107 核融合実験炉用ダイバータ模擬試験体の熱負荷特性

概要

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Divertor plates of nuclear fusion experimental reactor are considered to be joined together the plasma facing armor materials having the heat resistance in the heat sink materials of metals cooled activiely. In this study, the divertor model was produced by joining together C/C composite in the oxygen free copper using a titanium foil. And electron beam heating teats were carried out for the divertor model. The temperature charcteristics in the case of heat load test to the divertor model were obtain analytically, and it were compared and was examined with the heat load experiment. The wear was observed in the heat load test in thermal load over about 12.5MW/m^2 on the surface of C/C compsite. When thickness of the titanium foil was 0.05mm, the temperature of each part of the divertor model got analytically showed the value which was smaller than the value got by the heat load experiment.
一般社団法人日本機械学会の論文
2002-08-23