2.プラズマと真空容器内機器の過渡挙動解析(<小特集>核融合施設における安全解析)
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概要
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This article provides a safety assessment method for plasma transients including thermal response of in-vessel components. We developed a safety analysis code (SAFALY) consisting of a 0-D plasma dynamics model and a 1.5-D thermal behavior model of in-vessel components. On the basis of ITER plasma physics reference, we made a plasma physics model for safety analysis which contains a beta limit, a density limit, H-L confinement mode transient, etc. This code can treat thermal hydraulic accidents using thermal hydraulic data from another code and analyze a passive plasma shutdown scenario through the use of a simple impurity transport model. A few specific off-normal events in the ITER were analyzed to investigate the code's safety performance. Plasma off-normal events were found that the confinement boundary can be kept intact during events, which would allow the cooling system to work normally. For ex-vessel LOCA in the first wall/blanket, we discovered a possibility of passive plasma shutdown by impurity ingress before the cooling tubes melt. The code needs further modification before its implementation as an analyses tool or safety code.
- 社団法人プラズマ・核融合学会の論文
- 1997-08-25