Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts
相原 純; 後藤 実; 稲葉 良知; 植田 祥平; 角田 淳弥; 橘 幸男
Aihara, Jun; Goto, Minoru; Inaba, Yoshitomo; Ueta, Shohei; Sumita, Junya; Tachibana, Yukio
Japan Atomic Energy Agency (JAEA) has started R&D for apply SiC/C mixed matrix to fuel element of high temperature gas-cooled reactors (HTGRs) to improve oxidation resistance of fuel. Nuclear thermal design of HTGR with SiC/C mixed matrix fuel compacts was carried out as a part of above R&Ds. Nuclear thermal design was carried out based on a small sized HTGR for developing countries, HTR50S. Maximum enrichment of uranium is set to be 10 wt%, because coated fuel particles with 10 wt% uranium have been fabricated in Japan. Numbers of kinds of enrichment and burnable poisons (BPs) were set to be same as those of original HTR50S (3 and 2, respectively). We succeeded in nuclear thermal design of a small sized HTGR which performance was equivalent to original HTR50S, with SiC/C mixed matrix fuel compacts. Based on nuclear thermal design, intactness of coated fuel particles was evaluated to be kept on internal pressure during normal operation.
使用言語 : English
掲載資料名 : Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (DVD-ROM)
ページ数 : p.814 - 822
発行年月 : 2016/11
出版社名 : American Nuclear Society
発表会議名 : 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016)
開催年月 : 2016/11
開催都市 : Las Vegas
開催国 : U. S. A.
特許データ :
論文URL :
キーワード : 高温ガス炉; 燃料; 核熱設計; 内圧破損; SiC/C混合母材
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 : 文部科学省
登録番号 : BB20160289
抄録集掲載番号 : 45000093
論文投稿番号 : 18429
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