FRETTING CORROSION OF N-REACTOR FUEL ASSEMBLIES AND PROCESS TUBE IN OUT-OF-REACTOR TESTING

摘要

Fretting corrosion resistance of N-Reactor Zircaloy-2 clad fuel elements in hot flowing water was studied in an out-of-reactor loop. Accelerated fretting corrosion of the inside of the outer fuel tube by the contacting supports of the inner fuel tube was observed in several fuel element assemblies. Fretting corrosion of the Zircaloy-2 process tube by the contacting supports of the outer fuel tube was also observed.