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Evaluation of SS316 first wall material for activation and afterheat for maintenance purposes

I. Schreinlechner, I. Šmid, G. Weimann1991年Fusion Engineering and DesignIF 1.7出版社

AbstractOne criterion for the choice of first wall materials in the post-activation behavior after exposure to fast fusion neutrons. For the reference material, stainless steel SS316, finite-element model calculations under NET technology phase conditions revealed the heat output after thermonuclear operation to stay almost constant for more than one year, declining with the decay of Mn and Co isotopes. Water cooling of the irradiated first wall was extended tto five hours after plasma shutdown. As soon as the water cooling is terminated, the temperature of the steel rises to >800°C, unless the top/bottom surfaces will be cooled. If a forced gas convection is installed after shutdown of watercooling, the temperature of the first wall may result in a steady state of as low as 200°C, depending on the velocity of the gas flow. If lower temperatures are desired for maintenance purposes, additional operational cooling will have to be considered.

日本語訳

核融合炉の高速中性子への曝露後の第一壁材料の選択基準の一つとして、その後の放射化挙動が挙げられる。参考材料であるステンレス鋼SS316について、NET技術段階の条件下での有限要素モデル計算により、熱核融合運転後の発熱量は、Mn同位体およびCo同位体の崩壊に伴い、1年以上にわたりほぼ一定に保たれることが明らかになった。照射された第一壁の水冷を、プラズマ停止後5時間まで延長した場合、水冷終了直後には鋼の温度は800℃を超えるまで上昇する。ただし、上下の表面が冷却される場合にはこの限りではない。水冷停止後に強制ガス対流冷却を導入すれば、ガス流速に応じて、第一壁の温度は200℃程度の定常状態にまで低下し得る。保守作業のためにさらなる低温化が必要な場合には、追加の能動冷却措置を検討する必要がある。

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