapah Test Range, Nevada

    SciTech Connect (OSTI)

    ITLV

    1998-07-01

    Corrective Action Unit 485, Corrective Action Site TA-39-001-TAGR, the Cactus Spring Ranch Soil Contamination Area, is located approximately six miles southwest of the Area 3 Compound at the eastern mouth of Sleeping Column Canyon in the Cactus Range on the Tonopah Test Range. This site was used in conjunction with animal studies involving the biological effects of radionuclides (specifically plutonium) associated with Operation Roller Coaster. According to field records, a hardened layer of livestock feces ranging from 2.54 centimeters (cm) (1 inch [in.]) to 10.2 cm (4 in.) thick is present in each of the main sheds. IT personnel conducted a field visit on December 3, 1997, and noted that the only visible feces were located within the east shed, the previously fenced area near the east shed, and a small area southwest of the west shed. Other historical records indicate that other areas may still be covered with animal feces, but heavy vegetation now covers it. It is possible that radionuclides are present in this layer, given the history of operations in this area. Chemicals of concern may include plutonium and depleted uranium. Surface soil sampling was conducted on February 18, 1998. An evaluation of historical documentation indicated that plutonium should not be and depleted uranium could not be present at levels significantly above background as the result of test animals being penned at the site. The samples were analyzed for isotopic plutonium using method NAS-NS-3058. The results of the analysis indicated that plutonium levels of the feces and surface soil were not significantly elevated above background.

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

    SciTech Connect (OSTI)

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

    2012-10-30

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

  19. Supercritical-fluid carbon dioxide (SCCO{sub 2}) cleaning of nuclear weapon components

    SciTech Connect (OSTI)

    Taylor, C.M.V.; Sivils, L.D.; Rubin, J.B.

    1998-05-01

    Supercritical fluid carbon dioxide (SCCO{sub 2}) has been evaluated as a cleaning solvent for the cleaning of plutonium (Pu) metal parts. The results of the evaluation show that SCCO{sub 2} is an effective alternative to halogenated solvents that are conventionally used for removing organic and inorganic contaminants from the surface of these parts. The cleaning process was demonstrated at the laboratory scale for steel and uranium substrates and has been found to be compatible with Pu. The efficacy of this cleaning method is found to be dependent on process conditions of pressure, temperature, fluid-flow rate, as well as cleaning time. Process parameters of P > 2,500 psi, T > 40 C, and moderate fluid flow rates, produced good cleaning results in less than 10 minutes using a simple flow-through process configuration. Within the parameter range studied, cleaning efficiency generally improved with increasing process pressure and flow rate. SCCO{sub 2} cleaning is suitable for a variety of component cleaning tasks and is adaptable to precision cleaning requirements. The SCCO{sub 2} cleaning process is currently being developed for deployment for weapons production at LANL.

  20. Analysis Of 2H-Evaporator Scale Pot Bottom Sample [HTF-13-11-28H

    SciTech Connect (OSTI)

    Oji, L. N.

    2013-07-15

    . dev. = 8.25E-01 wt %). Analyses results for Pu-238 and Pu-239, and Pu-241 are 7.06E-05 {+-} 7.63E-06 wt %, 9.45E-04 {+-} 3.52E-05 wt %, and <2.24E-06 wt %, respectively. These results are provided so that SRR can calculate the equivalent uranium-235 concentrations for the NCSA. Because this 2H evaporator pot bottom scale sample contained a significant amount of elemental mercury (11.7 wt % average), it is recommended that analysis for mercury be included in future Technical Task Requests on 2H evaporator sample analysis at SRNL. Results confirm that the uranium contained in the scale remains depleted with respect to natural uranium. SRNL did not calculate an equivalent U-235 enrichment, which takes into account other fissionable isotopes U-233, Pu-239 and Pu-241.

  1. BISMUTH PHOSPHATE CARRIER PROCESS FOR Pu RECOVERY

    DOE Patents [OSTI]

    Finzel, T.G.

    1959-02-01

    An improvement in the bismuth phosphate carrier precipitation process for recovering plutonium is described. It has been found that a more granular and more easily filterable carrier precipitiite is formed if the addition of the bismuth and phosphate ions is effected by first adding 9/10 of the bismuth ions necessary, then slowly adding all of the source of the phosphate ions to be incorporated in the precipitate, while digesting at 75 C and afterwards incorporating the remainder of the total bismuth ions necessary

  2. Calorimetry of low mass Pu239 items

    SciTech Connect (OSTI)

    Cremers, Teresa L; Sampson, Thomas E

    2010-01-01

    Calorimetric assay has the reputation of providing the highest precision and accuracy of all nondestructive assay measurements. Unfortunately, non-destructive assay practitioners and measurement consumers often extend, inappropriately, the high precision and accuracy of calorimetric assay to very low mass items. One purpose of this document is to present more realistic expectations for the random uncertainties associated with calorimetric assay for weapons grade plutonium items with masses of 200 grams or less.

  3. Progress on Nuclear Data Covariances: AFCI-1.2 Covariance Library

    SciTech Connect (OSTI)

    Oblozinsky,P.; Oblozinsky,P.; Mattoon,C.M.; Herman,M.; Mughabghab,S.F.; Pigni,M.T.; Talou,P.; Hale,G.M.; Kahler,A.C.; Kawano,T.; Little,R.C.; Young,P.G

    2009-09-28

    Improved neutron cross section covariances were produced for 110 materials including 12 light nuclei (coolants and moderators), 78 structural materials and fission products, and 20 actinides. Improved covariances were organized into AFCI-1.2 covariance library in 33-energy groups, from 10{sup -5} eV to 19.6 MeV. BNL contributed improved covariance data for the following materials: {sup 23}Na and {sup 55}Mn where more detailed evaluation was done; improvements in major structural materials {sup 52}Cr, {sup 56}Fe and {sup 58}Ni; improved estimates for remaining structural materials and fission products; improved covariances for 14 minor actinides, and estimates of mubar covariances for {sup 23}Na and {sup 56}Fe. LANL contributed improved covariance data for {sup 235}U and {sup 239}Pu including prompt neutron fission spectra and completely new evaluation for {sup 240}Pu. New R-matrix evaluation for {sup 16}O including mubar covariances is under completion. BNL assembled the library and performed basic testing using improved procedures including inspection of uncertainty and correlation plots for each material. The AFCI-1.2 library was released to ANL and INL in August 2009.

  4. Kondo Physics and Unconventional Superconductivity in the U Intermetallic U2PtC2 Revealed by NMR

    SciTech Connect (OSTI)

    Mounce, Andrew M.; Thompson, Joe David

    2015-12-17

    The set of slides begins by discussing the topic NMR of heavy fermion superconductors under the topics heavy fermion materials, superconductivity, and nuclear magnetic resonance. The history of these phenomena is sketched, with particular mention made of CeCu2Si2, UPt3, and UBe13. Unconventional superconductivity, which is non-phonon mediated superconductivity, presents a high Tc (up to ~150 K), and involves a more complicated spin/orbital wave function. The presentation then goes on to give experimental NMR results for U2PtC2 and Pu-115’s.

  5. Experimental studies of actinide volatilities with application to mixed waste oxidation processors

    SciTech Connect (OSTI)

    Krikorian, O.H.; Ebbinghaus, B.B.; Condit, R.H.; Adamson, M.G.; Fontes, A.S. Jr.; Fleming, D.L.

    1993-04-30

    The transpiration technique is used to measure volatilities of U from U{sub 3}O{sub 8}(s), Pu from PuO{sub 2}(s) and Pu and Am from PuO{sub 2}/2%AmO{sub 2}(s) in the presence of steam and oxygen at temperatures ranging from 900 to 1300{degree}C.

  6. Investigation of the Performance of D2O-Cooled High-Conversion...

    Office of Scientific and Technical Information (OSTI)

    ... FeCrAl) on the performance of Pu conversion ... The report also shows sensitivity and uncertainty analyses ... parameters (keff and void coefficient) for selected reactor cores ...

  7. Ames Laboratory Middle School Science Bowl Feb. 20 | The Ames...

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

    (Adel), Ames, Boone, Clarion-Goldfield, Dallas Center-Grimes, Eleanor Roosevelt (Dubuque), Glenwood, Le Mars, Lenox, Madrid, Melcher-Dallas, New Hampton, North Union (Swea City), ...

  8. Health Spa Space Heating Low Temperature Geothermal Facility...

    Open Energy Info (EERE)

    Spa Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Health Spa Space Heating Low Temperature Geothermal Facility Facility Glenwood Springs Health...

  9. PowerPoint Presentation

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

    Simon Sandstone Jordan Sandstone St. Peter Sandstone Glenwood Fm. Precambrian Geology of Iowa Dallas Center Structure Dallas Center Structure Stanhope Structure Stanhope Structure ...

  10. Analysis of burnup and isotopic compositions of BWR 9 x 9 UO{sub 2} fuel assemblies

    SciTech Connect (OSTI)

    Suzuki, M.; Yamamoto, T.; Ando, Y.; Nakajima, T.

    2012-07-01

    In order to extend isotopic composition data focusing on fission product nuclides, measurements are progressing using facilities of JAEA for five samples taken from high burnup BWR 9 x 9 UO{sub 2} fuel assemblies. Neutronics analysis with an infinite assembly model was applied to the preliminary measurement data using a continuous-energy Monte Carlo burnup calculation code MVP-BURN with nuclear libraries based on JENDL-3.3 and JENDL-4.0. The burnups of the samples were determined to be 28.0, 39.3, 56.6, 68.1, and 64.0 GWd/t by the Nd-148 method. They were compared with those calculated using node-average irradiation histories of power and in-channel void fractions which were taken from the plant data. The comparison results showed that the deviations of the calculated burnups from the measurements were -4 to 3%. It was confirmed that adopting the nuclear data library based on JENDL-4.0 reduced the deviations of the calculated isotopic compositions from the measurements for {sup 238}Pu, {sup 144}Nd, {sup 145}Nd, {sup 146}Nd, {sup 148}Nd, {sup 134}Cs, {sup 154}Eu, {sup 152}Sm, {sup 154}Gd, and {sup 157}Gd. On the other hand, the effect of the revision in the nuclear. data library on the neutronics analysis was not significant for major U and Pu isotopes. (authors)

  11. Verification of RESRAD-RDD. (Version 2.01)

    SciTech Connect (OSTI)

    Cheng, Jing-Jy; Flood, Paul E.; LePoire, David; Kamboj, Sunita; Yu, Charley

    2015-09-01

    In this report, the results generated by RESRAD-RDD version 2.01 are compared with those produced by RESRAD-RDD version 1.7 for different scenarios with different sets of input parameters. RESRAD-RDD version 1.7 is spreadsheet-driven, performing calculations with Microsoft Excel spreadsheets. RESRAD-RDD version 2.01 revamped version 1.7 by using command-driven programs designed with Visual Basic.NET to direct calculations with data saved in Microsoft Access database, and re-facing the graphical user interface (GUI) to provide more flexibility and choices in guideline derivation. Because version 1.7 and version 2.01 perform the same calculations, the comparison of their results serves as verification of both versions. The verification covered calculation results for 11 radionuclides included in both versions: Am-241, Cf-252, Cm-244, Co-60, Cs-137, Ir-192, Po-210, Pu-238, Pu-239, Ra-226, and Sr-90. At first, all nuclidespecific data used in both versions were compared to ensure that they are identical. Then generic operational guidelines and measurement-based radiation doses or stay times associated with a specific operational guideline group were calculated with both versions using different sets of input parameters, and the results obtained with the same set of input parameters were compared. A total of 12 sets of input parameters were used for the verification, and the comparison was performed for each operational guideline group, from A to G, sequentially. The verification shows that RESRAD-RDD version 1.7 and RESRAD-RDD version 2.01 generate almost identical results; the slight differences could be attributed to differences in numerical precision with Microsoft Excel and Visual Basic.NET. RESRAD-RDD version 2.01 allows the selection of different units for use in reporting calculation results. The results of SI units were obtained and compared with the base results (in traditional units) used for comparison with version 1.7. The comparison shows that RESRAD

  12. Off-Site Radiation Exposure Review Project: Phase 2 soils program

    SciTech Connect (OSTI)

    McArthur, R.D.; Miller, F.L. Jr.

    1989-12-01

    To help estimate population doses of radiation from fallout originating at the Nevada Test Site, soil samples were collected throughout the western United States. Each sample was prepared by drying and ball-milling, then analyzed by gamma-spectrometry to determine the amount of {sup 137}Cs it contained. Most samples were also analyzed by chemical separation and alpha-spectrometry to determine {sup 239 + 240}Pu and by isotope mass spectroscopy to determine the ratios of {sup 240}Pu to {sup 239}Pu and {sup 241}Pu to {sup 239}Pu. The total inventories of cesium and plutonium at 171 sites were computed from the results. This report describes the sample collection, processing, and analysis, presents the analytical results, and assesses the quality of the data. 10 refs., 9 figs., 12 tabs.

  13. A Fission Gas Release Model for High-Burnup LWR ThO{sub 2}-UO{sub 2} Fuel

    SciTech Connect (OSTI)

    Long, Yun; Yi Yuan; Kazimi, Mujid S.; Ballinger, Ronald G.; Pilat, Edward E.

    2002-06-15

    Fission gas release in thoria-urania fuel has been investigated by creating a specially modified FRAPCON-3 code. Because of the reduced buildup of {sup 239}Pu and a flatter distribution of {sup 233}U, the new model THUPS (Thoria-Urania Power Shape) was developed to calculate the radial power distribution, including the effects of both plutonium and {sup 233}U. Additionally, a new porosity model for the rim region was introduced at high burnup. The mechanisms of fission gas release in ThO{sub 2}-UO{sub 2} fuel are expected to be essentially similar to those of UO{sub 2} fuel; therefore, the general formulations of the existing fission gas release models in FRAPCON-3 were retained. However, the gas diffusion coefficient was adjusted to a lower level to account for the smaller observed release fraction in the thoria-based fuel. To model the accelerated fission gas release at high burnup properly, a new athermal fission gas release model was introduced. The modified version of FRAPCON-3 was calibrated using the measured fission gas release data from the light water breeder reactor. Using the new model to calculate the gas release in typical pressurized water reactor hot pins gives data that indicate that the ThO{sub 2}-UO{sub 2} fuel will have considerably lower fission gas release above a burnup of 50 MWd/kg HM.

  14. Preliminary Neutronic Study of D2O-cooled High Conversion PWRs

    SciTech Connect (OSTI)

    Hikaru Hiruta; Gilles Youinou

    2013-10-01

    This paper presents a preliminary neutronics analysis of tight-pitch D2O-cooled high-conversion PWRs loaded with MOX fuel aiming at high Pu conversion and negative void coefficient. SCALE6.1 has been exclusively utilized for this study. The analyses are performed in two separate parts. The first part of this paper investigates the performance of axial and internal blankets and seeks break-even or near-breeder core even without the presence of radial blankets. The second part of this paper performs sensitivity and uncertainty analyses of integral parameters (keff and void coefficient) for selected systems in order to analyze the characters of this high-conversion PWR from different aspects.

