Search

Susceptibility to stress corrosion cracking (SCC) of zirconium was investigated as for in the spent nuclear fuel dissolver environment of the reprocessing facilities. Constant load tensile tests were conducted in the nonradioactive simulated spent nuclear fuel solution in both nobler potential and boiling heat-transfer conditions. It was found that susceptibility to SCC of zirconium strongly depended on electrode potential. The time to failure clearly declined at 1.55 V (vs. SSE) and the cleavage fracture like a facet-shaped was observed. Quasi-cleavage fracture was only observed on the specimen surface less noble than 1.50 V, but the time to failure scarcely declined comparing to that of silicon oil. Decline of time to failure was also observed under boiling heat-transfer condition. However, the decline of time to failure under boiling heat-transfer condition was nearly equal to the corresponding temperature to heat-transfer condition with silicon oil. As for the index of susceptibility to SCC, the ratio of transition time from secondary to third creep to failure time indicated that the susceptibility to SCC were very high in 1.55 V. The index indicated that boiling heat-transfer scarcely enhanced the susceptibility. It's considered that SCC behavior of zirconium in spent nuclear fuel dissolver environment mainly depends on its creep property. (author)