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U.S. Department of Energy
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TESTING ALLOYS OF ZIRCONIUM WITH NIOBIUM AND/OR SILICON WITH A VIEW TO THEIR USE AS CLADDING MATERIAL IN WATER-COOLED NUCLEAR REACTORS. Quarterly Report No. 5, April 1, 1961-June 30, 1961

Technical Report ·
OSTI ID:4085799
Experiments were conducted to determine the influence of various heat treatments on length variations brought about by thermal cycling. The results of these tests showed that the shrinkage observed in extrusion-hardened Zircaloy-2 and ZrNb/sub 3/Sn/sub 1/ tube sections can be avoided by annealing for one hour at 575 deg C. The fatigue tests on the alloys Zircaloy-2 and ZrNb/sub 2/ were completed. Comparison of the results with those hitherto obtained for the alloy The alloy ZrNb/sub 3/Sn/sub 1/ in particular has a considerably better fatigue behavior than Zircaloy-2, even when subjected to thermal treatment which is unfavorable to the fatigue behavior but favorable to the corrosion behavior. (auth)
Research Organization:
Metallgesellschaft A.G., Frankfurt am Main
NSA Number:
NSA-18-014359
OSTI ID:
4085799
Report Number(s):
EURAEC-136
Country of Publication:
United States
Language:
English