  15. DOE-HDBK-1145-2001; Radiological Safety Training for Plutonium...

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

    ... Loose PuO 2 powder has a density of about 2 gcm 3 , and sintered pellets have a density ... Loose PuO 2 powder has a density of about 2 gcm 3 , and sintered pellets have a density ...

  16. BENCHMARKING UPGRADED HOTSPOT DOSE CALCULATIONS AGAINST MACCS2 RESULTS

    SciTech Connect (OSTI)

    Brotherton, Kevin

    2009-04-30

    The radiological consequence of interest for a documented safety analysis (DSA) is the centerline Total Effective Dose Equivalent (TEDE) incurred by the Maximally Exposed Offsite Individual (MOI) evaluated at the 95th percentile consequence level. An upgraded version of HotSpot (Version 2.07) has been developed with the capabilities to read site meteorological data and perform the necessary statistical calculations to determine the 95th percentile consequence result. These capabilities should allow HotSpot to join MACCS2 (Version 1.13.1) and GENII (Version 1.485) as radiological consequence toolbox codes in the Department of Energy (DOE) Safety Software Central Registry. Using the same meteorological data file, scenarios involving a one curie release of {sup 239}Pu were modeled in both HotSpot and MACCS2. Several sets of release conditions were modeled, and the results compared. In each case, input parameter specifications for each code were chosen to match one another as much as the codes would allow. The results from the two codes are in excellent agreement. Slight differences observed in results are explained by algorithm differences.

  17. HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX

    SciTech Connect (OSTI)

    Kyser, E. A.; King, W. D.

    2012-07-31

    Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after ~4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

  18. HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX

    SciTech Connect (OSTI)

    Kyser, E.; King, W.

    2012-04-25

    Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after {approx}4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

  19. Aspects of plutonium solution chemistry

    SciTech Connect (OSTI)

    Choppin, G.R.

    1983-01-01

    The effect of pH and complexation on the relative stabilities of the oxidation states of Pu is discussed. A set of ionic radii are presented for Pu in different oxidation states and different coordination numbers. A model for Pu hydration is presented and the relation between hydrolysis and oxidation state evaluated, including the problem of hydrous polymerization. Complexation of Pu is discussed in terms of the relative stabilities of different oxidation states and the effective ionic charge of PuO/sub 2//sup +/ and PuO/sub 2//sup +2/. An equation is proposed for calculating stability constants of Pu complexes and its correlation with experimental values demonstrated. The competition between inner vs outer sphere complexation as affected by the oxidation state of Pu and the pKa of the ligand is reviewed. Two examples of uses of specific complexing agents for Pu indicate a useful direction for future studies. 29 references, 8 figures, 3 tables.

  20. CIRCE2/DEKGEN2

    Energy Science and Technology Software Center (OSTI)

    2007-09-28

    CIRCE2 is a computer code for modeling the optical performance of three-dimensional dish-type and trough-type solar energy concentrators (possibly made up of several separate reflecting surfaces or "facets" of various curvatures and projected shapes). Statistical methods are used to evaluate the directional distribution of reflected rays from any given point on the conventrator. Given concentrator and receiver geometries, sunshape (angular distribution of incident rays from the sun), and concentrator imperfections such as surface roughness andmore » random deviation in slope, the code predicts the flux spatio-angular distribution and total power incident upon the flat or volumetric receiver. Great freedom exists in the variety of concentrator and receiver configurations that can be modeled. Additionally, provisions for shading, blocking, and receiver aperturing are included. DEKGEN2 is a preprocessor designed to facilitate input of sun models and concentrator geometry and surface imperfections.« less

  1. Sorption Behavior and Morphology of Plutonium in the Presence of Goethite at 25 and 80C

    SciTech Connect (OSTI)

    Zavarin, M; Zhao, P; Dai, Z; Carroll, S A; Kersting, A B

    2012-06-11

    In this study, we examined the sorption behavior of Pu at elevated temperatures in the presence of one relevant mineral, goethite ({alpha}-FeOOH), over a range of concentrations that span solubility-controlled to adsorption-controlled concentrations. We focused on the sorptive behavior of two common forms of Pu: aqueous Pu(IV) and intrinsic Pu(IV) nano-colloids at 25 and 80 C in a dilute pH 8 NaCl/NaHCO{sub 3} solution. The morphology of Pu sorbed to goethite was characterized using transmission electron microscopy (TEM). We examined the relative stability of PuO{sub 2} precipitates, PuO{sub 2} nano-colloids, Pu{sub 4}O{sub 7} surface precipitates, and monomeric sorbed Pu as a function of temperature and over a time scale of months.

  2. MOX Fuel Presentation to Duke Board of Directors

    National Nuclear Security Administration (NNSA)

    PuO 2 with 95% depleted UO 2 - Like LEU fuel pellets, MOX fuel pellets are primarily uranium * Fission power comes primarily from plutonium (Pu 239 ) instead of uranium (U 235 )...

  3. Thermodynamic stability of actinide pyrochlore minerals in deep...

    Office of Scientific and Technical Information (OSTI)

    Crystalline phases of pyrochlore (e.g., CaPuTisub 2Osub ... free energies of formation of pyrochlore phases (CaMTisub 2Osub 7). The Pu-pyrochlore phase is predicted to be ...

  4. Plutonium Oxidation and Subsequent Reduction by Mn (IV) Minerals

    SciTech Connect (OSTI)

    KAPLAN, DANIEL

    2005-09-13

    Plutonium sorbed to rock tuff was preferentially associated with manganese oxides. On tuff and synthetic pyrolusite (Mn{sup IV}O{sub 2}), Pu(IV) or Pu(V) was initially oxidized, but over time Pu(IV) became the predominant oxidation state of sorbed Pu. Reduction of Pu(V/VI), even on non-oxidizing surfaces, is proposed to result from a lower Gibbs free energy of the hydrolyzed Pu(IV) surface species versus that of the Pu(V) or Pu(VI) surface species. This work suggests that despite initial oxidation of sorbed Pu by oxidizing surfaces to more soluble forms, the less mobile form of Pu, Pu(IV), will dominate Pu solid phase speciation during long term geologic storage. The safe design of a radioactive waste or spent nuclear fuel geologic repository requires a risk assessment of radionuclides that may potentially be released into the surrounding environment. Geochemical knowledge of the radionuclide and the surrounding environment is required for predicting subsurface fate and transport. Although difficult even in simple systems, this task grows increasingly complicated for constituents, like Pu, that exhibit complex environmental chemistries. The environmental behavior of Pu can be influenced by complexation, precipitation, adsorption, colloid formation, and oxidation/reduction (redox) reactions (1-3). To predict the environmental mobility of Pu, the most important of these factors is Pu oxidation state. This is because Pu(IV) is generally 2 to 3 orders of magnitude less mobile than Pu(V) in most environments (4). Further complicating matters, Pu commonly exists simultaneously in several oxidation states (5, 6). Choppin (7) reported Pu may exist as Pu(IV), Pu(V), or Pu(VI) oxic natural groundwaters. It is generally accepted that plutonium associated with suspended particulate matter is predominantly Pu(IV) (8-10), whereas Pu in the aqueous phase is predominantly Pu(V) (2, 11-13). The influence of the character of Mn-containing minerals expected to be found in subsurface

  5. NR Pu SEIS Advisory 07152010 _final_.doc

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

    NPT Compliance Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires increased investments across the nuclear security enterprise. Maintaining the safety, security and effectiveness of the nuclear deterrent without nuclear testing - especially at lower numbers - requires increased investments across the nuclear security enterprise. Maintaining the safety, security and effectiveness of a smaller nuclear

  6. Feb 1996 PU The Frist 50 Years.pdf

    National Nuclear Security Administration (NNSA)

  7. Microsoft Word - Pu Disposition Red Team Report.docx

    National Nuclear Security Administration (NNSA)

    Final Report of the Plutonium Disposition Red Team Date: 13 August 2015 Oak Ridge, Tennessee Thom Mason, Chair This r eport w as p repared a s a n a ccount o f w ork s ponsored b y a n a gency o f t he U nited S tates Government. N either t he U nited S tates G overnment n or any a gency t hereof, n or a ny o f t heir employees, m akes a ny w arranty, e xpress o r i mplied, o r a ssumes a ny l egal l iability o r responsibility f or t he a ccuracy, c ompleteness, o r u sefulness o f a ny i

  8. The Evolution in Pu Nanocluster Electronic Structure: from Atomicity...

    Office of Scientific and Technical Information (OSTI)

    Close Cite: Bibtex Format Close 0 pages in this document matching the terms "" Search For Terms: Enter terms in the toolbar above to search the full text of this document for ...

  9. Assessment of Plutonium-238 (Pu-238) Production Alternatives

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

    Plutonium-238 Production Alternatives Briefing for Nuclear Energy Advisory Committee April 21, 2008 Dennis ... Statement of Work Desired end state: - Reliable, sustainable, affordable ...

  10. Evaluation of Los Alamos National Laboratory (LANL) PU238 Waste...

    Office of Environmental Management (EM)

    This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the ...

  11. Shenzhen Prosunpro PengSangPu Solar Industrial Products Corporation...

    Open Energy Info (EERE)

    China Zip: 518055 Sector: Solar Product: Shenzhen Prosunpro makes and installs flat panel solar passive energy collectors and engineers central solar hot water systems....

  12. Photochemical oxidation of oxalate in Pu-238 process streams

    SciTech Connect (OSTI)

    Long, K. M.; Ford, D. K.; Trujillo, L. A.

    2003-01-01

    For over forty years, NASA has relied on plutonium-238 in Radioisotope Thermoelectric Generator (RTG) units and Radioisotope Heater Units ( W s ) to provide power and heat for many space missions including Transit, Pioneer, Viking, Voyager, Galileo, Ulysses and Cassini. RHUs provide heat to keep key components warm in extremely cold environments found on planets, moons, or in deep space. RTGs convert heat generated from the radioactive decay of plutonium-238 into electricity using a themocouple, Plutonium-238 has proven to be an excellent heat source far deep space missions because of its high thermal power density, useful lifetime, minimal shielding requirements, and oxide stability.

  13. Elasticity of Pu -a window into fundamental understanding and...

    Office of Scientific and Technical Information (OSTI)

    Visit OSTI to utilize additional information resources in energy science and technology. A ... 2012-05-22 - 2012-05-23 ; Los Alamos, New Mexico, United States Research Org: Los Alamos ...

  14. Report on the Feasibility of Pu Photoelectron Spectroscopy with...

    Office of Scientific and Technical Information (OSTI)

    Authors: Tobin, J G Publication Date: 2012-09-11 OSTI Identifier: 1053685 Report Number(s): LLNL-TR-582213 DOE Contract Number: W-7405-ENG-48 Resource Type: Technical Report ...

  15. Status of Pu-239 Evaluations (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Resource Type: Conference Resource Relation: Conference: NEMEA-7CIELO, International Collaboration on Nuclear Data A workshop of the Collaborative International Evaluated Library ...

  16. NREL to Host Demonstration of Ford's Electric Ranger PU Truck

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

    Renewable Energy Laboratory to Host Demonstration of Ford's Electric Ranger Pickup Truck ... Media are invited to cover Ford's demonstration of the Electric Ranger at the National ...

  17. Microsoft Word - Pu Disposition Red Team Report.docx

    National Nuclear Security Administration (NNSA)

    ... baseline c hange p roposal BWR boiling---water r eactor CCO Criticality C ontrol O ... D isposition A greement PWG Plutonium D isposition W orking G roup PWR pressurized---water ...

  18. Status of Pu-239 Evaluations (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    DOE Contract Number: AC52-06NA25396 Resource Type: Conference Resource Relation: Conference: NEMEA-7CIELO, International Collaboration on Nuclear Data A workshop of the ...

  19. Aluminum Target Dissolution in Support of the Pu-238 Program

    SciTech Connect (OSTI)

    McFarlane, Joanna; Benker, Dennis; DePaoli, David W; Felker, Leslie Kevin; Mattus, Catherine H

    2014-09-01

    Selection of an aluminum alloy for target cladding affects post-irradiation target dissolution and separations. Recent tests with aluminum alloy 6061 yielded greater than expected precipitation in the caustic dissolution step, forming up to 10 wt.% solids of aluminum hydroxides and aluminosilicates. We present a study to maximize dissolution of aluminum metal alloy, along with silicon, magnesium, and copper impurities, through control of temperature, the rate of reagent addition, and incubation time. Aluminum phase transformations have been identified as a function of time and temperature, using X-ray diffraction. Solutions have been analyzed using wet chemical methods and X-ray fluorescence. These data have been compared with published calculations of aluminum phase diagrams. Temperature logging during the transients has been investigated as a means to generate kinetic and mass transport data on the dissolution process. Approaches are given to enhance the dissolution of aluminum and aluminosilicate phases in caustic solution.

  20. V-213: PuTTY SSH Handshake Integer Overflow Vulnerabilities ...

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

    source code repository Addthis Related Articles V-222: SUSE update for Filezilla V-157: Adobe Reader Acrobat Multiple Vulnerabilities V-066: Adobe AcrobatReader Multiple Flaws...

  1. Elasticity of Pu -a window into fundamental understanding and...

    Office of Scientific and Technical Information (OSTI)

    Resource Relation: Conference: Plutonium Aging workshop ; 2012-05-22 - 2012-05-23 ; Los Alamos, New Mexico, United States Research Org: Los Alamos National Laboratory (LANL) ...

  2. RECOVERY OF Pu FROM CERIUM TRIFLUORIDE BY FLUORINATION

    DOE Patents [OSTI]

    Brown, H.S.; Bohlmann, E.G.

    1959-02-10

    An improved process is prcsented for selectively recovering plutonium from a solution containing fission products comprising precipitating cerium trifluoride in the solution for effccting carrier precipitation of plutonium. The resulting carrier precipitate is dried and subjected to fluorination at about 600 C. The plutonium forms a volatile fiuoridc and is so separated from the nonvolatile cerium fluoride.

  3. RECOVERY OF Pu VALUES BY FLUORINATION AND FRACTIONATION

    DOE Patents [OSTI]

    Brown, H.S.; Webster, D.S.

    1959-01-20

    A method is presented for the concentration and recovery of plutonium by fluorination and fractionation. A metallic mass containing uranium and plutonium is heated to 250 C and contacted with a stream of elemental fluorine. After fluorination of the metallic mass, the rcaction products are withdrawn and subjected to a distillation treatment to separate the fluorination products of uranium and to obtain a residue containing the fluorination products of plutonium.

  4. Beamline 4.2.2

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

    Beamline 4.2.2 Beamline 4.2.2 Print Tuesday, 20 October 2009 08:31 Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography...

  5. Part 2

    Office of Environmental Management (EM)

    ... March 13, 2013 PERMIT PART 2 Page 2-6 of 21 2.3.3.6. PCB Waste Wastes with polychlorinated biphenyls (PCBs) not authorized under an EPA PCB waste disposal authorization are not ...

