Present Status of Fusion Safety Experiments for Thermal-Hydraulics

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Other Title
  • 核融合熱流動安全性実験の現状
  • カク ユウゴウ ネツ リュウドウ アンゼンセイ ジッケン ノ ゲンジョウ
  • 3.核融合熱流動安全性実験の現状(<小特集>核融合施設における安全解析)
  • 核融合熱流動安全性実験の現状
  • 小特集 核融合施設における安全解析
  • ショウ トクシュウ カク ユウゴウ シセツ ニ オケル アンゼン カイセキ

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As part of experimental study of thermal-hydraulic safety for the International Thermonuclear Experimental Reactor (ITER), preliminary experiments on the ingress of coolant event (ICE) and the loss of vacuum event (LOVA) have been carried out by the Japan Atomic Energy Research Institute (JAERI). In the ICE experiment, boiling heat transfer and pressure rise characteristics in the vacuum vessel (VV) were investigated and the depressurization effect of the suppression tank after the ICE occurred was clarified. In the LOVA experiment, thermal-hydraulic characteristics of buoyancy-driven exchange flows through breaches in the VV under the LOVA conditions were investigated for various breach conditions. Results of the ICE and LOVA experiments were utilized as validation data for thermofluids-safety analysis codes in ITER.



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