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Journal Articles

Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts

Aihara, Jun; Goto, Minoru; Inaba, Yoshitomo; Ueta, Shohei; Sumita, Junya; Tachibana, Yukio

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.814 - 822, 2016/11

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.

Oral presentation

Analysis of high burnup irradiation tests of coated fuel for high temperature gas-cooled reactors

Kawano, Kaito*; Aihara, Jun; Sawa, Kazuhiro*

no journal, , 

Failure probability of coated fuel particles (CFPs) of high temperature gas-cooled reactors (HTGRs) under irradiation is strongly dependent on irradiation characters of pyrolytic carbon (PyC) layers of CFPs. But it is very difficult to newly obtain irradiation data of PyC layers with experiments. Therefore, in the past study, it was suggested to calculate failure probabilities based on a report summarizing irradiation data obtained at various irradiation temperatures of PyC layers of various Bacon anisotropy factor (BAF), and on result of failure probability measurement of irradiation test of the High Temperature Engineering Test Reactor (HTTR) fuel. Then a BAF of PyC layers of Japanese CFPs was suggested to use to calculate failure probability of Japanese CFPs. In this study, the failure probability was carried out under high burnup condition compared to the HTTR.

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