  6. Qualification of the Savannah River National Laboratories Coulometer, Model SRNL-Rev. 2 (Serial # SRNL-003 Coulometer) for use in Process 3401a, Plutonium Assay by Controlled Coulometer

    SciTech Connect (OSTI)

    Tandon, Lav; Colletti, Lisa M.; Drake, Lawrence R.; Lujan, Elmer J. W.; Garduno, Katherine

    2012-08-22

    This report discusses the process used to prove in the SRNL-Rev.2 coulometer for isotopic data analysis used in the special plutonium material project. In May of 2012, the PAR 173 coulometer system that had been the workhorse of the Plutonium Assay team since the early 1970s became inoperable. A new coulometer system had been purchased from Savannah River National Laboratory (SRNL) and installed in August of 2011. Due to funding issues the new system was not qualified at that time. Following the failure of the PAR 173, it became necessary to qualify the new system for use in Process 3401a, Plutonium Assay by Controlled Coulometry. A qualification plan similar to what is described in PQR -141a was followed. Experiments were performed to establish a statistical summary of the performance of the new system by monitoring the repetitive analysis of quality control sample, PEOL, and the assay of plutonium metals obtained from the Plutonium Exchange Program. The data for the experiments was acquired using work instructions ANC125 and ANC195. Figure 1 shows approximately 2 years of data for the PEOL material obtained using the PAR 173. The required acceptance criteria for the sample are that it returns the correct value for the quality control material of 88.00% within 2 sigma (95% Confidence Interval). It also must meet daily precision standards that are set from the historical data analysis of decades of data. The 2 sigma value that is currently used is 0.146 % as evaluated by the Statistical Science Group, CCS-6. The average value of the PEOL quality control material run in 10 separate days on the SRNL-03 coulometer is 87.98% with a relative standard deviation of 0.04 at the 95% Confidence interval. The date of data acquisition is between 5/23/2012 to 8/1/2012. The control samples are run every day experiments using the coulometer are carried out. It is also used to prove an instrument is in statistical control before any experiments are undertaken. The total number of

  7. Beamline 12.2.2

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

    2.2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational...

  8. Amendment 2

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

    2 Page 1 of 1 This Amendment incorporates the following significant changes to solicitation DE-RP36- 07GO97036: I. Sections L3(f)(2)(1)-(2) are deleted and replaced as indicated in Attachment 1. II. Section L4(e)(2)(vi) is deleted and replaced as indicated in attachment 1. III

  9. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational...

  10. Beamline 4.2.2

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

    4.2.2 Print Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) Scientific discipline: Structural biology GENERAL...

  11. March 2

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

    2 March 2 PDSF Users Meeting 3210 Cluster status: Utilization has been heaviest in 6 months, loaded to capacity at times (1000 jobs) Outages: A few problems with some individual...

  12. Method for dissolving plutonium oxide with HI and separating plutonium

    DOE Patents [OSTI]

    Vondra, Benedict L.; Tallent, Othar K.; Mailen, James C.

    1979-01-01

    PuO.sub.2 -containing solids, particularly residues from incomplete HNO.sub.3 dissolution of irradiated nuclear fuels, are dissolved in aqueous HI. The resulting solution is evaporated to dryness and the solids are dissolved in HNO.sub.3 for further chemical reprocessing. Alternatively, the HI solution containing dissolved Pu values, can be contacted with a cation exchange resin causing the Pu values to load the resin. The Pu values are selectively eluted from the resin with more concentrated HI.

  13. Attachment C2

    Office of Environmental Management (EM)

    C2 1 RESERVED 2

  14. ch_2

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

    10 Background 2.2 High-Level Waste Overview 2.2.1 HIGH-LEVEL WASTE DESCRIPTION According to Section 2(12) of the Nuclear Waste Policy Act (42 USC 10101), high-level radioac- tive waste means: In July 1999, DOE issued Order 435.1 Radioactive Waste Management. This Order and its associated Manual and Guidance set forth the authorities, responsibilities, and requirements for the management of DOE's inventory of HLW, transuranic waste, and low-level waste. Specific to HLW, DOE uses the Nuclear Waste

  15. SU-E-I-49: The Evaluation of Usability of Multileaf Collimator for Diagnostic Radiation in Cephalometric Exposure

    SciTech Connect (OSTI)

    Han, S; Kim, K; Jung, H; Kim, M; Ji, Y; Park, S; Choi, S

    2014-06-01

    Purpose: This study evaluated usability of Multileaf collimator (MLC) for diagnostic radiation in cephalometric exposure using optical stimulated luminance dosimeters (OSLDs) Methods: The MLC material was made alloy tool steel (SKD-11) and the density of it is 7.89g/m3 that is similar to it of steel (Fe, 7.85 g/m3) and the MLC was attached to general radiography unit (Rex-650R, Listem Inc, Korea) for cephalometric exposure. The OSLDs that used were nanoDotTM Dosimeter (Landauer Inc, Glenwood, USA) and we read out OSLDs with micro star system (Landauer Inc, Glenwood, USA). The Optical annealing system contained fluorescent lamps (Osram lumilux, 24 W, 280 ?780 nm). To measure absorbed dose using OSLDs, was carried out dosimetric characteristics of OSLDs. Based on these, we evaluated dose reduction of critical organ (Eyes, Thyroids) with MLC in cephalometric exposure Results: The dosimetric characteristics were following that batch homogeneity was 1.21% and reproducibility was 0.96% of the coefficient of variation The linearity was that the correlation of between dose and count was fitted by linear function (dose,mGy = 0.00029 Count, R2 =0.997). The range of angular dependence was from ?3.6% to 3.7% variation when each degree was normalized by zero degree. The organ dose of Rt. eye, Lt eye, thyroids were 77.8 ?Gy, 337.0 ?Gy, 323.1?Gy, respectively in open field and the dose reduction of organ dose was 10.6%(8.3?Gy), 12.4 %(42 ?Gy), 87.1%(281.4?Gy) with MLC Conclusion: We certified dose reduction of organ dose in cephalometric exposure. The dose reduction of Eye was 11% because of reduction of field size and it of thyroids was 87% by primary beam shielding.

  16. February 2

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

    2 February 2 PDSF Users Meeting 2/2/10 Attending: Eric, Jay and Iwona from PDSF and users Andrei, Marjorie, and Jeff P. Cluster status: Utilization has been light Outages: None Upcoming downtimes: None, but Jay mentioned sending a list of nodes for retirement to the pdsf-pi email list. New hardware: Data transfer node has been reaced and has power and installation should be completed this week We will keep the old node alive for a while. ATLAS storage order has been placed. /eliza11 will be

  17. February 2

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

    2 PDSF Users Meeting 2210 Attending: Eric, Jay and Iwona from PDSF and users Andrei, Marjorie, and Jeff P. Cluster status: Utilization has been light Outages: None...

  18. zoltan2

    Energy Science and Technology Software Center (OSTI)

    2012-09-11

    Zoltan2 is a refactoring of the open-source Zoltan library that enables Zoltan users to take better advantage of current and emerging high performance computing architectures and software tools. Like Zoltan, Zoltan2 is a toolkit of combinatorial scientific computing algorithms that enable better performance of scientific codes via improved data locality and parallel scalability. Specifically Zoltan2 partitions data, colors graphs, and orders matrices. Zoltan2 is a software library written in template C++; it supports a widermore » range of data types and problem sizes than Zoltan. It will be available as part of Sandia's Trilinos framework of scientific computing packages.« less

  19. Improved mixed oxide fuel calculations with the evaluated nuclear data library JEFF-3.2

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

    Noguere, G.; Bernard, D.; Blaise, P.; Bouland, O.; Leal, Luiz C.; Leconte, P.; Litaize, O.; Peneliau, Y.; Roque, B.; Santamarina, A.; et al

    2016-02-01

    In this study, an overestimation of the keff values for mixed oxide (MOX) fuels was identified with Monte Carlo (TRIPOLI-4) and deterministic (APOLLO2) calculations based on the Joint Evaluated Fission and Fusion (JEFF) evaluated nuclear data library. The overestimation becomes sizeable with Pit aging, reaching a reactivity change of Delta(p)similar or equal to+700 pcm for integral measurements carried out with MOX fuel containing a large amount of americium. This bias was observed for various critical configurations performed in the zero power reactor EOLE of the Commissariat a l'energie atomique et aux energies alternatives (CEA), Cadarache, France. The present work focusesmore » on the improvements achieved with the new 239PU and 241Am evaluated nuclear data files available in the latest version of the JEFF library (JEFF-3.2). The resolved resonance range of the plutonium evaluation was reevaluated at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, with the Ski/NH code in collaboration with CEA Cadarache. The resonance parameters of the americium evaluation were obtained with the REFIT code in collaboration with the research institutes Institute for Reference Materials and Measurements aRmm, Geel, Belgium, and Institut de recherche sur les lois fondamentales de l'Univers ofio, Saclay, France.« less

  20. DIY2

    SciTech Connect (OSTI)

    Morozov, Dmitriy; Peterka, Tom

    2015-05-01

    DIY2 is a data parallel out-of-core library, written in C++. It provides facilities for domain decomposition into blocks and abstracts both neighborhood and global communication patterns to the level of blocks. DIY2 supports automatic threading. It also provides a data serialization mechanism, using which it allows for automatic movement of blocks in and out of core.

  1. OFF-SITE SURVEILLANCE ACTIVITIES bF TFE

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

    ... RULISON, MILROW, COLORADO ALASKA DeBeque Grand Valley Rulison Rifle Mesa Silt Glenwood ... on Highway 95, 10 miles west of Highway Junction 9516, At these locations at 1740 and ...

  2. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION...

  3. March 2

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

    2 March 2 PDSF Users Meeting 3/2/10 Cluster status: Utilization has been heaviest in 6 months, loaded to capacity at times (~1000 jobs) Outages: A few problems with some individual batch nodes but otherwise nothing. Upcoming downtimes: None. New hardware: ATLAS storave and ALICE nodes should show up in mid March. Retirement plan: Didn't get started on this yet. ATLAS grid activities. No news to report. SL5: still only on pdsf1 and pdsf5 Squid/Fuse: No new news. Other Topics: - STAR project

  4. Slide 2

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

    ... Barrel of Oil Input CostGallon of Fuel @ 42 gallonsBarrel of Oil Crude Oil (DOE Target Price) 90.00 2.14 Biofuel Production Systems Lbs of Sugar for 1 Gallon Biofuel ...

  5. 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.

  6. PRODUCTION OF PLUTONIUM FROM PLUTONIUM FLUORIDE

    DOE Patents [OSTI]

    Baker, R.D.

    1959-06-01

    Reduction of PuF/sub 4/ to metal is described. In the example given, PuF/sub 4/ is mixed with 0.3 mole I/sub 2/ per mole of Pu and Ca powder 25% in excess of that required for eduction of the Pu salt, and I/sub 2/ is added. The mixture is charged to a magnesia-lined steel bomb which is heated until reacted in a furnace. The Pu is reduced to metal and recovered as a slug after the bomb is cooled and opened. About 90% yield is obtained. (T.R.H.)

  7. Beamline 4.2.2

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

    4.2.2 Print Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) Scientific discipline: Structural biology GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend Energy range 5,500-16,000eV Monochromator Rosenbaum-Rock Si(111) sagitally focused monochromator Calculated flux (1.9 GeV, 400 mA) 2.5 x 1011 photons/s at 12 keV Resolving power (E/ΔE) 7,000 with Si(111) crystals Endstations Minihutch Detectors

  8. Beamline 4.2.2

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

    4.2.2 Print Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) Scientific discipline: Structural biology GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend Energy range 5,500-16,000eV Monochromator Rosenbaum-Rock Si(111) sagitally focused monochromator Calculated flux (1.9 GeV, 400 mA) 2.5 x 1011 photons/s at 12 keV Resolving power (E/ΔE) 7,000 with Si(111) crystals Endstations Minihutch Detectors

  9. Beamline 4.2.2

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

    4.2.2 Print Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) Scientific discipline: Structural biology GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend Energy range 5,500-16,000eV Monochromator Rosenbaum-Rock Si(111) sagitally focused monochromator Calculated flux (1.9 GeV, 400 mA) 2.5 x 1011 photons/s at 12 keV Resolving power (E/ΔE) 7,000 with Si(111) crystals Endstations Minihutch Detectors

  10. Beamline 8.2.2

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

    2 Beamline 8.2.2 Print Tuesday, 20 October 2009 08:54 Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size

  11. Beamline 4.2.2

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

    4.2.2 Print Molecular Biology Consortium Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) Scientific discipline: Structural biology GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend Energy range 5,500-16,000eV Monochromator Rosenbaum-Rock Si(111) sagitally focused monochromator Calculated flux (1.9 GeV, 400 mA) 2.5 x 1011 photons/s at 12 keV Resolving power (E/ΔE) 7,000 with Si(111) crystals Endstations Minihutch Detectors

  12. Beamline 8.2.2

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

    2 Beamline 8.2.2 Print Tuesday, 20 October 2009 08:54 Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size

  13. Prosa2

    Energy Science and Technology Software Center (OSTI)

    1984-02-21

    PROSA2 is an implementation of the probalistic response surface technique developed for use with accident analysis programs to conduct probability studies of hypothetical accidents. PROSA2 determines the distribution of a random variale that is a function of many other random variables when this functionality is not known analytically and can be obtained only through parametric studies with a deterministic computer code. The program first systematically provides input parameter combinations, multivariate quadratic response surfaces are generatedmore » approximating the functionality between the input and output of the deterministic code. Using these response surfaces PROSA2 calculates probability histograms and joint histograms for the output variables. Special features of the code generate or treat sensitivities, statistical moments of the input and output variables regionwise response surfaces, correlated input parameters, and conditional distribution.« less

  14. August 2

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

    2 August 2 Attending: Eric, Jay, Craig, JeffA, JeffP, Marjorie Utilization: Cluster mostly full, some free cycles on the weekends. Mostly STAR jobs but quite a lot of groups have been running some. Recent Outages: Nothing major in the past two weeks. Upcoming Downtimes: We will schedule something soon probably for the week of 8/15. Probably an eight hour downtime to complete the /common migration as well as redo some network cabling related to the problems a few weeks ago (borrowed cable from

  15. NSDann2BS, a neutron spectrum unfolding code based on neural networks technology and two bonner spheres

    SciTech Connect (OSTI)

    Ortiz-Rodriguez, J. M.; Reyes Alfaro, A.; Reyes Haro, A.; Solis Sanches, L. O.; Miranda, R. Castaneda; Cervantes Viramontes, J. M.; Vega-Carrillo, H. R.

    2013-07-03

    In this work a neutron spectrum unfolding code, based on artificial intelligence technology is presented. The code called ''Neutron Spectrometry and Dosimetry with Artificial Neural Networks and two Bonner spheres'', (NSDann2BS), was designed in a graphical user interface under the LabVIEW programming environment. The main features of this code are to use an embedded artificial neural network architecture optimized with the ''Robust design of artificial neural networks methodology'' and to use two Bonner spheres as the only piece of information. In order to build the code here presented, once the net topology was optimized and properly trained, knowledge stored at synaptic weights was extracted and using a graphical framework build on the LabVIEW programming environment, the NSDann2BS code was designed. This code is friendly, intuitive and easy to use for the end user. The code is freely available upon request to authors. To demonstrate the use of the neural net embedded in the NSDann2BS code, the rate counts of {sup 252}Cf, {sup 241}AmBe and {sup 239}PuBe neutron sources measured with a Bonner spheres system.

