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Thermofluid experiments on ingress of coolant event

Tomoaki Kunugi, Kazuyuki Takase, Mitsuhiko Shibata, Ryouichi Kurihara, Yasushi Seki1998年Fusion Engineering and DesignIF 1.7出版社

AbstractOne of the serious thermofluid safety issues in a fusion experimental reactor is an ingress of coolant event (ICE), when the water in a coolant pipe is ejected into the vacuum vessel (VV) if an accident occurs, such as a runaway electron impact on the coolant pipes. If the VV cannot withstand the high pressurization caused by water evaporation in the VV, and on the high-temperature plasma-facing components, the steam containing activated dusts could be transferred from the VV to the environment. Therefore, it is important to understand the entire thermofluid characteristics during ICE conditions. This paper describes the first set of ICE experimental results, such as pressure transients in VV and transient temperature distributions on a water-jet impingement wall. It was found that pressurization under vacuum conditions, as an initial pressure condition in VV, is very different from that under atmospheric pressure conditions when the VV is filled with air at 0.1 MPa. The reasons for this discrepancy and some heat transfer characteristics on the target wall are discussed.

日本語訳

核融合実験炉における深刻な熱流体安全問題の一つは、冷却材侵入事象(ICE)である。これは、例えば逃走電子が冷却管に衝突するなどの事故が発生した場合に、冷却管内の水が真空容器(VV)内に噴出する現象である。真空容器内での水の蒸発による高い加圧、および高温プラズマ対向部材上での事象に真空容器が耐えられない場合、放射性ダストを含む蒸気が真空容器から環境中へ移行する可能性がある。したがって、ICE条件下における全体的な熱流体特性を理解することが重要である。本論文では、真空容器内の圧力過渡現象および水ジェット衝突壁面上の過渡温度分布など、ICE実験結果の第一報を報告する。真空容器の初期圧力条件としての真空条件下での加圧は、真空容器が0.1 MPaの空気で満たされている大気圧条件下での加圧とは大きく異なることが見出された。この相違の理由および対象壁面上のいくつかの熱伝達特性について考察する。

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