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先進プラズマ研究開発

6th International Symposium on Fusion Nuclear Technology

掲載日:2018年12月26日更新
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HIGH HEAT LOAD TEST OF CFC DIVERTOR TARGET PLATE WITH SCREW TUBE FOR JT-60 SUPERCONDUCTING MODIFICATION

K. MASAKI, M. TANIGUCHI, Y. MIYO, S. SAKURAI, K. SATO, K. EZATO, H. TAMAI, A. SAKASAI, M. MATSUKAWA, S. ISHIDA, N. MIYA
Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Mukouyama, Naka-machi, Naka-gun, Ibaraki-ken, 311-0193 JAPAN

Abstract.
A flat carbon fiber composite tile mock-up with screw tubes, which have helical fins like a nut, was fabricated aiming at further improvement of the heat removal performance of the cost-effectively manufactured divertor target for JT-60SC (modified JT-60 as a superconducting coil tokamak). The heat removal performance of the mock-up was successfully demonstrated on the JAERI Electron Beam Irradiation Stand. The estimated heat transfer coefficient of the screw tube at the non-boiling region was roughly 3 times higher than that of the smooth tube. This corresponds to 1.5 times that of the swirl tube. A heat cycle test of 10 MW/m2 showed that the mock-up with the screw tubes could withstand for 1400 cycles. These results indicate that the divertor target plate with the flat carbon fiber composite tile and the screw tube can be a promising candidate for the JT-60SC divertor target.