Study on thermal fatigue testing of a prototypical first wall component

AbstractThe thermal fatigue testing of a prototypical first wall mock-up is described and a comparison is made between the experimental results and numerical calculations. The ASME-III and RCC-MR nuclear standards are applied to assess possible extensions to the design of the fusion reactor first wall as far as cyclic thermal loads are concerned.

日本語訳

原型第一壁モックアップの熱疲労試験について説明し、実験結果と数値計算の比較を行う。ASME-IIIおよびRCC-Mの原子力規格を適用して、循環熱負荷に関する核融合炉第一壁の設計拡張の可能性を評価する。