  16. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  17. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  18. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  19. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  20. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  1. Beamline 12.2.2

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

    2.2 Print High-Pressure Endstations: High-pressure single-crystal diffraction(in development, February 2015) High pressure laser heating GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend magnet, 1.9GeV, 5.29Tesla, 500mA Monochromator Si(111) or Multilayer Energy range 6-40 keV for Si(111), 14-28 keV for Multilayer Resolving power (E/ΔE) Si(111) = 7000, Multilayer =100 Beam size (HxV) Focused: 10 x 10 micron Unfocused: 90 x 100 micron Scientific applications

  2. 62413 (2)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Costs Associated With Propane Vehicle Fueling Infrastructure Factors to consider in the implementation of fueling stations and equipment Margaret Smith, New West Technologies (DOE HQ Technical Support) John Gonzales, National Renewable Energy Laboratory This document has been peer reviewed by the propane industry. August 2014 2 Introduction This document is designed to help fleets understand the cost factors associated with propane vehicle fueling infrastructure. It provides an overview of the

  3. ch_2

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

    4 Background 2.1.3 CURRENT MISSION The current INEEL mission is to develop, demonstrate, and deploy advanced engineering technology and systems to improve national competitiveness and security, to make the pro- duction and use of energy more efficient, and to improve the quality of the environment. Areas of primary emphasis at INEEL include waste management and waste minimization, environ- mental engineering and restoration, energy effi- ciency, renewable energy, national security and defense,

  4. Amendment 2

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

    2 Date: 7/25/2016 ISSUED BY: National Renewable Energy Laboratory 15013 Denver West Parkway Golden, CO 80401 PROJECT NAME & LOCATION Service and Preventive Maintenance Agreement for Standby Power Generators The above numbered solicitation is amended as set forth below. The hour and date specified for receipt of offers [] is not extended. [x] is extended to August 3, 2016. OFFERORS ARE ADVISED TO ACKNOWLEDGE THIS AMENDMENT IN THEIR PROPOSAL. FAILURE TO ACKNOWLEDGE THIS AMENDMENT MAY RESULT IN

  5. Chi-Nu Level 2 Review

    SciTech Connect (OSTI)

    Haight, Robert Cameron; Lee, Hye Young; Mosby, Shea Morgan; O'Donnell, John M.; Solomon, Clell Jeffrey Jr.; Taddeucci, Terry Nicholas; Fotiadis, Nikolaos; Devlin, Matthew James; Ullmann, John Leonard; Bredeweg, Todd Allen; Jandel, Marian; Nelson, Ronald Owen; Wender, Stephen Arthur; Neudecker, Denise; Rising, Michael Evan; White, Morgan Curtis; Wu, Ching-Yen; Bucher, Brian Michael; Buckner, Matthew Quinn; Henderson, Roger Alan

    2015-09-18

    This series of slides presents information on Chi-Nu measurements and analysis of prompt fission neutron spectra (PFNS) for neutron energy below 1 MeV for 235U. A key focus of the Chi-Nu measurement is to address the energy dependence of the low-energy emissions. The 235U PFNS evaluation is in progress. Chi-Nu delivered preliminary experimental data and input for part of the old experimental data base. The 239Pu PFNS evaluation is finalized and submitted for testing. Data from 252Cf spontaneous fission will also be obtained.

  6. Section 2

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

    Figure 1. Box plots of differences of 2-minute aver- ages of TB and PWV for non-precipitating conditions. The box encloses 50% of the data; the line inside the box indicates the median. The vertical lines enclose 100% of the data; the circles above and below indicate statistical outliers. The outliers are due to broken cloud fields transiting the radiometers' fields of view at slightly different times. The Liebe-87 model was used to predict the TB at the ARM frequencies from those measured with

  7. TRUSTBUILDER2

    Energy Science and Technology Software Center (OSTI)

    2007-05-15

    In trust negotiation, resource providers specify access control policies in terms of the attributes that should be possessed by authorized users, rather than the identities of these users. Users can prove ownership of certain attributes through the use of digital credentials issued by trusted entities. For example, the Department of Motor Vehicles might issue vehicle owners X.509 driver’s licenses that can be used to demonstrate proof of their current age, address, or ability to drive.more » These types of digital credentials may also be protected by user-specified policies controlling their release to remote parties; for example, Alice might only be willing to show her VISA card credential to members of the Better Business Bureau. In this way, a request to access a given resource can result in a bilateral and iterative exchange of policies and credentials that represents a negotiation between the participating parties. To date, research interest in trust negotiation has been primarily theoretical and any implementations have been largely proofs of concept; experimenting with these prototypes is often not a straightforward task. TrustBuilder2 is a flexible framework for supporting research in the area trust negotiation protocols, designed to allow researchers to quickly prototype and experiment with various approaches to trust negotiation. In TrustBuilder2, the primary components of a trust negotiation system are represented using abstract interfaces.« less

  8. TRUSTBUILDER2

    SciTech Connect (OSTI)

    Lee, Adam J.; Perano, Kenneth J.

    2007-05-15

    In trust negotiation, resource providers specify access control policies in terms of the attributes that should be possessed by authorized users, rather than the identities of these users. Users can prove ownership of certain attributes through the use of digital credentials issued by trusted entities. For example, the Department of Motor Vehicles might issue vehicle owners X.509 driver’s licenses that can be used to demonstrate proof of their current age, address, or ability to drive. These types of digital credentials may also be protected by user-specified policies controlling their release to remote parties; for example, Alice might only be willing to show her VISA card credential to members of the Better Business Bureau. In this way, a request to access a given resource can result in a bilateral and iterative exchange of policies and credentials that represents a negotiation between the participating parties. To date, research interest in trust negotiation has been primarily theoretical and any implementations have been largely proofs of concept; experimenting with these prototypes is often not a straightforward task. TrustBuilder2 is a flexible framework for supporting research in the area trust negotiation protocols, designed to allow researchers to quickly prototype and experiment with various approaches to trust negotiation. In TrustBuilder2, the primary components of a trust negotiation system are represented using abstract interfaces.

  9. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  10. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  11. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  12. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  13. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  14. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  15. TTW 2-2-06

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

    2, 2006 WIPP Quick Facts (As of 02-01-06) 4,295 Shipments received since opening 35,108 Cubic meters of waste disposed 74,480 Containers disposed in the underground New location! The WIPP Santa Fe Office has moved. Come see us at: 2905 Rodeo Park Drive, East Building 4 Santa Fe, New Mexico Anderson appointed manager, Assurance Programs Beck Anderson has been appointed Manager, Assurance Programs. In this position he is responsible for the independent assessment program, corrective action

  16. Beamline 8.2.2

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

    2 Print Berkeley Center for Structural Biology (BCSB) Multiple-Wavelength Anomalous Diffraction (MAD) and Macromolecular Crystallography (MX) GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Superbend (5.0 T, single pole) Energy range 5-16 keV Monochromator Double crystal, Si(111) Measured flux (1.9 GeV, 400 mA) 3.0 x 1011 photons/sec Resolving power (E/ΔE) 7,000 Divergence (max at sample) 3.0(h) x 0.5(v) mrad Measured spot size at sample (FWHM) 100 µm Endstations Minihutch

  17. Plutonium partitioning in uranium and plutonium co-recovery system for fast reactor fuel recycling with enhanced nuclear proliferation resistance

    SciTech Connect (OSTI)

    Nakahara, Masaumi; Koma, Yoshikazu; Nakajima, Yasuo

    2013-07-01

    For enhancement of nuclear proliferation resistance, a 'co-processing' method for U and Pu co-recovery was studied. Two concepts, no U scrubbing and no Pu reduction partitioning, were employed to formulate two types of flow sheets by using a calculation code. Their process performance was demonstrated using radioactive solutions derived from an irradiated fast reactor fuel. These experimental results indicated that U and Pu were co-recovered in the U/Pu product, and the Pu content in the U/Pu product increased approximately 2.3 times regardless of using reductant. The proposed no U scrubbing and no Pu reductant flow sheet is applicable to fast reactor fuel reprocessing and enhances its resistance to nuclear proliferation. (authors)

  18. Am phases in the matrix of a U–Pu–Zr alloy with Np, Am, and rare-earth elements

    SciTech Connect (OSTI)

    Janney, Dawn E.; Kennedy, J. Rory; Madden, James W.; O’Holleran, Thomas P.

    2015-01-01

    Phases and microstructures in the matrix of an as-cast U-Pu-Zr alloy with 3 wt% Am, 2% Np, and 8% rare-earth elements were characterized by scanning and transmission electron microscopy. The matrix consists primarily of two phases, both of which contain Am: ζ-(U, Np, Pu, Am) (~70 at% U, 5% Np, 14% Pu, 1% Am, and 10% Zr) and δ-(U, Np, Pu, Am)Zr2 (~25% U, 2% Np, 10-15% Pu, 1-2% Am, and 55-60 at% Zr). These phases are similar to those in U-Pu-Zr alloys, although the Zr content in ζ-(U, Np, Pu, Am) is higher than that in ζ-(U, Pu) and the Zr content in δ-(U, Np, Pu, Am)Zr2 is lower than that in δ-UZr2. Nanocrystalline actinide oxides with structures similar to UO2 occurred in some areas, but may have formed by reactions with the atmosphere during sample handling. Planar features consisting of a central zone of ζ-(U, Np, Pu, Am) bracketed by zones of δ-(U, Np, Pu, Am)Zr2 bound irregular polygons ranging in size from a few micrometers to a few tens of micrometers across. The rest of the matrix consists of elongated domains of ζ-(U, Np, Pu, Am) and δ-(U, Np, Pu, Am)Zr2. Each of these domains is a few tens of nanometers across and a few hundred nanometers long. The domains display strong preferred orientations involving areas a few hundred nanometers to a few micrometers across.

  19. Photochemical oxygenation of a technetium fluoride using F{sub 2} and O{sub 2}

    SciTech Connect (OSTI)

    Beitz, J.V.; Williams, C.W.

    1996-10-01

    Photochemical conversion of technetium fluorides and oxyfluorides is largely uninvestigated. Because technetium was introduced into U.S. uranium enrichment plants, decommissioning and decontamination of these plants will involve technetium fluorides and oxyfluorides. Photochemical conversion of such compounds may facilitate waste minimization and cost avoidance goals during plant clean-up. Photochemical fluorination using ultraviolet photolysis of a mixture of fluorine and oxygen gases is an effective means of converting solid, nonvolatile fluorides of fight actinides, such as U, Np, and Pu, into volatile hexafluorides thereby removing surface radioactive contamination. Our studies involved the interaction of ultraviolet light, oxygen, and fluorine with technetium fluoride.

  20. Method of immobilizing weapons plutonium to provide a durable, disposable waste product

    DOE Patents [OSTI]

    Ewing, Rodney C.; Lutze, Werner; Weber, William J.

    1996-01-01

    A method of atomic scale fixation and immobilization of plutonium to provide a durable waste product. Plutonium is provided in the form of either PuO.sub.2 or Pu(NO.sub.3).sub.4 and is mixed with and SiO.sub.2. The resulting mixture is cold pressed and then heated under pressure to form (Zr,Pu)SiO.sub.4 as the waste product.

  1. OSMOSE program : statistical review of oscillation measurements in the MINERVE reactor R1-UO2 configuration.

    SciTech Connect (OSTI)

    Stoven, G.; Klann, R.; Zhong, Z.; Nuclear Engineering Division

    2007-08-28

    The OSMOSE program is a collaboration on reactor physics experiments between the United States Department of Energy and the France Commissariat Energie Atomique. At the working level, it is a collaborative effort between the Argonne National Laboratory and the CEA Cadarache Research Center. The objective of this program is to measure very accurate integral reaction rates in representative spectra for the actinides important to future nuclear system designs, and to provide the experimental data for improving the basic nuclear data files. The main outcome of the OSMOSE measurement program will be an experimental database of reactivity-worth measurements in different neutron spectra for the heavy nuclides. This database can then be used as a benchmark to verify and validate reactor analysis codes. The OSMOSE program (Oscillation in Minerve of isotopes in Eupraxic Spectra) aims at improving neutronic predictions of advanced nuclear fuels through oscillation measurements in the MINERVE facility on samples containing the following separated actinides: {sup 232}Th, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 243}Am, {sup 244}Cm, and {sup 245}Cm. The first part of this report provides an overview of the experimental protocol and the typical processing of a series of experimental results which is currently performed at CEA-Cadarache. In the second part of the report, improvements to this technique are presented, as well as the program that was created to process oscillation measurement results from the MINERVE facility in the future.

  2. table2.2_02.xls

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

    Total United States RSE Column Factors: 1.4 0.4 1.6 1.2 1.2 1.1 0.7 1.2 ... 0 0 * 0 324 Petroleum and Coal Products 3,689 * 2 * 0 Q 2 3,407 4.4 324110 Petroleum Refineries 3,307 0 0 0 ...

  3. Design of the Laboratory-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

    SciTech Connect (OSTI)

    Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Orton, Robert D.; Rapko, Brian M.; Smart, John E.

    2015-05-01

    This report describes a design for a laboratory-scale capability to produce plutonium oxide (PuO2) for use in identifying and validating nuclear forensics signatures associated with plutonium production, as well as for use as exercise and reference materials. This capability will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including PuO2 dissolution, purification of the Pu by ion exchange, precipitation, and re-conversion to PuO2 by calcination.

  4. A practical strategy for reducing the future security risk of United States spent nuclear fuel

    SciTech Connect (OSTI)

    Chodak, P. III; Buksa, J.J.

    1997-06-01

    Depletion calculations show that advanced oxide (AOX) fuels can be used in existing light water reactors (LWRs) to achieve and maintain virtually any desired level of US (US) reactor-grade plutonium (R-Pu) inventory. AOX fuels are composed of a neutronically inert matrix loaded with R-Pu and erbium. A 1/2 core load of 100% nonfertile, 7w% R-Pu AOX and 3.9 w% UO{sub 2} has a net total plutonium ({sup TOT}Pu) destruction rate of 310 kg/yr. The 20% residual {sup TOT}Pu in discharged AOX contains > 55% {sup 242}Pu making it unattractive for nuclear explosive use. A three-phase fuel-cycle development program sequentially loading 60 LWRs with 100% mixed oxide, 50% AOX with a nonfertile component displacing only some of the {sup 238}U, and 50% AOX, which is 100% nonfertile, could reduce the US plutonium inventory to near zero by 2050.

  5. 3Q10Web Rev 1, 1-20-11.docm

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

    ... <6.58E+02 <6.58E+02 Eu-154 2.65E+02 2.65E+02 Np-237 () (t 12 ) > 5 yr <1.46E+01 <1.46E+01 Pu-238 () (t 12 ) > 5 yr 2.03E+04 2.03E+04 Pu-239 () (t 12 ) > 5 yr ...

