| Autor: |
Koreyuki Shiba, Hajime Nakajima, Shiro Jitsukawa, Takashi Tsukada, Itaru Shibahara, Y. Sato |
| Rok vydání: |
1993 |
| Předmět: |
|
| Zdroj: |
Journal of Nuclear Materials. 207:159-168 |
| ISSN: |
0022-3115 |
| DOI: |
10.1016/0022-3115(93)90258-z |
| Popis: |
Type 316 stainless steel from the core of the experimental fast breeder reactor (FBR) JOYO was examined by the slow strain rate tensile (SSRT) test in pure, oxygenated-water and air and by the electrochemical potentiokinetic reactivation (EPR) test to evaluate a susceptibility to the irradiation assisted stress corrosion cracking (IASCC) and the radiation-in-duced segregation (RIS). The solution annealed and 20% cold-worked materials had been irradiated at 425°C to a neutron fluence of 8.3 × 1026n/m2 (〉 0.1 MeV) which is equivalent to 40 displacement per atom (dpa). Intergranular cracking was induced by the SSRT in water at 200 and 300°C, but was not observed on specimen tested in water at 60°C and in air at 300°C. This indicates that irradiation increased a susceptibility to stress corrosion cracking (SCO in water. After the EPR test, grain boundary etching was observed in addition to grain face etching. This suggests Cr depletion may have occurred both at grain boundary and at defect clusters during the irradiation. The results are compared with the behavior of similar materials irradiated with different neutron spectrum. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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