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Experimental verification of effectiveness of integrated pressure suppression systems in fusion reactors during in-vessel loss of coolant events

K. Takase, H. Akimoto2001年被引用 9Nuclear FusionIF 3出版社

An integrated ingress of coolant event (ICE) test facility was constructed to demonstrate that the ITER safety design approach and design parameters for ICEs are adequate. The major objectives of the integrated ICE test facility are: to estimate the performance of an integrated pressure suppression system; to obtain validation data for safety analysis codes; and to clarify the effects of two phase pressure drops at the divertor and condensation in the suppression tank. The integrated ICE test facility simulates the current ITER components with a scaling factor of 1/1600. The TRAC-PF1 code is used to verify the integrated ICE experimental results. From the present study the effectiveness of the ITER pressure suppression system was verified experimentally and analytically, and then it was clarified quantitatively that the prediction accuracy of the TRAC-PF1 code is very high.

日本語訳

冷却材侵入事象(ICE)のためのITER安全設計アプローチと設計パラメータが妥当であることを実証するために、統合冷却材侵入事象試験施設を建設した。統合ICE試験施設の主な目的は、統合圧力抑制系の性能を評価すること、安全解析コードの検証データを取得すること、ならびにダイバータにおける二相圧力損失および圧力抑制タンク内での凝縮の影響を明らかにすることである。統合ICE試験施設は、現在のITER構成機器を1/1600のスケーリング係数で模擬している。TRAC-PF1コードを用いて、統合ICE実験結果の検証を行った。本研究により、ITER圧力抑制系の有効性が実験的および解析的に検証され、TRAC-PF1コードの予測精度が非常に高いことが定量的に明らかになった。

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iter中精度(概要文一致)

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In-vessel components
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