Post-irradiation examination of uranium-silicon alloy fuel elements irradiated in exp-NRX-430 PDF Download
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Author: K. D. Cotnam
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Languages : en
Pages : 0
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Author: K. D. Cotnam
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: K. D. Cotnam
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: K. D. Cotnam
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Category :
Languages : en
Pages : 0
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Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
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Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Author: P. Hiramatsu
Publisher:
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Category :
Languages : en
Pages : 0
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Author: R. J. Chenier
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Category :
Languages : en
Pages : 0
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Author:
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Category :
Languages : en
Pages : 11
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Two irradiation test vehicles, designated RERTR-1 and RERTR-2, were inserted into the Advanced Test Reactor in Idaho in August 1997. These tests were designed to obtain irradiation performance information on a variety of potential new, high-density uranium alloy dispersion fuels, including U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru and U-10Mo-0.05Sn; the intermetallic compounds U2Mo and U3Si2 were also included in the fuel test matrix. These fuels are included in the experiments as ''microplates'' (76 mm x 22 mm x 1.3 mm outer dimensions) with a nominal fuel volume loading of 25% and irradiated at relatively low temperature ((approximately) 100 C). RERTR-1 and RERTR-2 were discharged from the reactor in November 1997 and July 1998, respectively, at calculated peak fuel burnups of 45 and 71 at.%-U235. Both experiments are currently under examination at the Alpha Gamma Hot Cell Facility at Argonne National Laboratory in Chicago. This paper presents the postirradiation examination results available to date from these experiments.
Author:
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Category :
Languages : en
Pages : 10
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This report discusses three natural uranium, X-8001 aluminum clad, I & E Hanford production fuel elements, which were irradiated in 3363-D as part of PT-IP-262-A, were selected for detailed examination in the Radiometallurgy Laboratory. The three pieces were from the same tube and each had lost about 15 grams of cladding during irradiation. Examination was requested to determine the extent of the corrosion and whether the attack was uniform or localized. Also, measurement of the uranium fuel was requested to reveal any change that occurred during irradiation. Corrosion was general rather than localized and occurred over approximately three-fourths of the surface. In each element. about one-fourth of the surface on one side was virtually unattacked and vas probably the area that lay between the ribs of the process tube during irradiation. In one element localized attack occurred beside two of the bumpers. External aluminum cladding thicknesses ranged from 0.020 to 0.043 inch. About 0.005 inch of the spire surface vas removed by corrosion. Both internal and external dimensions of the uranium increased. The average external diameter was 0.010 inch larger and the average internal diameter vas 0.011 inch larger than the average preirradiation diameter measurements. The growth vas not uniform as ellipticity up to 0.028 inch was observed.
Author: R. R. Elder
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author:
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ISBN:
Category :
Languages : en
Pages : 16
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A low-enrichment uranium (LEU) irradiation test (SIMONE project) was performed in the 45 MW Petten High-flux Reactor (HFR) as part of the Reduced Enrichment for Research and Test Reactor (RERTR) program. An LEU U3Si{sub 1.6}-Al dispersion fuel element with a fuel loading of 5.5 g cm−3 was irradiated and performed well to a total burnup of 66% and a peak burnup of 85%. The swelling behavior of the fuel was similar to that observed in previous U3Si(subscript x) irradiation experiments. The resulting fuel plate thickness increases and associated changes in coolant channel cross-sections were well within acceptable limits.
