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

Author: Jung-Koenig, W.
Published: United States : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961.
Physical Description: microfiche : negative ; 8 x 13 cm
Additional Creators: Richter, H. and Zwicker, U.

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Summary

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)

Report Numbers

EURAEC-136

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: EUR/C/262/2/60 E
NSA number: NSA-18-014359
OSTI Identifier 4085799
Research organization: Metallgesellschaft A.G., Frankfurt am Main.

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