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Simulation of cryogenic He spills as basis for planning of experimental campaign in the EVITA facility

G. Caruso, H.W. Bartels, M. Iseli, R. Meyder, S. Nordlinder, V. Pasler, M.T. Porfiri2006年被引用 7Nuclear FusionIF 3出版社

Code validation activities have been promoted inside the European fusion development agreement (EFDA) to test the capability of codes in simulating accident phenomena in fusion facilities and, specifically, in the International thermonuclear experimental reactor (ITER). This work includes a comparison between three different computer codes (CONSEN, MAGS and MELCOR) and one analytical model (ITER Model) in simulating cryogenic helium releases into the vacuum vessel (VV) which contains hot structures. The scope was the evaluation of the transient pressure inside the VV. The results will be used to design a vent duct (equivalent diameter, length and roughness) to allow pressure relief for the protection of the VV, which has a maximum design pressure of 200 kPa. The model geometry is a simplified scheme preserving the main features of the ITER design. Based on the results of the simulations, a matrix of experiments was developed to validate the calculated results and to design the vent duct for the ITER VV. The experiments are planned to be performed in the EVITA test facility, located in the CEA Cadarache research centre (France).

日本語訳

欧州核融合開発協定(EFDA)内で、核融合施設、特に国際熱核融合実験炉(ITER)における事故現象のシミュレーションにおけるコードの能力を試験するために、コード検証活動が推進されてきた。この作業には、高温構造物を収容する真空容器(VV)への極低温ヘリウム放出のシミュレーションにおける、3つの異なるコンピュータコード(CONSEN、MAGS、MELCOR)と1つの解析モデル(ITERモデル)との比較が含まれる。目的は、VV内部の過渡圧力の評価であった。結果は、最大設計圧力200 kPaを有するVVを保護するための圧力逃がしを可能にするベントダクト(等価直径、長さ、粗さ)の設計に使用される予定である。モデル形状は、ITER設計の主要な特徴を保持した簡略化スキームである。シミュレーションの結果に基づいて、計算結果を検証し、ITER VV用のベントダクトを設計するための実験マトリクスが開発された。実験は、フランスのCEAカダラッシュ研究センターにあるEVITA試験施設で実施される予定である。

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