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- W153817811 abstract "This paper presents an overview of research on the strength of fusion reactor first-wall materials, and on thermal hydraulics for high heat flux components. The first wall of a fusion reactor is assumed to be subjected to a high heat flux on plasma disruption and a high heat cycle corresponding to plasma on and off conditions. It is important to investigate the irradiation effect of high heat flux on material strength since a high heat flux can cause melting and evaporation in the wall. An experimental material strength study was conducted on two 100- {times} 20- {times} 10-mm bars by applying a high heat flux using a 10-kW CO{sub 2} laser system. The materials used were 20-mm-thick plates made of SUS 316 and 304." @default.
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- W153817811 date "1990-03-01" @default.
- W153817811 modified "2023-09-26" @default.
- W153817811 title "The University of Tsukuba" @default.
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- W153817811 doi "https://doi.org/10.13182/fst90-a39887" @default.
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