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Demonstration Fuel Element Shipping Cask From Laminated Uranium Metal. Part 2 Fabrication and Costs.

Description: This report describes the work performed by the Paducah Gaseous Diffusion Plant operated by Union Carbide Corporation, Nuclear Division, for the U. S. Atomic Energy Commission relative to the fabrication of a demonstration fuel element shipping cask utilizing laminated depleted uranium as shielding material. A detailed presentation is given of the fabrication, machining, cleaning, and heat treating operations followed in producing the cask. Machining characteristics of uranium are described and… more
Date: January 1, 1969
Creator: Smith, V. A. & Loveland, C. W.
Partner: UNT Libraries Government Documents Department
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Investigation of breached depleted UF sub 6 cylinders

Description: In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that oc… more
Date: January 1, 1991
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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Influence of safeguards and fire protection on criticality safety

Description: There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described.
Date: January 1, 1980
Creator: Six, D E
Partner: UNT Libraries Government Documents Department
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Preparation of UO/sub 2/ fragments for fuel-debris experiments

Description: A unique process was developed for preparing multi-kilogram quantities of > 90% dense fragments of enriched and depleted UO/sub 2/ sized 20 mm to 0.038 mm for fuel debris experiments. Precipitates of UO/sub 4/ . xH/sub 2/O were treated to obtain UO/sub 2/ powders that would yield large cohesive green pieces when isostatically pressed to 206 MPa. The pressed pieces were crushed into fragments that were about 30% oversized, and heated to 1800/sup 0/C for 24 h in H/sub 2/. Oversizing compensates f… more
Date: January 1, 1982
Creator: Tinkle, M.C.; Kircher, J.A.; Zinn, R.M. & Eash, D.T.
Partner: UNT Libraries Government Documents Department
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Effects of drop testing on scale model shipping containers shielded with depleted uranium

Description: Three scale model shipping containers shielded with depleted uranium were dropped onto an essentially unyielding surface from various heights to determine their margins to failure. This report presents the results of a thorough posttest examination of the models to check for basic structural integrity, shielding integrity, and deformations. Because of unexpected behavior exhibited by the depleted uranium shielding, several tests were performed to further characterize its mechanical properties. … more
Date: February 1, 1980
Creator: Butler, T. A.
Partner: UNT Libraries Government Documents Department
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Environmental survey of the B-3 and Ford's Farm ranges.

Description: The Army has been firing depleted-uranium (DU) projectiles into targets on the Aberdeen Proving Ground, Maryland. An environmental survey was conducted of two areas known as the B-3 range and the Ford's Farm range to determine the location of DU in their environments. The survey included ground survey measurements and some environmental sampling. Several special studies were also conducted, including analyses of the isotopic composition of uranium in a limited number of samples and a dissolutio… more
Date: August 1, 1983
Creator: Stoetzel, G. A.; Waite, D. A. & Gilchrist, R. L.
Partner: UNT Libraries Government Documents Department
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Safety analysis of the existing 851 Firing Facility

Description: A safety analysis was performed to determine if normal operations and/or potential accidents at the 851 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but two of the hazards were either low or of the type or magnitud… more
Date: June 5, 1986
Creator: Odell, B.N.
Partner: UNT Libraries Government Documents Department
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An ion beam simulation of the swelling of U/sub 3/Si

Description: Uranium intermetallics are under consideration as possible low-enrichment reactor fuels. These materials divide into two classes with regard to dimensional stability during their service lifetime: those which suffer extreme dimensional growth and those which do not. It has been suggested that the rapid-swelling materials are those that become glassy under irradiation while the low-swelling materials are those that remain crystalline. The structural and dimensional stabilities of U/sub 3/Si (dep… more
Date: December 1, 1987
Creator: Allen, C. W.; Birtcher, R. C.; Rehn, L. E. & Hofman, G. L.
Partner: UNT Libraries Government Documents Department
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Waste systems. Progress report, January 1982-February 1983

Description: A laboratory-scale beryllium electrorefining cell has been placed in operation and metallic beryllium with a purity greater than 99.95% has been produced. Methods of uranium chip disposal have been evaluated by performing bench- and pilot-scale testing and by surveying present chip disposal methods. A design criteria has been completed for a new production uranium chip disposal facility. Two types of cementation immobilization processes are being developed to treat several Rocky Flats wastes wh… more
Date: October 24, 1983
Creator: Hickle, G.L.
Partner: UNT Libraries Government Documents Department
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Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Description: This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP).
Date: September 30, 2008
Creator: Greenspan, Ehud
Partner: UNT Libraries Government Documents Department
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Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

Description: This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and sign… more
Date: March 1, 2008
Creator: Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan et al.
Partner: UNT Libraries Government Documents Department
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Multiple-Coincidence Active Neutron Interrogation of Fissionable Materials

Description: Using a beam of tagged 14.1 MeV neutrons to probe for the presence of fissionable materials, we have measured n-γ-γ coincidences from depleted uranium (DU). The multiple coincidence rate is substantially above that measured from lead, tungsten, and iron. The presence of coincidences involving delayed gammas in the DU time spectra provides a signature for fissionable materials that is distinct from non-fissionable ones. In addition, the information from the tagged neutron involved in the coincid… more
Date: August 6, 2008
Creator: J.P. Hurley, R.P. Keegan, J.R. Tinsley, R. Trainham, and S.C. Wilde
Partner: UNT Libraries Government Documents Department
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Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

Description: This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that… more
Date: September 7, 2007
Creator: Larson, H L
Partner: UNT Libraries Government Documents Department
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Fission Detection Using the Associated Particle Technique

Description: A beam of tagged 14 MeV neutrons from the deuterium-tritium (DT) reaction is used to induce fission in a target composed of depleted uranium. The generator yield is 107 neutrons/second radiated into a 4π solid angle. Two 4 in.×4 in. NaI detectors are used for gamma-ray detection. The fission process is known to produce multiple gamma-rays and neutrons. Triple coincidences (α-γ-γ) are measured as a function of neutron flight time up to 90 ns after fission, where the α-particle arises from the DT… more
Date: September 18, 2008
Creator: R.P. Keegan, J.P. Hurley, J.R. Tinsley, R. Trainham, S.C. Wilde
Partner: UNT Libraries Government Documents Department
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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.

Description: 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, engineeri… more
Date: October 1, 2007
Creator: Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Division, Nuclear Engineering et al.
Partner: UNT Libraries Government Documents Department
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Prediction of External Corrosion for Steel Cylinders--2004 Report

Description: Depleted uranium hexafluoride (UF{sub 6}) is stored in over 60,000 steel cylinders at the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee, at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. The cylinders range in age from 4 to 53 years. Although when new the cylinders had wall thicknesses specified to within manufacturing tolerances, over the years corrosion has reduced their actual wall th… more
Date: July 7, 2004
Creator: Schmoyer, RLS
Partner: UNT Libraries Government Documents Department
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ToF-SIMS study of polycrystalline uranium after exposure to deuterium

Description: Time-of-flight secondary ion mass spectrometry (ToF-SIMS) is employed to examine specific features observed on a polycrystalline depleted uranium sample after exposure to high purity D{sub 2} gas. The ToF-SIMS investigation, being the first of its kind on uranium, investigates a site where the deuterated form of uranium hydride (UD{sub 3}) is clearly observed to have broken through the thin, air-formed oxide. Density functional theory calculations have been performed, which confirm the stabilit… more
Date: January 19, 2006
Creator: Morrall, P; Price, D; Nelson, A; Siekhaus, W; Nelson, E; Wu, K J et al.
Partner: UNT Libraries Government Documents Department
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Capstone Depleted Uranium Aerosols: Generation and Characterization

Description: In a study designed to provide an improved scientific basis for assessing possible health effects from inhaling depleted uranium (DU) aerosols, a series of DU penetrators was fired at an Abrams tank and a Bradley fighting vehicle. A robust sampling system was designed to collect aerosols in this difficult environment and continuously monitor the sampler flow rates. Aerosols collected were analyzed for uranium concentration and particle size distribution as a function of time. They were also ana… more
Date: October 19, 2004
Creator: Parkhurst, MaryAnn; Szrom, Fran; Guilmette, Ray; Holmes, Tom; Cheng, Yung-Sung; Kenoyer, Judson L. et al.
Partner: UNT Libraries Government Documents Department
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Prediction of External Corrosion for Steel Cylinders--2007 Report

Description: Depleted uranium hexafluoride (DUF{sub 6}) is stored in over 62,000 containment cylinders at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. Over 4,800 of the cylinders at Portsmouth were recently moved there from the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The cylinders range in age up to 56 years and come in various models, but most are 48-inch diameter 'thin-wall'(312.5 mil) and… more
Date: January 1, 2008
Creator: Schmoyer, Richard L
Partner: UNT Libraries Government Documents Department
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Shielding and Criticality Analyses of Phase I Reference Truck and Rail Cask Designs for Spent Nuclear Fuel

Description: This work was performed in support of the planned Phase I request for proposals (RFP) for spent nuclear fuel (SNF) transportation cask designs. The funding for this work was provided by the Office of Civilian Radioactive Waste Management (OCRWM) through its M&O contractor, TRW Environmental Safety Systems (TESS). The objective of this work was to prepare for the criticality and shielding evaluation of the Phase I cask design proposals by investigating the effect of SNF and design variables … more
Date: January 1, 1993
Creator: Broadhead, B.L.
Partner: UNT Libraries Government Documents Department
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Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary.

Description: This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assess… more
Date: July 1, 2005
Creator: Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Mo, Tin (U.S. Nuclear Regulatory Commission, Washington, DC); Billone, Michael C. (Argonne National Laboratory, Argonne, IL) et al.
Partner: UNT Libraries Government Documents Department
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Radiation Effect on Microstructural Stability of RERTR Fuel

Description: Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-cladding interaction product using proton irradiation. SEM analysis indicates the presence of the phases of interest: U(Si,Al)3, (U,Mo)(Si,Al)3 and a mixture of UMo2Al20, U6Mo4Al43, and UAl4. Irradiation with 2.6 MeV protons at 200ºC to the doses of 0.1, 1.0 and 3.0 dpa are carried out.
Date: March 1, 2008
Creator: Gan, J.; Keiser, D. D. Jr.; Miller, B. D.; Allen, T. R. & Wachs, D. M.
Partner: UNT Libraries Government Documents Department
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Development of a Novel Depleted Uranium Treatment Process at Lawrence Livermore National Laboratory

Description: A three-stage process was developed at Lawrence Livermore National Laboratory to treat potentially pyrophoric depleted uranium metal wastes. The three-stage process includes waste sorting/rinsing, acid dissolution of the waste metal with a hydrochloric and phosphoric acid solution, and solidification of the neutralized residuals from the second stage with clay. The final product is a solid waste form that can be transported to and disposed of at a permitted low-level radioactive waste disposal … more
Date: January 22, 2007
Creator: Gates-Anderson, D.; Bowers, J.; Laue, C. & Fitch, T.
Partner: UNT Libraries Government Documents Department
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