  6. Two Dihydroxo-Bridged Plutonium(IV) Nitrate Dimers and Their Relevance to Trends in Tetravalent Ion Hydrolysis and Condensation

    SciTech Connect (OSTI)

    Knope, Karah E.; Skanthakumar, S.; Soderholm, L.

    2015-11-02

    We report the room temperature synthesis and structural characterization of a μ2-hydroxobridged PuIV dimer obtained from an acidic, nitric acid solution. The discrete Pu2(OH)2(NO3)6(H2O)4 moiety crystallized with two distinct crystal structures, (1) [Pu2(OH)2(NO3)6(H2O)4]2·11H2O and (2) Pu2(OH)2(NO3)6(H2O)4·2H2O, which differ primarily in the number of incorporated water molecules. High-energy X-ray scattering (HEXS) data obtained from the mother liquor showed evidence of a correlation at 3.7(10) Å but only after concentration of the stock solution. This distance is consistent with the dihydroxo-bridged distance of 3.799(1) Å seen in the solid-state structure as well as with the known Pu-Pu distance in PuO2. The structural characterization of a dihydroxo-bridged Pu moiety is discussed in terms of its relevance to the underlying mechanisms of tetravalent-metal-ion condensation

  7. Type B Accident Investigation on the August 5, 2003, Pu-238 Multiple Uptake Event at the Pu Facility, Los Alamos National Laboratory

    Office of Energy Efficiency and Renewable Energy (EERE)

    On August 5, 2003, a release of plutonium-238 occurred in a storage room at the Plutonium Facility, Los Alamos National Laboratory, resulting in radiation doses to two workers in the room. The Accident Investigation Board concluded that the direct cause of the accident was the release of airborne contamination from a degraded package that contained cellulose material and plutonium-238 residues.

  8. Turbocharging the Chrysler 2. 2 liter engine

    SciTech Connect (OSTI)

    Allen, F.E.; Rinschler, G.L.

    1984-01-01

    A new turbocharged 2.2 liter engine has been developed by Chrysler Corporation. It is derived from the Chrysler 2.2 liter naturally aspirated four cylinder powerplant. A number of new and redesigned components were required to yield a durable, high performance.

  9. Beamline 5.3.2.2

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

    3.2.2 Beamline 5.3.2.2 Print Tuesday, 20 October 2009 08:37 Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized

  10. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Beamline 5.3.2.2 Print Tuesday, 20 October 2009 08:37 Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active

  11. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Beamline 5.3.2.2 Print Tuesday, 20 October 2009 08:37 Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active

  12. X-ray absorption fine structure spectroscopic determination of plutonium speciation at the Rocky Flats environmental technology

    SciTech Connect (OSTI)

    Lezama-pacheco, Juan S; Conradson, Steven D; Clark, David L

    2008-01-01

    X-ray Absorption Fine Structure spectroscopy was used to probe the speciation of the ppm level Pu in thirteen soil and concrete samples from the Rocky Flats Environmental Technology Site in support of the site remediation effort that has been successfully completed since these measurements. In addition to X-ray Absorption Near Edge Spectra, two of the samples yielded Extended X-ray Absorption Fine Structure spectra that could be analyzed by curve-fits. Most of these spectra exhibited features consistent with PU(IV), and more specificaJly, PuO{sub 2+x}-type speciation. Two were ambiguous, possibly indicating that Pu that was originally present in a different form was transforming into PuO{sub 2+x}, and one was interpreted as demonstrating the presence of an unusual Pu(VI) compound, consistent with its source being spills from a PUREX purification line onto a concrete floor and the resultant extreme conditions. These experimental results therefore validated models that predicted that insoluble PuO{sub 2+x} would be the most stable form of Pu in equilibrium with air and water even when the source terms were most likely Pu metal with organic compounds or a Pu fire. A corollary of these models' predictions and other in situ observations is therefore that the minimal transport of Pu that occurred on the site was via the resuspension and mobilization of colloidal particles. Under these conditions, the small amounts of diffusely distributed Pu that were left on the site after its remediation pose only a negligible hazard.

  13. Flight Path Target 2

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

    Target 2 provides experimenters direct access to the 800 MeV proton beam as well as several flight paths. Target 2 is located in MPF-7 at LANSCE.. Target 2 Target 2 is housed in ...

  14. ex1ex2v2 Version 2.10

    Energy Science and Technology Software Center (OSTI)

    2007-09-12

    ex1ex2v2 is a translator program which will convert a database in exodus1 format to exodusII format. The exodus 1 format is a defined series of Fortran unformatted writes/reads; the exodusII format is defined by the ExodusII API.

  15. ECO2N V2.0

    SciTech Connect (OSTI)

    Pan, Lehua; Spycher, Nicolas; Doughty, Christine; Pruess, Karsten

    2015-02-01

    ECO2N V2.0 is a fluid property module for the TOUGH2 simulator (Version 2.1) that was designed for applications to geologic sequestration of CO2 in saline aquifers and enhanced geothermal reservoirs. ECO2N V2.0 is an enhanced version of the previous ECO2N V1.0 module (Pruess, 2005). It expands the temperature range up to about 300oC whereas V1.0 can only be used for temperatures below about 110oC. V2.0 includes a comprehensive description of the thermodynamic and thermophysical properties of H2O - NaCl - CO2 mixtures, that reproduces fluid properties largely within experimental error for the temperature, pressure and salinity conditions 10 °C < T < 300 °C, P < 600 bar, and salinity up to halite saturation. This includes density, viscosity, and specific enthalpy of fluid phases as functions of temperature, pressure, and composition, as well as partitioning of mass components H2O, NaCl and CO2 among the different phases. In particular, V2.0 accounts for the effects of water on the thermophysical properties of the CO2-rich phase, which was ignored in V1.0, using a model consistent with the solubility models developed by Spycher and Pruess (2005, 2010). In terms of solubility models, V2.0 uses the same model for partitioning of mass components among the different phases (Spycher and Pruess, 2005) as V1.0 for the low temperature range (<99oC) but uses a new model (Spycher and Pruess, 2010) for the high temperature range (>109oC). In the transition range (99-109oC), a smooth interpolation is applied to estimate the partitioning as a function of the temperature. Flow processes can be modeled isothermally or non-isothermally, and phase conditions represented may include a single (aqueous or CO2-rich) phase, as well as two-phase (brine-CO2) mixtures. Fluid phases may appear or disappear in the course of a simulation, and solid salt may precipitate or dissolve. Note that the model cannot be applied to subcritical conditions that involves both liquid and gaseous CO2 unless

  16. ECO2N V2.0

    Energy Science and Technology Software Center (OSTI)

    2015-02-01

    ECO2N V2.0 is a fluid property module for the TOUGH2 simulator (Version 2.1) that was designed for applications to geologic sequestration of CO2 in saline aquifers and enhanced geothermal reservoirs. ECO2N V2.0 is an enhanced version of the previous ECO2N V1.0 module (Pruess, 2005). It expands the temperature range up to about 300oC whereas V1.0 can only be used for temperatures below about 110oC. V2.0 includes a comprehensive description of the thermodynamic and thermophysical propertiesmore » of H2O - NaCl - CO2 mixtures, that reproduces fluid properties largely within experimental error for the temperature, pressure and salinity conditions 10 °C < T < 300 °C, P < 600 bar, and salinity up to halite saturation. This includes density, viscosity, and specific enthalpy of fluid phases as functions of temperature, pressure, and composition, as well as partitioning of mass components H2O, NaCl and CO2 among the different phases. In particular, V2.0 accounts for the effects of water on the thermophysical properties of the CO2-rich phase, which was ignored in V1.0, using a model consistent with the solubility models developed by Spycher and Pruess (2005, 2010). In terms of solubility models, V2.0 uses the same model for partitioning of mass components among the different phases (Spycher and Pruess, 2005) as V1.0 for the low temperature range (<99oC) but uses a new model (Spycher and Pruess, 2010) for the high temperature range (>109oC). In the transition range (99-109oC), a smooth interpolation is applied to estimate the partitioning as a function of the temperature. Flow processes can be modeled isothermally or non-isothermally, and phase conditions represented may include a single (aqueous or CO2-rich) phase, as well as two-phase (brine-CO2) mixtures. Fluid phases may appear or disappear in the course of a simulation, and solid salt may precipitate or dissolve. Note that the model cannot be applied to subcritical conditions that involves both liquid and gaseous CO2

  17. H2 Safety Snapshot - Vol. 2, Issue 2, July 2011

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

    2, July 2011 How Do I Perform A Hazard Analysis? Perform the hazard analysis at the project's earliest stages using any of the established industry methods described on page 2. A hazard analysis typically consists of the fve major steps shown in the graphic to the right (see Safety Planning Guidance for Hydrogen and Fuel Cell Projects in the list of Helpful Resources on page 2 for more information). Once the hazards are identifed, their risks should be categorized in terms of potential impact

  18. Step 2: Project Options

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

    2: Project Options 2 2 Design 1 Potential 3 Refinement 4 Implementation 2 Options 5 Operations & Maintenance 1/28/2016 2 Presentation Agenda * Step 2: Project Options * Project members and roles * Activity * Project ownership options - Interconnection, net metering, permitting, and considerations * Tools * Case in Point 3 Potential Options Refinement Implementation Operations & Maintenance 4 Step 2: Roles, Business Structures, & Regulatory Considerations Purpose: Determine ownership

  19. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  20. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  1. Beamline 5.3.2.2

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

    5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25

  2. Beamline 5.3.2.2

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

    5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25

  3. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample

  4. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  5. Beamline 5.3.2.2

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

    3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  6. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample

  7. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample

  8. Beamline 5.3.2.2

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

    Beamline 5.3.2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample

  9. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  10. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  11. Beamline 5.3.2.2

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

    2.2 Print Polymer Scanning Transmission X-Ray Microscopy (STXM) @ 5.3.2.2 GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 250-780 eV Monochromator Low-dispersion, spherical-grating monochromator, one grating Calculated flux (1.9 GeV, 500 mA) 1 x 107 photons/s at sample Resolving power (E/ΔE) ≤ 5,000 Endstations Scanning transmission x-ray microscope (STXM) Characteristics Active servo-stabilized toroidal premirror Spot size at sample (FWHM) 25 nm

  12. T2WELL/ECO2N

    Energy Science and Technology Software Center (OSTI)

    002966IBMPC00 T2Well/ECO2N Version 1.0: Multiphase and Non-Isothermal Model for Coupled Wellbore-Reservoir Flow of Carbon Dioxide and Variable Salinity Water http:..esd.lbl.gov/tough/licensing.html

  13. Plutonium(IV) precipitates formed in alkaline media in the presence of various anions

    SciTech Connect (OSTI)

    Krot, N.N.; Shilov, V.P.; Yusov, A.B.; Tananaev, I.G.; Grigoriev, M.S.; Garnov, A.Yu.; Perminov, V.P.; Astafurova, L.N.

    1998-09-01

    The tendency of Pu(IV) to hydrolyze and form true solutions, colloid solutions, or insoluble precipitates has been known since the Manhattan Project. Since then, specific studies have been performed to examine in detail the equilibria of Pu(IV) hydrolytic reactions in various media. Great attention also has been paid to the preparation, structure, and properties of Pu(IV) polymers or colloids. These compounds found an important application in sol-gel technology for the preparation of nuclear fuel materials. A most important result of these works was the conclusion that Pu(IV) hydroxide, after some aging, consists of very small PuO{sub 2} crystallites and should therefore be considered to be Pu(IV) hydrous oxide. However, studies of the properties and behavior of solid Pu(IV) hydroxide in complex heterogeneous systems are rare. The primary goal of this investigation was to obtain data on the composition and properties of Pu(IV) hydrous oxide or other compounds formed in alkaline media under different conditions. Such information is important to understand Pu(IV) behavior and the forms of its existence in the Hanford Site alkaline tank waste sludge. This knowledge then may be applied in assessing plutonium criticality hazards in the storage, retrieval, and treatment of Hanford Site tank wastes as well as in understanding its contribution to the transuranic waste inventory (threshold at 100 nCi/g or about 5 {times} 10{sup {minus}6} M) of the separate solution and solid phases.

  14. Flight Path Target 2

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

    Target 2 provides experimenters direct access to the 800 MeV proton beam as well as several flight paths. Target 2 is located in MPF-7 at LANSCE.. About Target 2 - Lead Slowing ...

  15. HASH v. 2.x

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

    HASH v. 2.x HASH v. 2.x Enhancements to HASH version 1.x October 8, 2014 software Available for thumbnail of Feynman Center (505) 665-9090 Email HASH v. 2.x Enhancements to hash...

  16. Electronic structure of U2PtC2 and U2RhC2

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

    Ronning, F.; Zhu, J. -X.

    2015-03-18

    In this study, we present density functional theory calculations within the generalized gradient approximation of U2RhC2 and U2PtC2. We find the calculated density of states are significantly less than that measured by specific heat indicating the need for electronic correlations. The mass enhancement found for U2PtC2 is m*/mband ≈ 4.

  17. 2. Chemical Kinetics

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

    2 Lecture) Chung K. Law Robert H. Goddard Professor Princeton University Princeton-CEFRC-Combustion Institute Summer School on Combustion June 20-24, 2016 1 Day 2: Generalized Formulations 1. Conservation Equations 1. Derivation and constitutive relations 2. Simplified diffusion-controlled system 3. Conserved scalar formulations 2. Discontinuity Surface Formulations 1. Generalized reaction-sheet formulation 2. Reaction-sheet analysis of diffusion flames 3. Rankine-Hugoniot waves in premixtures 2

  18. Monitoring, Controlling and Safeguarding Radiochemical Streams at Spent Fuel Reprocessing Facilities, Part 2: Gamma-Ray Spectroscopic Methods

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Bryan, Samuel A.; Orton, Christopher R.; Levitskaia, Tatiana G.; Fraga, Carlos G.

    2012-02-10

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-useable nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies based upon gamma-ray and optical spectroscopic measurements to potentially reduce the time and resource burden associated with current techniques. The Multi-Isotope Process (MIP) Monitor uses gamma spectroscopy and multivariate analysis to identify off-normal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major stable flowsheet reagents using UV-Vis, Near IR and Raman spectroscopy. Multi-variate analysis is also applied to the optical measurements in order to quantify concentrations of analytes of interest within a complex array of radiochemical streams. This paper will provide an overview of these methods and reports on-going efforts to develop

  19. Word Pro - S2

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

    Table 2.2 Residential Sector Energy Consumption (Trillion Btu) Primary Consumption a Electricity ... See Note 3, "Supplemental Gaseous Fuels," at end of Section 4. d Includes ...

  20. 2. Chemical Kinetics

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

    3 Lecture) Chung K. Law Robert H. Goddard Professor Princeton University ... fuels 3. Droplet combustion 1. The d 2 -Law 2. Multicomponent fuels 4. Other ...

  1. Polymerizable 2(2-hydroxynaphthyl)2H-benzotriazole compounds

    DOE Patents [OSTI]

    Gomez, P.M.; Neidlinger, H.H.

