Radiometallurgical examination of 1.47 enriched I&E fuel elements for PT-IP-247-A

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Under the conditions of PT-IP-247-A, four columns of self-supported and four columns of rib-supported I&E 1.47% enriched fuel elements were irradiated to determine their relative performance under severe operating conditions. Four of the self-supported and two of the rib-supported control elements were received for nation. The two rib-supported control pieces, which were classified as ``near failures`` had received average exposures of 353 and 359 MWD/T at average specific power levels of 91 and 108 KW/ft before they were discharged because of other ruptured pieces in the tubes. The nominal specified canned fuel dimensions of the rib supported elements was 1.445 … continued below

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16 p.

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Teats, R. July 19, 1960.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
    Place of Publication: Richland, Washington

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Under the conditions of PT-IP-247-A, four columns of self-supported and four columns of rib-supported I&E 1.47% enriched fuel elements were irradiated to determine their relative performance under severe operating conditions. Four of the self-supported and two of the rib-supported control elements were received for nation. The two rib-supported control pieces, which were classified as ``near failures`` had received average exposures of 353 and 359 MWD/T at average specific power levels of 91 and 108 KW/ft before they were discharged because of other ruptured pieces in the tubes. The nominal specified canned fuel dimensions of the rib supported elements was 1.445 in. OD, .310 in bore, and 7.640 in. long. The first two self-supported elements were selected for examination on the basis of high weight losses sustained during irradiation, and the second two were selected to determine the effect of specific power levels on the AlSi bonding. The average specific power levels of the four self-supported elements varied from 79 to 110 KW/ft and the exposure varied from 845 MWD/T to 949 MWD/T. The nominal canned dimensions of the self-supported elements, which were made oversize to attain high annular coolant temperatures with respect to the interior coolant channel, were 1.460 in. OD, .375 in. bore, and 7.640 in. long. The eight bridge rail supports were spot welded on and gave an effective rib outside diameter of 1.600 in. All of the components were X-8001 aluminum alloy.

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16 p.

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OSTI as DE94010987; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

Other Information: DN: Declassified

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  • July 19, 1960

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  • Nov. 3, 2018, 11:47 a.m.

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  • Nov. 12, 2024, 1:26 a.m.

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Teats, R. Radiometallurgical examination of 1.47 enriched I&E fuel elements for PT-IP-247-A, report, July 19, 1960; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1311876/: accessed July 20, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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