Abstract
To understand microstructural evolution during fission neutron irradiation, a pure Fe-Cr-Ni ternary alloy, phosphorus-containing model austenitic stainless steels and SUS316 were irradiated in a Japanese Material Testing Reactor (JMTR) at 493 and 613 K. At 493 K, the density of defect cluster increased with the irradiation dose, but there was no significant change in loop density and loop size among all the materials. At 613 K, on the other hand, interstitial type dislocation loops and phosphides were formed in pure ternary and phosphorus-containing alloys, respectively, by an early stage of irradiation. These results suggest that the defect cluster formation at 493 and 613 K is mainly controlled by the cascade damage and long-range migration of free point defects, respectively.
| Original language | English |
|---|---|
| Pages (from-to) | 381-384 |
| Number of pages | 4 |
| Journal | Journal of Nuclear Materials |
| Volume | 271-272 |
| DOIs | |
| Publication status | Published - May 1999 |
| Event | Proceedings of the 1997 8th International Conference on Fusion Reactor Materials (ICFRM-8), Part C - Sendai, Jpn Duration: Oct 26 1997 → Oct 31 1997 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering