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Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part II: steels pre-damaged with 20 MeV W ions and high heat flux

O.V. Ogorodnikova, Z. Zhou, K. Sugiyama, M. Balden, G. Pintsuk, Yu. Gasparyan, V. Efimov2017年被引用 22Nuclear FusionIF 3出版社

The reduced-activation ferritic/martensitic (RAFM) steels including Eurofer (9Cr) and oxide dispersion strengthened (ODS) steels by the addition of Y2O3 particles investigated in Part I were pre-damaged either with 20 MeV W ions at room temperature at IPP (Garching) or with high heat flux at FZJ (Juelich) and subsequently exposed to low energy (~20–200 eV per D) deuterium (D) plasma up to a fluence of 2.9  ×  1025 D m−2 in the temperature range from 290 K to 700 K. The pre-irradiation with 20 MeV W ions at room temperature up to 1 displacement per atom (dpa) has no noticeable influence on the steel surface morphology before and after the D plasma exposure. The pre-irradiation with W ions leads to the same concentration of deuterium in all kinds of investigated steels, regardless of the presence of nanoparticles and Cr content. It was found that (i) both kinds of irradiation with W ions and high heat flux increase the D retention in steels compared to undamaged steels and (ii) the D retention in both pre-damaged and undamaged steels decreases with a formation of surface roughness under the irradiation of steels with deuterium ions with incident energy which exceeds the threshold of sputtering. The increase in the D retention in RAFM steels pre-damaged either with W ions (damage up to ~3 µm) or high heat flux (damage up to ~10 µm) diminishes with increasing the temperature. It is important to mention that the near surface modifications caused by either implantation of high energy ions or a high heat flux load, significantly affect the total D retention at low temperatures or low fluences but have a negligible impact on the total D retention at elevated temperatures and high fluences because, in these cases, the D retention is mainly determined by bulk diffusion.

日本語訳

第I部で調査した、Y₂O₃粒子の添加によるODS鋼を含むRAFM鋼(ユーロフェル96、9Cr)を、まずIPP(ガルヒング)において20 MeVのWイオンで室温照射するか、またはFZJ(ユーリッヒ)において高熱流束に曝露して予備損傷を与え、その後、290 Kから700 Kの温度範囲で、低エネルギー(Dあたり約20~200 eV)の重水素(D)プラズマに、2.9 × 10²⁵ D m⁻²のフルエンスまで曝露した。20 MeVのWイオンによる室温での1 dpaまでの予備照射は、Dプラズマ曝露前後の鋼の表面形態に顕著な影響を及ぼさない。Wイオンによる予備照射は、ナノ粒子の有無やCr含有量に関係なく、調査したすべての鋼種において同じ重水素濃度をもたらす。(i)Wイオン照射と高熱流束曝露の両方の予備損傷が、未損傷鋼と比較して鋼中のD保持を増加させること、(ii)予備損傷の有無にかかわらず、D保持は、スパッタリングの閾値を超える入射エネルギーを持つ重水素イオンによる照射下での鋼の表面粗さの形成に伴い減少することが見出された。Wイオン(損傷深さ約3 µm)または高熱流束(損傷深さ約10 µm)のいずれかによる予備損傷を受けたRAFM鋼におけるD保持の増加は、温度の上昇とともに減少する。高エネルギーイオンの注入または高熱流束負荷によって引き起こされる表面近傍の改質は、低温または低フルエンスでの総D保持に有意に影響するが、高温および高フルエンスでは、D保持が主にバルク拡散によって支配されるため、その影響は無視できる程度であることに言及することが重要である。

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DeuteriumDeuterium plasmaDeuterium retention
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