    1991-07-16

    Benzotriazole compounds having the formula: ##STR1## wherein R.sub.1 is H, Cl, or OCH.sub.3 ; R.sub.2 is a hydroxynaphthyl group; and R.sub.3 is a vinyl unsaturated polymerizable group. Homopolymers or copolymers thereof are effective as UV light stabilizers and absorbers.

  2. Polymerizable 2(2-hydroxynaphthyl)2H-benzotriazole compounds

    DOE Patents [OSTI]

    Gomez, Peter M.; Neidlinger, Hermann H.

    1991-01-01

    Benzotriazole compounds having the formula: ##STR1## wherein R.sub.1 is H, Cl, or OCH.sub.3 ; R.sub.2 is a hydroxynaphthyl group; and R.sub.3 is a vinyl unsaturated polymerizable group. Homopolymers or copolymers thereof are effective as UV light stabilizers and absorbers.

  3. GUM Analysis for SIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2

    SciTech Connect (OSTI)

    Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

    2009-01-01

    This report describes GUM calculations for TIMS and SIMS isotopic ratio measurements of reactor graphite samples. These isotopic ratios are used to estimate reactor burn-up, and currently consist of various ratios of U, Pu, and Boron impurities in the graphite samples. The GUM calculation is a propagation of error methodology that assigns uncertainties (in the form of standard error and confidence bound) to the final estimates.

  4. ARM - Datastreams - sp2

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

    Datastreamssp2 Documentation Data Quality Plots Citation DOI: 10.5439/1182118

  5. Track 2: Worker Engagement

    Broader source: Energy.gov [DOE]

    ISM Workshop Presentations Knoxville Convention Center, Knoxville, TN August 2009 Track 2: Worker Engagement

  6. PLUTONIUM UPTAKE AND BEHAVIOR IN PLANTS OF THE DESERT SOUTHWEST: A PRELIMINARY ASSESSMENT

    SciTech Connect (OSTI)

    Caldwell, E.; Duff, M.; Ferguson, C.

    2011-03-01

    Eight species of desert vegetation and associated soils were collected from the Nevada National Security Site (N2S2) and analyzed for 238Pu and 239+240Pu concentrations. Amongst the plant species sampled were: atmospheric elemental accumulators (moss and lichen), the very slow growing, long-lived creosote bush and the rapidly growing, short-lived cheatgrass brome. The diversity of growth strategies provided insight into the geochemical behavior and bio-availability of Pu at the N2S2. The highest concentrations of Pu were measured in the onion moss (24.27 Bq kg-1 238Pu and 52.78 Bq kg-1 239+240Pu) followed by the rimmed navel lichen (8.18 Bq kg-1 and 18.4 Bq kg-1 respectively), pointing to the importance of eolian transport of Pu. Brome and desert globemallow accumulated between 3 and 9 times higher concentrations of Pu than creosote and sage brush species. These results support the importance of species specific elemental accumulation strategies rather than exposure duration as the dominant variable influencing Pu concentrations in these plants. Total vegetation elemental concentrations of Ce, Fe, Al, Sm and others were also analyzed. Strong correlations were observed between Fe and Pu. This supports the conclusion that Pu was accumulated as a consequence of the active accumulation of Fe and other plant required nutrients. Cerium and Pu are considered to be chemical analogs. Strong correlations observed in plants support the conclusion that these elements displayed similar geochemical behavior in the environment as it related to the biochemical uptake process of vegetation. Soils were also sampled in association with vegetation samples. This allowed for the calculation of a concentration ratio (CR). The CR values for Pu in plants were highly influenced by the heterogeneity of Pu distribution among sites. Results from the naturally occurring elements of concern were more evenly distributed between sample sites. This allowed for the development of a pattern of plant

  7. 2. Chemical Kinetics

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

    3 Lecture) Chung K. Law Robert H. Goddard Professor Princeton University Princeton-CEFRC-Combustion Institute Summer School on Combustion June 20-24, 2016 1 Day 3: Diffusion Flames and Heterogeneous Combustion 1. Burke-Schumann and counterflow flames 2. Heat & mass transfer with condensed fuels 3. Droplet combustion 1. The d 2 -Law 2. Multicomponent fuels 4. Other heterogeneous systems 1. Carbon and metal particles 2. Spray flames 2 1. Burke-Schumann and Counterflow Flames 3 The

  8. 2. Chemical Kinetics

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

    4 Lecture) Chung K. Law Robert H. Goddard Professor Princeton University Princeton-CEFRC-Combustion Institute Summer School on Combustion June 20-24, 2016 1 Day 4: Laminar Premixed Flames 1. The standard premixed flame 1. Phenomenological and asymptotic analyses 2. Parametric dependence 3. Chemical structure 2. Limit phenomena 1. The S-curve concept 2. Extinction through volumetric heat loss 3. Aerodynamics of flames 1. Hydrodynamic stretch 2. Flame stretch 3. Flamefront instabilities 2 1. The

  9. 6th US-Russian Pu Science Workshop Lawrence Livermore National...

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

    Stability, Phase Transformations, and Aging Effects Co-Chairs: Ted Massalski (CMU) and ... Oral Presentation by K. Moore, "Transmission electron microscopy of actinide ...

  10. Materials Data on PuOF (SG:216) by Materials Project

    SciTech Connect (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

  11. Materials Data on PuI3 (SG:63) by Materials Project

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

    Kristin Persson

    2015-02-18

    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

  12. Pu-Zr alloy for high-temperature foil-type fuel

    DOE Patents [OSTI]

    McCuaig, Franklin D.

    1977-01-01

    A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron reflux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.

  13. Pu-ZR Alloy high-temperature activation-measurement foil

    DOE Patents [OSTI]

    McCuaig, Franklin D.

    1977-08-02

    A nuclear reactor fuel alloy consists essentially of from slightly greater than 7 to about 4 w/o zirconium, balance plutonium, and is characterized in that the alloy is castable and is rollable to thin foils. A preferred embodiment of about 7 w/o zirconium, balance plutonium, has a melting point substantially above the melting point of plutonium, is rollable to foils as thin as 0.0005 inch thick, and is compatible with cladding material when repeatedly cycled to temperatures above 650.degree. C. Neutron flux densities across a reactor core can be determined with a high-temperature activation-measurement foil which consists of a fuel alloy foil core sandwiched and sealed between two cladding material jackets, the fuel alloy foil core being a 7 w/o zirconium, plutonium foil which is from 0.005 to 0.0005 inch thick.

  14. Materials Data on PuPd3 (SG:221) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-02-09

    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

  15. Llr. Norgnn of the St. Louis office tolepbonod Dr. ;PuAuff mcently

    Office of Legacy Management (LM)

    Company of 122 East l&xi Btmot, f&w PO* 17, N. ,P., had also expressed an intereat ir.having their mbsidi.arg, the J. T. Baker Chemical Coqany, get into the field. BU aeked...

  16. Materials Data on Pu5Ir3 (SG:140) by Materials Project

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

    Kristin Persson

    2015-02-09

    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. METHOD OF SEPARATING Pu FROM METATHESIZED BiPO$sub 4$ CARRIER

    DOE Patents [OSTI]

    Knox, W.J.; Thompson, S.G.

    1960-05-31

    A process is given for separating uranium, neptunium, and/or plutonium from a bismuth hydroxide carrier by selective dissolution of these actinides with nitric acid of a concentration of from 0.05 to 0.5N.

  18. Type B Accident Investigation on the August 5, 2003, Pu-238 Multiple...

    Energy Savers [EERE]

    Los Alamos National Laboratory Type B Accident Investigation on the August 5, 2003, ... The Accident Investigation Board concluded that the direct cause of the accident was the ...

  19. Microscopic Calculation of 240Pu Scission with a Finite-Range...

    Office of Scientific and Technical Information (OSTI)

    The hot-scission line is identified in the quadrupole-octupole-moment coordinate space. Fission-fragment shapes are extracted from the calculations. A benchmark calculation for ...

  20. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides

    DOE Patents [OSTI]

    Lloyd, Milton H.

    1983-01-01

    Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

  1. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides

    DOE Patents [OSTI]

    Lloyd, M.H.

    1981-01-09

    Method for direct coprocessing of nuclear fuels derived from a product stream of fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

  2. Microsoft Word - Template_SLAC Proprietary Use Agreement_PU 11...

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

    increased flexibility such agreements afford. Where this agreement is to be used as an umbrella agreement for multiple transactions it may be modified to reflect such usage....

  3. Request for One-Time Shipment of 32 Watt PU-328 Source in 9968 Packaging

    SciTech Connect (OSTI)

    Massey, W.M.

    1998-11-25

    The 9968 package is designed for surface shipment of fissile and other radioactive materials where a high degree of double containment is required. The use of the 9968 radioactive material package for a one time shipment of a 32 watt heat source versus the SARP approved maximum 30 watt heat source is addressed in this report. The analyses show that the small increase in heat load from 30 watts to 32 watts does not substantially increase internal temperatures or pressures that would approach limits for the package. Also, the weight of the content is within the current 9968 package limits. It is concluded that the 32-watt heat source can be safely shipped in the 9968 package and therefore a waiver to ship the source is justified.

  4. Analysis of Pu-Only Partitioning Strategies in LMFBR Fuel Cycles...

    Office of Scientific and Technical Information (OSTI)

    A paper copy of this document is also available for sale to the public from the National Technical Information Service, Springfield, VA at www.ntis.gov. Sodium cooled Fast Reactors ...

  5. Discovery of Pu-based superconductors and relation to other classes...

    Office of Scientific and Technical Information (OSTI)

    APA Chicago Bibtex Export Metadata Endnote Excel CSV XML Save to My Library Send to Email Send to Email Email address: Content: Close Send Cite: MLA Format Close Cite: APA ...

  6. Materials Data on PuAs (SG:225) by Materials Project

    SciTech Connect (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

  7. Campaign 1.7 Pu Aging. Development of Time of Flight Secondary Ion Mass Spectroscopy

    SciTech Connect (OSTI)

    Venhaus, Thomas J.

    2015-09-09

    The first application of Time-of-Flight Secondary Ion Mass Spectroscopy (ToF-SIMS) to an aged plutonium surface has resulted in a rich set of surface chemistry data, as well as some unexpected results. FY15 was highlighted by not only the first mapping of hydrogen-containing features within the metal, but also a prove-in series of experiments using the system’s Sieverts Reaction Cell. These experiments involved successfully heating the sample to ~450 oC for nearly 24 hours while the sample was dosed several times with hydrogen, followed by an in situ ToF-SIMS analysis. During this year, the data allowed for better and more consistent identification of the myriad peaks that result from the SIMS sputter process. In collaboration with the AWE (U.K), the system was also fully aligned for sputter depth profiling for future experiments.

  8. Microsoft PowerPoint - Draft HAB Pu presentation CJK 040412.pptx [Read-Only]

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

    6

  9. Evaluation of Los Alamos National Laboratory (LANL) PU238 Waste Management Practices

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  10. Hidden disorder in the α'→δ transformation of Pu-1.9 at....

    Office of Scientific and Technical Information (OSTI)

    Authors: Jeffries, J. R. ; Manley, M. E. ; Wall, M. A. ; Blobaum, K. J. M. ; Schwartz, A. J. Publication Date: 2012-06-06 OSTI Identifier: 1103511 Type: Publisher's Accepted ...

  11. Summary of Pu?u ?O?o - Kupaianaha Eruption, Kilauea Volcano...

    Open Energy Info (EERE)

    Survey, 2012 DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Summary of Puu Oo - Kupaianaha Eruption, Kilauea Volcano, Hawaii...

  12. Microscopic Calculation of 240Pu Scission with a Finite-Range...

    Office of Scientific and Technical Information (OSTI)

    calculation for sup 226Th is obtained and compared to results in the literature. ... Country of Publication: United States Language: English Subject: 73 NUCLEAR PHYSICS AND ...

  13. Summary of EXAFS results on Cd-doped PuRhIn5 (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    Technical Information Service, Springfield, VA at www.ntis.gov. Authors: Booth, C H ; Bauer, E D ; Tobin, J G Publication Date: 2014-06-12 OSTI Identifier: 1149554 Report...

  14. Materials Data on Pu3Al (SG:123) by Materials Project

    SciTech Connect (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

  15. Materials Data on Pu5Os3 (SG:140) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-03-19

    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

  16. CAPABILITY TO RECOVER PLUTONIUM-238 IN H-CANYON/HB-LINE

    SciTech Connect (OSTI)

    Fuller, K.; Smith, Robert H. Jr.; Goergen, Charles R.

    2013-01-09

    Plutonium-238 is used in Radioisotope Thermoelectric Generators (RTGs) to generate electrical power and in Radioisotope Heater Units (RHUs) to produce heat for electronics and environmental control for deep space missions. The domestic supply of Pu-238 consists of scrap material from previous mission production or material purchased from Russia. Currently, the United States has no significant production scale operational capability to produce and separate new Pu-238 from irradiated neptunium-237 targets. The Department of Energy - Nuclear Energy is currently evaluating and developing plans to reconstitute the United States capability to produce Pu-238 from irradiated Np-237 targets. The Savannah River Site had previously produced and/or processed all the Pu-238 utilized in Radioisotope Thermoelectric Generators (RTGs) for deep space missions up to and including the majority of the plutonium for the Cassini Mission. The previous full production cycle capabilities included: Np-237 target fabrication, target irradiation, target dissolution and Np-237 and Pu-238 separation and purification, conversion of Np-237 and Pu-238 to oxide, scrap recovery, and Pu-238 encapsulation. The capability and equipment still exist and could be revitalized or put back into service to recover and purify Pu-238/Np-237 or broken General Purpose Heat Source (GPHS) pellets utilizing existing process equipment in HB-Line Scrap Recovery, and H-anyon Frame Waste Recovery processes. The conversion of Np-237 and Pu-238 to oxide can be performed in the existing HB-Line Phase-2 and Phase-3 Processes. Dissolution of irradiated Np-237 target material, and separation and purification of Np-237 and Pu-238 product streams would be possible at production rates of ~ 2 kg/month of Pu-238 if the existing H-Canyon Frames Process spare equipment were re-installed. Previously, the primary H-Canyon Frames equipment was removed to be replaced: however, the replacement project was stopped. The spare equipment is

  17. Capability to Recover Plutonium-238 in H-Canyon/HB-Line - 13248

    SciTech Connect (OSTI)

    Fuller, Kenneth S. Jr.; Smith, Robert H. Jr.; Goergen, Charles R.

