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Horton, R.M.; Miller, R.L.; Reimann, G.A.
Idaho National Engineering Lab., Idaho Falls (USA)1978
Idaho National Engineering Lab., Idaho Falls (USA)1978
AbstractAbstract
[en] The corrosion and hydriding behavior of galvanically coupled 5454 aluminum and zircaloy-4 in a nuclear reactor core was studied in a simulated fuel-cladding/canister configuration. Tests were conducted in reactor quality water at 298 and 3550K. Possible control methods by means of protective coatings were also studied. The results indicate that embrittlement of zircaloy-4 by corrosion-induced hydriding would not be a problem in this application, and corrosion damage to the aluminum would not be significant. Findings are applicable for limited periods of service or storage
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Aug 1978; 101 p; TREE--1169; Available from NTIS., PC A06/MF A01
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