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Plutonium isotopic analysis of highly enriched mixed oxides

Description: We investigated the analysis method used by the International Atomic Energy Agency (IAEA) to determine the plutonium isotopic composition of highly enriched mixed oxides (MOX). The IAEA currently uses the Cicero multichannel analyzer and the IAEAPU algorithm for its analysis. In our investigation the plutonium isotopic measurements were found to be good for PuO/sub 2/ powder or low-enriched MOX, but acceptable for highly enriched MOX in IAEA special nuclear material (SNM) accountability applica… more
Date: August 1, 1986
Creator: Clement, S. D. & Augustson, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the thorium axial blanket experiments in the PROTEUS reactor

Description: An extensive program of reactor physics experiments in GCFR fuel pin lattices has been completed recently at the PROTEUS critical facility located at EIR laboratory in Switzerland. The PROTEUS reactor consists of a central test zone surrounded by a uranium buffer and thermal driver region. The test lattices included a PuO/sub 2//UO/sub 2/ fuel region with internal and axial blankets of UO/sub 2/, ThO/sub 2/, and thorium metal. Detailed analysis of the thorium-bearing lattices has been performed… more
Date: January 1, 1980
Creator: White, J.R.; Ingersoll, D.T. & Schmocker, U.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Environmental radiation safety: source term modification by soil aerosols. Interim report

Description: The goal of this project is to provide information useful in estimating hazards related to the use of a pure refractory oxide of /sup 238/Pu as a power source in some of the space vehicles to be launched during the next few years. Although the sources are designed and built to withstand re-entry into the earth's atmosphere, and to impact with the earth's surface without releasing any plutonium, the possibility that such an event might produce aerosols composed of soil and /sup 238/PuO/sub 2/ ca… more
Date: August 1, 1980
Creator: Moss, O.R.; Allen, M.D.; Rossignol, E.J. & Cannon, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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End of life fission product distributions in F-1 experiment fuel rods

Description: Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of sealed, mixed-oxide fuel rods irradiated in the fast flux of EBR-II. Cesium, rubidium, iodine, and strontium data obtained from axial gamma scanning, mass spectrometry, and radiochemical analyses are presented. The results show significant migration of cesium, probably as both a volatile species and as the noble gas precursor. Cesium metal species leaving the fuel region accumulate predominately at… more
Date: May 1, 1980
Creator: Goodin, D. T.; Langer, S. & Bell, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Examination of fast reactor fuels, FBR analytical quality assurance standards and methods, and analytical methods development: Irradiation tests. Progress report, July 1--September 30, 1977. [PuO/sub 2/; UO/sub 2/]

Description: Information is presented concerning the examination of fast reactor fuels, FBR analytical quality assurance standards, and analytical methods development irradiation tests.
Date: November 1, 1977
Creator: Baker, R.D. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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/sup 238/Pu fuel-form processes. Quarterly report, October-December 1981

Description: Progress in the Savannah River /sup 238/Pu Fuel Form Program is summarized. Work during this period concentrated on the extensive cracking of the /sup 238/PuO/sub 2/ fuel form prior to encapsulation in the iridium containment shell for heat sources. This cracking results in increased recycle cost and decreased production efficiency. To better understand this cracking, Savannah River Laboratory (SRL) has made an extensive review of the development of /sup 238/PuO/sub 2/ fuel forms from small-sca… more
Date: May 1, 1982
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Milliwatt generator project: Progress report, April 1983--March 1984

Description: This report covers progress on the Milliwatt Generator Project during April 1983--March 1984. Activities included (plutonium 238 oxide) fuel processing and characterization, production of heat sources, fabrication of pressure-burst test units, compatibility studies, impact testing, examination of surveillance units, Inconel weld development, and qualilty assurance.
Date: May 1, 1988
Creator: Rinehart, G.H. & Latimer, T.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gamma densitometer for measuring Pu density in fuel tubes

Description: A fuel-gamma-densitometer (FGD) has been developed to examine nondestructively the uniformity of plutonium in aluminum-clad fuel tubes at the Savannah River Plant (SRP). The monitoring technique is ..gamma..-ray spectroscopy with a lead-collimated Ge(Li) detector. Plutonium density is correlated with the measured intensity of the 208 keV ..gamma..-ray from /sup 237/U (7d) of the /sup 241/Pu (15y) decay chain. The FGD measures the plutonium density within 0.125- or 0.25-inch-diameter areas of th… more
Date: January 1, 1982
Creator: Winn, Willard G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ir/PuO/sub 2/ compatibility: transfer of impurities from plutonium dioxide to iridium metal during high temperature aging

Description: 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 f… more
Date: January 1, 1984
Creator: Taylor, D. H.; Christie, W. H. & Pavone, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Voloxidation and dissolution of irradiated plutonium recycle fuels

Description: Voloxidation removed > 99.4% of the tritium in the fuels tested (LWR recycled fuels containing /sup 239/Pu). Voloxidation increased the amount of insoluble residue by roughly a factor of two. Voloxidation increased the amount of plutonium in the insoluble residue by factors of 4 to 5. Voloxidation made the insoluble plutonium much harder to dissolve.
Date: January 1, 1980
Creator: Cadieux, J.R. & Stone, J.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tested method to minimize plutonium assay discrepancies between laboratories

Description: Plutonium assay differences are frequently observed between laboratories exchanging plutonium dioxide powders. These differences are commonly the result of chemical changes and/or nonhomogeneities in sampled materials. The irregularities are often caused by moisture absorption during sampling, packaging, shipment, and storage of the materials. A method is proposed which eliminates the effects of chemical change in samples, particularly moisture absorption, and minimizes sampling error. A nondes… more
Date: January 29, 1982
Creator: Seiler, R. J.; Goss, R. L.; Rodenburg, W. W. & Rogers, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium from HEPA filters by Ce(IV): promoted dissolution of PuO/sub 2/ and recycle of the cerium promoter