    2013-07-01

    Plutonium-238 is used in Radioisotope Thermoelectric Generators (RTGs) to generate electrical power and in Radioisotope Heater Units (RHUs) to produce heat for electronics and environmental control for deep space missions. The domestic supply of Pu-238 consists of scrap material from previous mission production or material purchased from Russia. Currently, the United States has no significant production scale operational capability to produce and separate new Pu-238 from irradiated neptunium-237 targets. The Department of Energy - Nuclear Energy is currently evaluating and developing plans to reconstitute the United States capability to produce Pu-238 from irradiated Np-237 targets. The Savannah River Site had previously produced and/or processed all the Pu-238 utilized in Radioisotope Thermoelectric Generators (RTGs) for deep space missions up to and including the majority of the plutonium for the Cassini Mission. The previous full production cycle capabilities included: Np- 237 target fabrication, target irradiation, target dissolution and Np-237 and Pu-238 separation and purification, conversion of Np-237 and Pu-238 to oxide, scrap recovery, and Pu-238 encapsulation. The capability and equipment still exist and could be revitalized or put back into service to recover and purify Pu-238/Np-237 or broken General Purpose Heat Source (GPHS) pellets utilizing existing process equipment in HB-Line Scrap Recovery, and H-Canyon Frame Waste Recovery processes. The conversion of Np-237 and Pu-238 to oxide can be performed in the existing HB-Line Phase-2 and Phase- 3 Processes. Dissolution of irradiated Np-237 target material, and separation and purification of Np-237 and Pu-238 product streams would be possible at production rates of ∼2 kg/month of Pu-238 if the existing H-Canyon Frames Process spare equipment were re-installed. Previously, the primary H-Canyon Frames equipment was removed to be replaced: however, the replacement project was stopped. The spare equipment

  18. Measured solubilities and speciations of neptunium, plutonium, and americium in a typical groundwater (J-13) from the Yucca Mountain region; Milestone report 3010-WBS 1.2.3.4.1.3.1

    SciTech Connect (OSTI)

    Nitsche, H.; Gatti, R.C.; Standifer, E.M.

    1993-07-01

    Solubility and speciation data are important in understanding aqueous radionuclide transport through the geosphere. They define the source term for transport retardation processes such as sorption and colloid formation. Solubility and speciation data are useful in verifying the validity of geochemical codes that are part of predictive transport models. Results are presented from solubility and speciation experiments of {sup 237}NpO{sub 2}{sup +}, {sup 239}Pu{sup 4+}, {sup 241}Am{sup 3+}/Nd{sup 3+}, and {sup 243}Am{sup 3+} in J-13 groundwater (from the Yucca Mountain region, Nevada, which is being investigated as a potential high-level nuclear waste disposal site) at three different temperatures (25{degree}, 60{degree}, and 90{degree}C) and pH values (5.9, 7.0, and 8.5). The solubility-controlling steady-state solids were identified and the speciation and/or oxidation states present in the supernatant solutions were determined. The neptunium solubility decreased with increasing temperature and pH. Plutonium concentrations decreased with increasing temperature and showed no trend with pH. The americium solutions showed no clear solubility trend with increasing temperature and increasing pH.

  19. COMPLEX FLUORIDES OF PLUTONIUM AND AN ALKALI METAL

    DOE Patents [OSTI]

    Seaborg, G.T.

    1960-08-01

    A method is given for precipitating alkali metal plutonium fluorides. such as KPuF/sub 5/, KPu/sub 2/F/sub 9/, NaPuF/sub 5/, and RbPuF/sub 5/, from an aqueous plutonium(IV) solution by adding hydrogen fluoride and alkali-metal- fluoride.

  20. Flight Path Target 2

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

    - Scientific Applications Target 2 provides experimenters direct access to the 800 MeV proton beam as well as several flight paths. Target 2 is located in MPF-7 at LANSCE.. Lead ...

  1. Beamline 7.2

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

    radiation Spatial resolution Port 1: <25 m transverse Port 2: 1 m position; <1 rad angle (x-ray BPM) Detectors Port 1: Analog CCD camera Port 2: Secondary emission copper...

  2. RACEE Phase 2 Documents

    Office of Energy Efficiency and Renewable Energy (EERE)

    In Phase 2 of the Remote Alaskan Communities Energy Efficiency (RACEE) Competition, the U.S. Department of Energy provided targeted technical assistance to up to 20 selected Community Efficiency Champions. The documents below are resources for Phase 2.

  3. Word Pro - S2

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

    2. Energy Consumption by Sector Figure 2.1 Energy Consumption by Sector (Quadrillion Btu) Total Consumption by End-Use Sector, 1949-2015 Total Consumption by End-Use Sector, ...

  4. ARM - Datastreams - dlcal2

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

    from you Send us a note below or call us at 1-888-ARM-DATA. Send Datastream : DLCAL2 Doppler Lidar - calibration scan 2 Active Dates 2010.10.21 - 2016.01.06 Measurement...

  5. Word Pro - S2

    Gasoline and Diesel Fuel Update (EIA)

    Coal Petroleum 0.0 0.2 0.4 0.6 0.8 1.0 Natural Gas Nuclear Electric Power Renewable Energy Web Page: http:www.eia.govtotalenergydatamonthlyconsumption. Source: Table 2.6.

  6. FY 2006 Volume 2

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

    2 February 2005 DOE/ME-0047 Volume 2 Other Defense Activities Security & Performance Assurance Environment, Safety & Health Legacy Management Nuclear Energy Defense Related Administrative Support Office of Hearings & Appeals Safeguards & Security Crosscut Department of Energy FY 2006 Congressional Budget Request Office of Management, Budget and Evaluation/CFO Volume 2 February 2005 DOE/ME-0047 Volume 2 Other Defense Activities Security & Performance Assurance Environment,

  7. FY 2008 Volume 2

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

    2 DOE/CF-015 Volume 2 Other Defense Activities Health, Safety and Security Legacy Management Nuclear Energy Defense-Related Administrative Support Hearings and Appeals Safeguards and Security Crosscut Department of Energy FY 2008 Congressional Budget Request February 2007 Office of Chief Financial Officer Volume 2 DOE/CF-015 Volume 2 Other Defense Activities Health, Safety and Security Legacy Management Nuclear Energy Defense-Related Administrative Support Hearings and Appeals Safeguards and

  8. FY 2009 Volume 2

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

    2 DOE/CF-025 Volume 2 Other Defense Activities Departmental Administration Inspector General Loan Guarantee Program Working Capital Fund Energy Information Administration Safeguards and Security Crosscut February 2008 Office of Chief Financial Officer Department of Energy FY 2009 Congressional Budget Request Volume 2 DOE/CF-025 Volume 2 Other Defense Activities Departmental Administration Inspector General Loan Guarantee Program Working Capital Fund Energy Information Administration Safeguards

  9. FY 2011 Volume 2

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

    2 DOE/CF-0048 Volume 2 Other Defense Activities Departmental Administration Inspector General Advanced Technology Vehicles Manufacturing Loan Program Title 17 Innovative Technology Loan Guarantee Program Working Capital Fund Energy Information Administration Safeguards and Security Crosscut Domestic Utility Fee Pensions Department of Energy FY 2011 Congressional Budget Request February 2010 Office of Chief Financial Officer Volume 2 DOE/CF-0048 Volume 2 Other Defense Activities Departmental

  10. FY 2013 Volume 2

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

    2 Volume 2 f Department of Energy FY 2013 Congressional B d R Budget Request Other Defense Activities Departmental Administration Inspector General Working Capital F nd Working Capital Fund Safeguards and Security Crosscut Pensions February 2012 Office of Chief Financial Officer Volume 2 DOE/CF-0072 Volume 2 f Department of Energy FY 2013 Congressional B d R Budget Request Other Defense Activities Departmental Administration Inspector General Working Capital F nd Working Capital Fund Safeguards

  11. Attachment F2

    Office of Environmental Management (EM)

    F2 TRAINING COURSE AND QUALIFICATION CARD OUTLINES Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 (This page intentionally blank) Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 PERMIT ATTACHMENT F2 Page F2-i ATTACHMENT F2 TRAINING COURSE AND QUALIFICATION CARD OUTLINES TABLE OF CONTENTS Course Outlines .......................................................................................................................... 1 GET-19X/GET-20X/GET-21X - General

  12. Attachment G2

    Office of Environmental Management (EM)

    G2 WASTE ISOLATION PILOT PLANT SHAFT SEALING SYSTEM COMPLIANCE SUBMITTAL DESIGN REPORT Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 (This page intentionally blank) Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 PERMIT ATTACHMENT G2 Page G2-i ATTACHMENT G2 WASTE ISOLATION PILOT PLANT SHAFT SEALING SYSTEM COMPLIANCE SUBMITTAL DESIGN REPORT ADAPTED FROM: SAND96-1326/1 DISTRIBUTION UNLIMITED RELEASE CATEGORY UC-721 PRINTED AUGUST 1996 WASTE ISOLATION PILOT PLANT

  13. Microsoft Word - ADM 2

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

    6 ADM 2 Rev 2 September 2010 ADMINISTRATIVE RECORDS SCHEDULE 2: PAYROLL AND PAY ADMINISTRATION RECORDS September 2010 Revision 2 Payrolling and pay administration records pertain to the disbursements employees receive in return for their personal services. This schedule covers commonly used pay records. Title 6, "Pay, Leave, and Allowances" in the GAO Policy and Procedures Manual provides guidance for preparing and maintaining Departmental pay accounts. Payroll systems use a leave

  14. Office of Nuclear Energy Teachers' Edition Doe...

    Energy Savers [EERE]

    ... 2 Water Graphite Fast Neutron Breeder Reactor (FBR) Japan, France, Russia 2 1 PuO2 and UO 2 Liquid sodium None needed ... Source: IAEA June 2012, Nuclear Power Reactors in the World ...

  15. ARM - Instrument - sp2

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

    govInstrumentssp2 Documentation ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Instrument : Single Particle Soot Photometer (SP2) Instrument Categories Aerosols The SP2 measures the soot (black carbon) mass of individual aerosol particles by laser-induced incandescence down to concentrations as low as 10 ng/m^3. The SP2 is part of the Aerosol Observing System (AOS). Output Datastreams sp2 : Single Particle Soot

  16. WIEN2k

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

    WIEN2k WIEN2k Description WIEN2k performs electronic structure calculations of solids using density functional theory (DFT). It is based on the full-potential (linearized) augmented plane-wave ((L)APW) + local orbitals (lo) method, one of the most accurate schemes for band structure calculations. Wien2k is available on Cori, and Edison. One special note for this application is that Wien2k runs under the Cray Cluster Compatibility Mode ONLY. It is important for users to follow the instructions

  17. Flight Path Target 2

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

    2 Target 2 provides experimenters direct access to the 800 MeV proton beam as well as several flight paths. Target 2 is located in MPF-7 at LANSCE.. Target 2 Target 2 is housed in the Blue Room in MPF-7 at LANSCE and provides experimenters direct access to the LANSCE proton beam. The Blue Room is a domed room with a diameter of 40 feet. The main floor of the Blue Room is constructed primarily of aluminum and elevated 20 feet above the basement floor to minimize neutron wall return for

  18. CP2K

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

    CP2K CP2K Description CP2K performs atomistic and molecular simulations of solid state, liquid, molecular and biological systems. It provides a general framework for different methods such as e.g. density functional theory (DFT) using a mixed Gaussian and plane waves approach (GPW), and classical pair and many-body potentials. How to Access CP2K This program is currently available at NERSC on Edison and Cori. NERSC uses modules to manage access to software. To use the default version of CP2K,

  19. Comparison of Spectroscopic Data with Cluster Calculations of Plutonium, Plutonium Dioxide and Uranium Dioxide

    SciTech Connect (OSTI)

    Tobin, J G; Yu, S W; Chung, B W; Ryzhkov, M V; Mirmelstein, A

    2012-05-15

    Using spectroscopic data produced in the experimental investigations of bulk systems, including X-Ray Absorption Spectroscopy (XAS), Photoelectron Spectroscopy (PES) and Bremstrahlung Isochromat Spectroscopy (BIS), the theoretical results within for UO{sub 2}{sup 6}, PuO{sub 2}{sup 6} and Pu{sup 7} clusters have been evaluated. The calculations of the electronic structure of the clusters have been performed within the framework of the Relativistic Discrete-Variational Method (RDV). The comparisons between the LLNL experimental data and the Russian calculations are quite favorable. The cluster calculations may represent a new and useful avenue to address unresolved questions within the field of actinide electron structure, particularly that of Pu. Observation of the changes in the Pu electronic structure as a function of size suggests interesting implications for bulk Pu electronic structure.

  20. H2FIRST Reference Station Design Task: Project Deliverable 2...

    Energy Savers [EERE]

    Reference Station Design Task: Project Deliverable 2-2 H2FIRST Reference Station Design Task: Project Deliverable 2-2 This H2FIRST project report, published in April 2015, presents ...

  1. Cybersecurity Capability Maturity Model (C2M2) | Department of...

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

    The C2M2 model, which is designed to be used by any organization to enhance its own ... support adoption of the C2M2. If your organization has questions about the C2M2 model or ...

  2. Mass balance and separation factor of actinides through series process test on pyro-process

    SciTech Connect (OSTI)

    Kitawaki, Shinichi; Fukushima, Mineo; Yahagi, Noboru; Kurata, Masaki

    2007-07-01

    An electrolysis test in a sequential condition was performed using U-Pu alloy and liquid Cd as an anode and a cathode material, respectively, in which the anode and cathode was changed three times. Mass balance of U and Pu after three-time electrolysis was determined from both the chemical analysis of salt and anode residue, and the weight increase in the cathode. Approximately 95% of U and 100% of Pu was detected even after three times electrolysis. The loss of U is more significant than that of Pu. The mass balance was also evaluated for the intermediate steps of the sequence. More than 90% of U and Pu with respect to the initial amount were constantly caught up with in each step. The separation factor of U/Pu in three cathodes were varied 1.62-2.06. The chemical form of the anode residue was UO, PuOCl and PuO{sub 2}, which can be converted to the chloride by a reaction with ZrCl{sub 4}. (authors)

  3. The solubility of hydrogen in plutonium in the temperature range 475 to 825 degrees centigrade

    SciTech Connect (OSTI)

    Allen, T.H.

    1991-01-01

    The solubility of hydrogen (H) in plutonium metal (Pu) was measured in the temperature range of 475 to 825{degree}C for unalloyed Pu (UA) and in the temperature range of 475 to 625{degree}C for Pu containing two-weight-percent gallium (TWP). For TWP metal, in the temperature range 475 to 600{degree}C, the saturated solution has a maximum hydrogen to plutonium ration (H/Pu) of 0.00998 and the standard enthalpy of formation ({Delta}H{degree}{sub f(s)}) is (-0.128 {plus minus} 0.0123) kcal/mol. The phase boundary of the solid solution in equilibrium with plutonium dihydride (PuH{sub 2}) is temperature independent. In the temperature range 475 to 625{degree}C, UA metal has a maximum solubility at H/Pu = 0.011. The phase boundary between the solid solution region and the metal+PuH{sub 2} two-phase region is temperature dependent. The solubility of hydrogen in UA metal was also measured in the temperature range 650 to 825{degree}C with {Delta}H{degree}{sub f(s)} = (-0.104 {plus minus} 0.0143) kcal/mol and {Delta}S{degree}{sub f(s)} = 0. The phase boundary is temperature dependent and the maximum hydrogen solubility has H/Pu = 0.0674 at 825{degree}C. 52 refs., 28 figs., 9 tabs.

