Radiative heat deposition analysis of fusion reactor first wall by Monte Carlo transport code.
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概要
- 論文の詳細を見る
Heat flux distribution on the first wall of a fusion reactor due to the thermal radiation from high temperature protection wall placed in front of the first wall was analyzed. With necessary modifications, a three-dimensional Monte Carlo transport code developed for neu-tronics calculation was successfully applied in the analysis. That is, reasonable results with sufficiently small statistical error were obtained with reasonable computational time. The heat flux distribution was found to be insensitive to the reflection characteristic of the radiation at the first wall i. e. diffusive or specular.
- 一般社団法人 日本原子力学会の論文
著者
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SEKI Yasushi
Japan Atomic Energy Research Institute
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IIDA Hiromasa
Japan Atomic Energy Research Institute
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SAKO Kiyoshi
Japan Atomic Energy Research Institute
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