照射損傷評価研究

Researches on radiation damage

伊藤 慶文*; 笹瀬 雅人*

Ito, Yoshifumi*; Sasase, Masato*

高速増殖炉「もんじゅ」の高度化炉心に対応した炉心構造材である酸化物分散強化型ステンレス鋼(以下、ODS鋼)や高Niオーステナイト系ステンレス鋼について、中性子照射によるスエリング特性を明らかにするために、イオン照射を用いた評価試験について、予備試験及び照射試験計画案の検討を行った。3MeVヘリウムイオン及び10MeV炭素イオンを連続的に照射したPNC316鋼及び9Cr-ODS鋼の照射挙動を評価し、PNC316鋼に対する中性子照射試験結果と比較した。その結果、ほぼ同程度の値が得られたことから、加速器によるイオン照射を用いたスエリング試験が中性子照射の模擬試験として適用可能であることが示唆された。

A feasibility study of irradiation experiments were carried out on radiation effect of oxide dispersion strengthened (ODS) steels and advanced austenitic stainless steels (PNC316) which are to be used in Fast Reactors. Void Swelling on the ion irradiation of PNC316 and 9Cr-ODS steels, which were irradiated in the Tandem accelerator in the Wakasawan Energy Research Center, were investigated. The samples were irradiated using 3 MeV He and 10 MeV C ions continuously. Transmission electron microscopy (TEM) examination was conducted to evaluate the swelling and microstructure. From the observation of the void sizes and densities, void swelling was estimated. A reproducibility of irradiation experiment is confirmed in our system. As a result, it was found out that the void swelling induced by the ion beam irradiation shows the similar behavior to the neutron-irradiation induced void swelling in the Fast Reactor cores. This implies the applicability of the ion beam irradiation to the neutron-irradiation induced void swelling simulation.