  4. Thrust 2 - JCAP

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

    2: Photoelectrocatalysis Research Why Solar Fuels Goals & Objectives Thrust 1 Thrust 2 Thrust 3 Thrust 4 Publications Research Highlights Videos Innovations User Facilities Expert Team Benchmarking Database Device Simulation Tool XPS Spectral Database Research Introduction Why Solar Fuels? Goals & Objectives Thrusts Thrust 1 Thrust 2 Thrust 3 Thrust 4 Library Publications Research Highlights Videos Resources User Facilities Expert Team Benchmarking Database Device Simulation Tool XPS

  5. BEAMLINE 11-2

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

    2 CURRENT STATUS: Open SUPPORTED TECHNIQUES: X-ray absorption spectroscopy Grazing incidence x-ray absorption spectroscopy MAIN SCIENTIFIC DISCIPLINES: Molecular Environmental and Interface Science (see also: BL11-2 User Support) % TIME GENERAL USE: 100% SCHEDULING: Proposal Submittal and Scheduling Procedures Current SPEAR and Beam Line Schedules SOURCE: 26-pole, 2.0-Tesla Wiggler ID End Station BEAM LINE SPECIFICATIONS: energy range resolution DE/E spot size flux angular acceptance focused

  6. Word Pro - S2

    Gasoline and Diesel Fuel Update (EIA)

    Natural Gas Renewable Energy 10.944 11.193 11.504 2014 2015 2016 0 2 4 6 8 10 12 14 J F M A M J J A S O N D 0.0 0.5 1.0 1.5 2.0 2.5 3.0 2014 2015 2016 Web Page: http:www.eia.gov...

  7. ARM - Datastreams - aosso2

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

    ... ( time ) Time offset from basetime timeoffset ( time ) Valve position for mass flow controller 1 unitless valvepositionMFC1 ( time ) Valve position mass flow controller 2 ...

  8. ARM - AMF2 Operations

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

    and Contacts Management and Operations Operations Overview ARM Links BCR | ECR ECO, EWO Extraview PIF, CAR, DQR & DQPR Operations Status System i.arm.gov AMF2 Deployment...

  9. Beamline 7.2

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

    Port 2: None (available for temporary experiments) Both ports are inside the ALS shielding. Characteristics Port 1: Pinhole-based x-ray system for transverse measurements Port...

  10. Beamline 7.2

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

    2 Print Diagnostic beamline GENERAL BEAMLINE INFORMATION Operational Yes, but not open to users Source characteristics Bend magnet Energy range Port 1: 17 keV transmission though...

  11. Attachment A2

    Office of Environmental Management (EM)

    A2 GEOLOGIC REPOSITORY Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 (This page intentionally blank) Waste Isolation Pilot Plant Hazardous Waste Permit October ...

  12. Attachment F2

    Office of Environmental Management (EM)

    F2 TRAINING COURSE AND QUALIFICATION CARD OUTLINES Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 (This page intentionally blank) Waste Isolation Pilot Plant ...

  13. Attachment G2

    Office of Environmental Management (EM)

    G2 WASTE ISOLATION PILOT PLANT SHAFT SEALING SYSTEM COMPLIANCE SUBMITTAL DESIGN REPORT Waste Isolation Pilot Plant Hazardous Waste Permit October 2013 (This page intentionally ...

  14. ARM - Datastreams - aerich2

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

    Datastreamsaerich2 Documentation Data Quality Plots Citation DOI: 10.54391025144 What is this? Generate Citation ARM Data Discovery Browse Data Comments? We would love to hear...

  15. ARM - Datastreams - assistch2

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

    Datastreamsassistch2 Documentation Data Quality Plots Citation DOI: 10.54391095590 What is this? Generate Citation ARM Data Discovery Browse Data Comments? We would love to...

  16. A2e

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

    Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & ...

  17. BEAMLINE 10-2

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

    0-2 CURRENT STATUS: Open SUPPORTED TECHNIQUES: 10-2a: X-ray absorption spectroscopy; XAS imaging 10-2b: X-ray scattering MAIN SCIENTIFIC DISCIPLINES: Biology / Materials / Environmental % TIME GENERAL USE: 100% SCHEDULING: Proposal Submittal and Scheduling Procedures Current SPEAR and Beam Line Schedules SOURCE: 30-pole, 1.45-Tesla Wiggler ID End Station BEAM LINE SPECIFICATIONS: energy range resolution DE/E spot size flux angular acceptance focused 4500 - 30000 eV 0.2 x .43 mm 1.5 mrad

  18. Word Pro - S2

    Gasoline and Diesel Fuel Update (EIA)

    Residential Commercial Industrial Transportation 0 1 2 3 4 Primary Consumption Total Consumption Electric Power Web Page: http:www.eia.govtotalenergydatamonthlyconsumption. ...

  19. CESP Tool 2.2: Stakeholder Invite | Department of Energy

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

    2: Stakeholder Invite CESP Tool 2.2: Stakeholder Invite Tool 2.2: Stakeholder Invite from Step 2: Identify and Engage Stakeholders of the Guide to Community Energy Strategic Planning. CESP Tool 2.2: Stakeholder Invite (48.46 KB) More Documents & Publications CESP Tool 1.1: Leadership Team Invite Guide to Community Energy Strategic Planning: Step 2

  20. ARM - Instrument - smps-2

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

    govInstrumentssmps-2 Documentation Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Instrument : Scanning Mobile Particle Sizer (SMPS-2) The Scanning Mobile Particle Sizer combines a differential mobility analyser (DMA) with a condensation particle counter (CPC) to achieve greater sensitivity for small particles.

  1. Microsoft Word - Document2

    Open Energy Info (EERE)

    min, average, and max average CO 2 emissions by month for AZNM subregion (lbs CO 2 MWh load) 800 1,100 1,400 1,700 January 800 1,100 1,400 1,700 February 800 1,100 1,400 1,700...

  2. FRAPCON-2 Developmental Assessment

    SciTech Connect (OSTI)

    Berna, G. A.; Lanning, D. D.; Rausch, W. N.

    1981-07-01

    FRAPCON-2 calculations using all mechanical and gas release options are compared with well-characterized experimental data and with calculations of generic fuel rod response by FRAPCON-1. These comparisons indicate that FRAPCON-2 is capable of analyzing the fuel rod response for the wide range of cases for which the code was designed and compares well with experimental data.

  3. FY 2005 Volume 2

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

    3 Volume 2 February 2004 Volume 2 Office of Management, Budget and Evaluation/CFO Other Defense Activities Other Defense Activities Energy Security and Assurance Energy Security and Assurance Security Security Independent Oversight & Performance Assurance Independent Oversight & Performance Assurance Civilian Radioactive Waste Management Civilian Radioactive Waste Management Environment, Safety & Health Environment, Safety & Health Legacy Management Legacy Management Nuclear

  4. TOUGHREACT V2

    Energy Science and Technology Software Center (OSTI)

    2011-12-01

    TOUGHREACT is a numerical simulation program for chemically reactive non-isothermal flows of multiphase fluids in porous and fractured media. The program is written in Fortran 77 and was developed by introducing reactive chemistry into the multiphase flow code TOUGH2 V2. Interactions between mineral assemblages and fluids can occur under local equilibrium or kinetic rates. The gas phase can be chemically active. Precipitation and dissolution reactions can change formation porosity and permeability, and can also modifymore » the unsaturated flow properties of the rock. The code is distributed with a comprehensive user?s guide that includes sample problems addressing geothermal reservoirs and hydrothermal systems, nuclear waste isolation, groundwater quality, sequestration of carbon dioxide in saline aquifers, and supergene copper enrichment. The TOUGHREACT V2 package supports the following fluid property modules packaged into TOUGH2 V2.0 (CR-1574): EOS1, EOS2, EOS3, EOS4, EOS7, EOS9, and ECO2N. New features in V2 include multi-site surface complexation and ion exchange, aqueous kinetics, restructuring for faster execution, and more flexible input formats.« less

  5. EnergyPlus 1.2.2

    Energy Science and Technology Software Center (OSTI)

    2005-05-01

    EnergyPlus (E+) is a new whole-building energy analysis program that combines the best capabilities and features from BLAST and DOE-2 along with new capabilities. E+ modular implementation facilitates extending the program and adding links to other programs. The fluid loops and HVAC components support a "manager-interface" simulation protocol that allows for the independent simulation of subsystems, each possibly using a customized solution procedure. Thus, the E+ program structure allows the solution to a particular subsystemmore » to be computed without affecting the solution schemes used for the other subsystems. This fundamental requirement enables the integration of external models in the El+ building systems simulation.« less

  6. THE ARCADE 2 INSTRUMENT

    SciTech Connect (OSTI)

    Singal, J.; Fixsen, D. J.; Kogut, A.; Mirel, P.; Wollack, E.; Levin, S.; Seiffert, M.; Limon, M.; Lubin, P.; Villela, T.; Wuensche, C. A.

    2011-04-01

    The second generation Absolute Radiometer for Cosmology, Astrophysics, and Diffuse Emission (ARCADE 2) instrument is a balloon-borne experiment to measure the radiometric temperature of the cosmic microwave background and Galactic and extragalactic emission at six frequencies from 3 to 90 GHz. ARCADE 2 utilizes a double-nulled design where emission from the sky is compared to that from an external cryogenic full-aperture blackbody calibrator by cryogenic switching radiometers containing internal blackbody reference loads. In order to further minimize sources of systematic error, ARCADE 2 features a cold fully open aperture with all radiometrically active components maintained at near 2.7 K without windows or other warm objects, achieved through a novel thermal design. We discuss the design and performance of the ARCADE 2 instrument in its 2005 and 2006 flights.

  7. OBES "One Pager"

    SciTech Connect (OSTI)

    Tobin, J G

    2008-11-07

    We are developing and utilizing photon dichroic and spin resolved techniques to investigate electron correlation in complex systems. These materials include potential spintronic device sources such as Fe/GaAs and f electronic materials such as non-magnetic {delta}-Pu. We are pursuing Double Polarization Photoelectron Dichroism measurements of the Fano Effect, using spin resolving detection in photoelectron spectroscopy, to test the nature of electron correlation in Pu. (See Pubs 2, 4 & 5.) If successful, we will solve the riddle of Pu electronic structure that has remained unresolved for the last 60 years. We are also developing a Bremstrahlung Isochromat Spectroscopy (BIS) capability to permit the direct measurement of the unoccupied electronic structure of Pu, which is another missing piece in the puzzle of Pu electronic structure.

  8. Beamline 2.1

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

    2.1 Beamline 2.1 Print Tuesday, 20 October 2009 08:16 National Center for X-Ray Tomography (NCXT) Scientific discipline: Biology GENERAL BEAMLINE INFORMATION Operational Yes Source characteristics Bend magnet Energy range 400 - 1300 eV Monochromator Zone-plate linear Measured flux (1.9 GeV, 400 mA) Images with 2048 x 2048 pixels Resolving power (E/ĢE) 500-700 Endstations X-ray microscope (XM-2) Characteristics Full-field soft x-ray transmission microscope Spatial resolution Zone-plate

  9. b2.xls

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

    Total Workers in All Buildings (thousand) Median Square Feet per Building (thousand) Median Square Feet per Worker Median Hours per Week Median Age of Buildings (years) All Buildings* .................................. 4,645 64,783 72,807 4.6 1,000 50 30.5 Building Floorspace (Square Feet) 1,001 to 5,000 ................................... 2,552 6,789 9,936 2.4 750 48 30.5 5,001 to 10,000 ................................. 889 6,585 7,512 7.2 1,300 50 30.5 10,001 to 25,000

  10. BEAMLINE 2-3

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

    2-3 CURRENT STATUS: Open SUPPORTED TECHNIQUES: X-ray absorption spectroscopy imaging MAIN SCIENTIFIC DISCIPLINES: Biology / Materials / Chemistry / Environmental % TIME GENERAL USE: 100% SCHEDULING: Proposal Submittal and Scheduling Procedures Current SPEAR and Beam Line Schedules SOURCE: 1.3 Tesla Bend Magnet BEAM LINE SPECIFICATIONS: energy range resolution DE/E spot size flux angular acceptance unfocused 4500-24000 eV ~5 x 10-4 2 x 2 microns ~1010 0.75 mrad OPTICS: Kirkpatrick-Baez system

  11. Beamline 7.2

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

    2 Print Diagnostic beamline GENERAL BEAMLINE INFORMATION Operational Yes, but not open to users Source characteristics Bend magnet Energy range Port 1: ~17 keV transmission though Mo filters Port 2: IR-visible from large-angle synchrotron radiation; UV-x-ray for beam position monitor (BPM) Endstations Port 1: Hard x-ray to visible converter (phosphor) Port 2: None (available for temporary experiments) Both ports are inside the ALS shielding. Characteristics Port 1: Pinhole-based x-ray system for

  12. Beamline 7.2

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

    2 Print Diagnostic beamline GENERAL BEAMLINE INFORMATION Operational Yes, but not open to users Source characteristics Bend magnet Energy range Port 1: ~17 keV transmission though Mo filters Port 2: IR-visible from large-angle synchrotron radiation; UV-x-ray for beam position monitor (BPM) Endstations Port 1: Hard x-ray to visible converter (phosphor) Port 2: None (available for temporary experiments) Both ports are inside the ALS shielding. Characteristics Port 1: Pinhole-based x-ray system for

  13. Critical Decision 2 (CD-2) Approval Template | Department of...

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

    Critical Decision 2 (CD-2) Approval Template Critical Decision 2 (CD-2) Approval Template File ExampleCD-2Template02-14-12.docx More Documents & Publications Example BCP...

  14. table3.2

    Gasoline and Diesel Fuel Update (EIA)

    ... NAICS Code(a) Subsector and Industry Total Net Electricity(b... RSE Row Factors Table 3.2 Fuel Consumption, 2002; Level: ... of Energy Markets and End Use, Energy Consumption ...

  15. Word Pro - S2

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

    primary consumption by the electric power sector (see Table 2.6) and the total energy content of electricity retail ... from power plants to end-use consum- ers (also called ...

  16. Word Pro - S2

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

    29 Table 2.1 Energy Consumption by Sector (Trillion Btu) End-Use Sectors Electric Power Sector c,d ... (CHP) and commercial electricity-only plants. b Industrial ...

  17. 2-ID-E

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

    General Users. For example, in collaboration with G. Woloschak et al, we have looked at TiO2-DNA nanocomposites in mammalian cells 1; B. Twining et al investigate trace elements...

  18. Beamline 7.2

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

    Bend magnet Energy range Port 1: 17 keV transmission though Mo filters Port 2: IR-visible from large-angle synchrotron radiation; UV-x-ray for beam position monitor (BPM)...

  19. battery2.indd

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

    6-1982J Solid-State Environmentally Safe Battery for Replacing Lithium Batteries 1. ... Signature 2. Joint Entry with High Power Battery Systems Company 5 Silkin Street, Apt. 40 ...

  20. L .~$;2-3

    Office of Legacy Management (LM)

    rucan*- -atbntshakiedoun atgmonItsmda)ai rrapkot0p;lurttf3ulna,'pllxr uutub0rf;,l% Tkmp3lultwillproaboth8nirlla2feedgredo umi tYmrgrudediaalaltra*orphatre llsd -...