Investigation on the Corrosion Behavior of Nuclear Grade Stainless Cladding Materials

Tests of pitting corrosion and intergranular corrosion of two Chinese stainless cladding materials are carried out according to standards of GB4334 7 84 and French RCC M MC1310. Under the water chemistry condition simulating pressurized water reactors(PWRs) coolant(temperature,345 ℃;B,800 mg/L;Li,2 mg/L), their stress corrosion and uniform corrosion behaviors are studied. The results show that no stress corrosion cracking in U shape samples is found and average static uniform corrosion rate is less than 2 mg/dm 2 after testing in high temperature borated water for 5 000 h. Both of stainless cladding materials have better corrosion resistance.