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Reexamination of D retention behavior in He ion irradiated RAFMs

H.-S. Zhou, Y.-P. Xu, H.-D. Liu, Y.-M. Lyu, F. Liu, X.-Z. Cao, B.-Y. Wang, T. Zhu, F. Ding, G.-N. Luo2018年被引用 11Nuclear FusionIF 3出版社

Helium (He) effects on deuterium (D) retention in reduced activation ferritic/martensitic steel (RAFMs) have been studied by high-energy He ion pre-injection and following D plasma exposure. He-damaged layers at the surface and inside the material bulk are induced by 3.5 MeV He ion bombardments with and without energy degrader, respectively. Iron (Fe) ion pre-irradiation is performed as a comparison so that He effects are clearly distinguished. It has been found that He injected into the bulk of RAFMs can suppress D retention whereas D behavior is not significantly affected by the damages from high-energy Fe ion. When the damage layers are shifted to the near surface, D retention is enhanced by both of He and Fe pre-irradiation.

日本語訳

ヘリウム(He)が低放射化フェライト/マルテンサイト鋼(RAFMs)における重水素(D)保持に及ぼす影響を、高エネルギーHeイオン事前照射とその後のDプラズマ曝露によって研究した。表面および材料内部のHe損傷層は、それぞれエネルギーデグレーダーを用いた場合と用いない場合の3.5 MeV Heイオン照射によって形成される。比較のため鉄(Fe)イオン事前照射も行い、Heの影響を明確に区別できるようにした。RAFMsの内部に注入されたHeはD保持を抑制できる一方、高エネルギーFeイオンによる損傷はDの挙動に大きな影響を与えないことが明らかになった。損傷層が表面近傍に移動した場合、D保持はHeおよびFeの事前照射の両方によって増強される。

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