Irradiation results in the range near 1/2% burnup and 500 to 600 deg C are presented for U-fissium amd U-Mo alloys. Under these conditions both classes of alloys show quite low growth coefficients and volume increases, with a few exceptions. Water queaching either alloy from 850 deg C is shown to be unsatisfactory. The effect of an axial hole for relief of fission gases appears to be inconclusive. Surface condition of irradiated U-base alloys appears to be not quite as good as that for U-20 wt.% Pu base alloys. (auth)
Publisher Info:
Argonne National Lab., Lemont, Ill.
Place of Publication:
Lemont, Illinois
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Irradiation results in the range near 1/2% burnup and 500 to 600 deg C are presented for U-fissium amd U-Mo alloys. Under these conditions both classes of alloys show quite low growth coefficients and volume increases, with a few exceptions. Water queaching either alloy from 850 deg C is shown to be unsatisfactory. The effect of an axial hole for relief of fission gases appears to be inconclusive. Surface condition of irradiated U-base alloys appears to be not quite as good as that for U-20 wt.% Pu base alloys. (auth)
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Smith, K.F.Irradiation of Uranium-Fissium Alloys and Related Compositions. Work Performed: 1956,
report,
September 1, 1957;
Lemont, Illinois.
(https://digital.library.unt.edu/ark:/67531/metadc1019629/:
accessed July 14, 2026),
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crediting UNT Libraries Government Documents Department.