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U.S. Department of Energy
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SUMMARY REPORT OF HRP IN-PILE CORROSION TEST AUTOCLAVE L53T-132

Technical Report ·
OSTI ID:4141809
Experiment L53T-132 employed a titanium autoclave to expose three Zircaloy-2 coupons and three titanium coupens in an experiment designed to provide information on the transport of Zircaloy-2 corrosion products in autoclaves and on the effects, if any, of such a transport on the radiation corrosion of Zircaloy-2. The data indicate that some of the Zircaloy-2 corrosion scales were transferred to titanium surfaces. The loose scale on the Zircaloy-2 specimens was only 0.7% uranium and contained only 1 ation g/ cm/sup 2/ of uranium. The underlying film and metal surface contained 22 ation g/cm/sup 2/ of uranium. The Zircaloy-2 corrosion rates in this test of a D/sub 2/ O solution were somewhat higher at given power densities than those in previous 280 tained C tests of all-Zircaloy-2 systems with similar light-water solutions. Radiochemical analyses of scale and surface samples indicated that little Cs/sup 137/ was included in the films and scales. Essentially all the Ru/ sup 103/ and much of the Pu/sup 239/ was deposited on the titanium surfaces. (auth)
Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-14-018760
OSTI ID:
4141809
Report Number(s):
CF-59-9-74
Country of Publication:
United States
Language:
English