Corrosion mechanism of component materials used in nuclear fuel reprocessing plant, 4; Confirmation of environment assisted cracking of zirconium by hot laboratory tests

Numata, Masami; Kato, Chiaki   ; Motooka, Takafumi; Endo, Shinya; Kitagawa, Isamu; Kizaki, Minoru; Yamamoto, Masahiro ; Kiuchi, Kiyoshi

We estimated environment assisted cracking of zirconium such as the unclear fuel dissolver in spent unclear fuel solution and considered the cold simulated solution with substituted similar oxidization ions for trans-uranium (TRU) and fission products (FP) and difference between the cold simulated solution and the hot spent unclear fuel. In addition, we considered radiation effect of ray under irradiation of cobalt-60 to simulate closely the dissolver condition. In this report, we confirmed that the cold simulated solution is appropriate solution to substitute for the spent nuclear fuel solution and radiation of ray doesn't accelerate environment assisted cracking of zirconium.