"Pin-cushion" Irradiation Tests of Uranium-chromium Alloys

Author: S. H. Paine

Publisher:

Published: 1958

Total Pages: 46

ISBN-13:

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Irradiation tests on small pins of wrought and heat-treated U235-Cr alloys mounted in special heat transfer blocks or ''cushions'' are described. Three compositions, estimated at 0.03, 0.07, and 0.22 wt.% Cr, were tested in three metallurgical conditions: alpha-annealed, beta-quenched, and isothermally transformed. Radiation damage to the specimens having the first two heat treatments was very similar to that observed in unalloyed uranium of comparable history, and the isothermally treated specimens were similar to beta-annealed uranium in behavior. In spite of this essentially null result, which is associated with failure to obtain grain refinement in the specimens, there is evidence that under proper conditions chromium additions to uranium may be beneficial.

"PIN-CUSHION" IRRADIATION TESTS OF URANIUM AND ITS ZIRCONIUM ALLOYS. Metallurgy Program 6.1.1

Author:

Publisher:

Published: 1956

Total Pages:

ISBN-13:

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ABS>An irradiation test of 1/16 in. diameter x 3/16 in. long U/sup 235/ and U/sup 235/-Zr alloy specimens, in the range 2 to 20 wt.% Zr, is described. The small pins were mounted in heat transfer blocks, or ''cushions, '' in such a way that suriace roughening and length changes could be observed, recorded, and compared for five stabilizing heat treatments up to exposure levels of approximately 1% total atom burnup. Addition of 2% Zr was found to be very beneficial, but the behavior of the alloys underwent distinct changes in going from 2 to 4 wt.% Zr. Material, both as-cast and subsequently isothermally treated, changed from minus to plus elongation, whereas wrought materials, either gamma-slow cooled or isothermally treated, changed from plus to minus behavior. Data-quenched wrought material varied unpredictably. Addition of Zr up to 20% showed further improvement in stability for all treatments. Factors which may have contributed to this behavior are discussed. (auth).

Status of Irradiation Tests of Dilute Uranium Alloys in NaK-Containing Stainless Steel Capsules
Status of Irradiation Tests of Dilute Uranium Alloys in NaK-Containing Stainless Steel Capsules

Author:

Publisher:

Published: 2001

Total Pages: 5

ISBN-13:

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To extend experience with uranium metal fuels to the high exposures required for power reactor operation, the Savannah River Laboratory has conducted over several years a series of irradiation tests of small uranium specimens of various alloy compositions in NaK-containing stainless steel capsules. These tests were designed specifically to establish the limits on exposure that could be reached during irradiation of the alloys at various temperatures without swelling and to determine the metallurgical factors that promoted the stability of the alloys. This paper discusses those test results.