核融合炉材料照射挙動のモデリング : 第一壁材料挙動に及ぼす非定常照射効果

概要

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The influence of radiation condition variations on microstructural evolution and its consequences in austenitic stainless steels is discussed, in order to help predicting the blanket / first wall materials behavior in fusion power devices. A kinetic microstructural evolution model developed for irradiated austenitic stainless steels was modified to incorporate a fully dynamic treatment of the point defect and point defect cluster evolutions. Using the modified model, microstructural evolution and cumulative defect flux imbalances were calculated for the simulated HFIR-RB13J temperature variation experiments and model neutron flux-temperature cycles in fusion reactors. The result indicated that a cyclic variation in irradiation temperature and neutron flux might stabilize or enhance macroscopic irradiation effects. It also suggested that hardening and the associated potential embrittlement will be anticipated, rather than swelling and irradiation creep, for fusion reactor materials during a long-pulsed operation.
社団法人プラズマ・核融合学会の論文
2001-02-25