Description: Studies carried out in this investigation included (1) electrolytic production of Ce(IV) from Ce(III), (2) leaching of refractory PuO/sub 2/ from HEPA filters with maintenance of Ce(IV) by anodic oxidation during leaching, and (3) evaluation of methods for contacting the HEPA solids with the leaching solution and for separating the solid residue from the leaching liquor. Anodic oxidation of Ce(III) was accomplished with an electric current efficiency of about 85% at current densities of 0.04 to… more
Date: May 1, 1980
Creator: Scheitlin, F.M. & Bond, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of pressure on the transient swelling rate of oxide fuel. [LMFBR]

Description: An analysis of the transient swelling rate of oxide fuel, based on fission-gas bubble conditions calculated with the FRAS3 code, has been developed and implemented in the code. The need for this capability arises in the coupling of the FRAS3 fission-gas analysis code to the FPIN fuel-pin mechanics code. An efficient means of closely coupling the calculations of swelling strains and stresses between the modules is required. The present analysis provides parameters that allow the FPIN calculation… more
Date: April 1, 1982
Creator: Gruber, E.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Space nuclear safety program. Progress report, August 1983

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.
Date: January 1, 1984
Creator: Bronisz, S. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979

Description: In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study … more
Date: January 1, 1980
Creator: Steindler, M J; Ader, M & Barletta, R E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ceramic and cermet targets

Description: Use of isotopic materials as targets in high temperature environments, e.g., reactor cores, require that chemically stable forms of the isotopes be employed. Usually oxides are compatible with temperatures > 1600/sup 0/K, although some light element oxides exhibit some volatility at temperatures > 1300/sup 0/K. Especially in the case of heavy elements, the relatively low melting points of the metals, poor compatibility of the metals with encapsulation materials, and high chemical reactivity at … more
Date: January 1, 1979
Creator: Kobisk, E. H.; Quinby, T. C. & Aaron, W. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Environmental and radiological safety studies: Interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, September 26-December 25, 1981

Description: Although existing radioisotope thermoelectric generator designs have proved more than adequately safe, more information is continually sought about the heat sources to improve their safety. The work here includes studies of the effects on the heat sources of terrestrial and aquatic environments and also of the effect of the heat sources on various simulated environments. This progress report presents recent data from environmental chamber and aquatic experiments and gives the present status of … more
Date: February 1, 1982
Creator: Matlack, G. M. & Patterson, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production equipment development needs for a 700 metric ton/year light water reactor mixed oxide fuel manufacturing plant

Description: A literature search and survey of fuel suppliers was conducted to determine how much development of production equipment is needed for a 700 metric tons/y LWR mixed-oxide (UO/sub 2/--PuO/sub 2/) fuel fabrication plant. Results indicate that moderate to major production equipment development is needed in the powder and pellet processing areas. The equipment in the rod and assembly processing areas need only minor development effort. Required equipment development for a 700 MT/y plant is not anti… more
Date: September 1, 1977
Creator: Blahnik, D.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide Partitioning and Transmutation Program. Progress report, April 1--June 30, 1977

Description: Experimental work on the 16 tasks comprising the Actinide Partitioning and Transmutation Program was continued. Summaries of work are given on Purex Process modifications, actinide recovery, Am-Cm recovery, radiation effects on ion exchangers, LMFBR transmutation studies, thermal reactor transmutation studies, fuel cycle studies, and partitioning-transmutation evaluation. (JRD)
Date: October 1, 1977
Creator: Tedder, D. W. & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of phosgene, chlorine, and hydrogen chloride as reagents for converting molten CaO. CaCl/sub 2/ to CaCl/sub 2/

Description: One method at Los Alamos for preparing impure plutonium metal from the impure oxide is by batch reduction with calcium metal at 850/sup 0/C in a CaCl/sub 2/ solvent. The solvent salt from this reduction is currently discarded as low-level radioactivity waste only because it is saturated with the CaO byproduct. We have demonstrated a pyrochemical technique for converting the CaO to CaCl/sub 2/ thereby incorporating solvent recycling into the batch reduction process. We will discuss the effective… more
Date: January 1, 1985
Creator: Fife, K. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Light Weight Radioisotopic Heater Unit (LWRHU) production for the Galileo Mission

Description: The Light Weight Radioisotopic Heater Unit (LWRHU) is a /sup 238/PuO/sub 2)minus/ fueled heat source designed to provide a thermal watt of power for space missions. The LWRHU will be used to maintain the temperature of various components on the spcaecraft at the required level. The heat source consists of a /sup 238/PuO/sub 2/ fuel pellet, a Pt-30Rh capsule, a pyrolytic graphite insulator, and a woven graphite aeroshell assembly. Los Alamos National Laboratory (LANL) has fabricated 134 heater u… more
Date: April 1, 1988
Creator: Rinehart, G.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reduced-size plutonium sample processing and packaging for the PAT-2 package

Description: A light-water container for the air transport of plutonium safeguards samples, the PAT-2 package, has been developed in the USA and is now licensed by the US NRC (Certificate of Compliance) and the US DOT (IAEA Certificate of Competent Authority). The very limited available space in this package for plutonium-bearing samples required the design of small-size canisters to meet the needs of international safeguards. The suitability of a new small canister and vial for powder and solution samples … more
Date: January 1, 1982
Creator: Kuhn, E.; Deron, S.; Aigner, H. & Andersen, J. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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