Comparison of Coolant Conditions in the Blanket for a Water-Cooled DEMO Reactor SlimCS
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概要
- 論文の詳細を見る
The blanket structure of the SlimCS has been studied under coolant condition of Pressurized Water Reactor (PWR) to improve the compatibility with F82 H. The neutronic and thermal calculation are performed for the simplified blanket structure, which Li4SiO4 pebbles or Li2O pebbles for tritium breeding and Be12Ti pebbles for neutron multiplication are mixed and these pebbles are filled in the blanket. As a result, the TBR of blanket by PWR water condition is higher than those of sub-critical water condition because the tritium breeding area in the blanket is extended by decreasing thickness of coolant tube in comparison with sub-critical water condition. The blanket with PWR water condition can attain target of the net TBR (≥ 1.05) and satisfy condition of conducting shell for MHD stability.
著者
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Tobita Kenji
Japan Atomic Energy Research Institute
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SOMEYA Youji
Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan
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TAKASE Haruhiko
Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan
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UTOH Hiroyasu
Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan
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ASAKURA Nobuyuki
Japan Atomic Energy Agency
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ASAKURA Nobuyuki
Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan
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LIU Changle
Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan
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UTOH Hiroyasu
Japan Atomic Energy Agency
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TAKASE Haruhiko
Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan
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SOMEYA Youji
Japan Atomic Energy Agency
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