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Ueta, Shohei; Mizuta, Naoki; Sasaki, Koei; Sakaba, Nariaki; Ohashi, Hirofumi; Yan, X.
Mechanical Engineering Journal (Internet), 7(3), p.19-00571_1 - 19-00571_12, 2020/06
JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 C. To increase economy of these HTGRs, JAEA has been upgrading the design method for the HTGR fuel, which can maintain their integrities at the burnup of three to four times higher than that of the conventional HTTR fuel. Design principles and specifications of various concepts of the high burnup HTGR fuels designed by JAEA are reported. As the latest results on post-irradiation examinations of the high burnup HTGR fuel progressing in a framework of international collaboration with Kazakhstan, irradiation shrinkage rate of the fuel compact as a function of fast neutron fluence was obtained at around 100 GWd/t. Furthermore, the future R&Ds needed for the high burnup HTGR fuel are described based on these experimental results.
Ueta, Shohei; Mizuta, Naoki; Sasaki, Koei; Sakaba, Nariaki; Ohashi, Hirofumi; Yan, X.
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 C. To increase economy of these HTGRs, JAEA has been upgrading the design method for the HTGR fuel, which can maintain their integrities at the burnup of three to four times higher than that of the conventional HTTR fuel. Design principles and specifications of various concepts of the high burnup HTGR fuels designed by JAEA are reported. As the latest results on post-irradiation examinations of the high burnup HTGR fuel progressing in a framework of international collaboration with Kazakhstan, irradiation shrinkage rate of the fuel compact as a function of fast neutron fluence was obtained at around 100 GWd/thm. Furthermore, the future R&Ds needed for the high burnup HTGR fuel are described based on these experimental results.
Sawa, Kazuhiro; Tobita, Tsutomu*; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Oda, Takefumi*; Watarumi, Kazutoshi*
JAERI-Tech 99-077, p.41 - 0, 1999/11
no abstracts in English
Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; Yoshimuta, Shigeharu*; ; ; ;
JAERI-Research 98-070, 25 Pages, 1998/11
no abstracts in English
Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; ; ; ;
Journal of Nuclear Science and Technology, 34(3), p.325 - 333, 1997/03
Times Cited Count:16 Percentile:75.29(Nuclear Science & Technology)no abstracts in English
; Akino, Fujiyoshi; Yamane, Tsuyoshi; ; Kitadate, Kenji; ; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko
JAERI 1305, 138 Pages, 1987/08
no abstracts in English
;
JAERI-M 87-023, 10 Pages, 1987/02
no abstracts in English
; ; ; Tobita, Tsutomu; Minato, Kazuo; Yamamoto, Katsumune; ;
JAERI-M 87-020, 79 Pages, 1987/02
no abstracts in English
; ; ; Minato, Kazuo; ; Ikawa, Katsuichi
Nihon Genshiryoku Gakkai-Shi, 26(1), p.57 - 74, 1984/00
Times Cited Count:1 Percentile:18.98(Nuclear Science & Technology)no abstracts in English
Ikawa, Katsuichi; ; ; ; ; Minato, Kazuo; Iwamoto, K.; ; ;
JAERI-M 83-012, 251 Pages, 1983/03
no abstracts in English
Ikawa, Katsuichi
Genshiryoku Kogyo, 28(8), p.53 - 57, 1982/00
no abstracts in English
; Minato, Kazuo; Ikawa, Katsuichi; ;
Journal of Nuclear Science and Technology, 18(11), p.887 - 894, 1982/00
Times Cited Count:4 Percentile:52.37(Nuclear Science & Technology)no abstracts in English
; ; ; Ikawa, Katsuichi
Nihon Genshiryoku Gakkai-Shi, 24(6), p.429 - 434, 1982/00
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)no abstracts in English
; Iwamoto, K.; Ikawa, Katsuichi
JAERI-M 9052, 19 Pages, 1980/08
no abstracts in English
; Iwamoto, K.; Ikawa, Katsuichi
JAERI-M 8952, 16 Pages, 1980/07
no abstracts in English
Tobita, Tsutomu; Iwamoto, K.
JAERI-M 5265, 19 Pages, 1973/05
no abstracts in English
Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji; Ishitsuka, Etsuo
no journal, ,
Coated fuel particles (CFPs) play an important role to the passive safety feature of the high temperature engineering test reactor (HTTR). However, random distribution of the CFPs also makes the simulation become more difficult and therefore affects the quality of the HTGR benchmark assessment. The highly accurate calculation enables the design of a commercial HTGR to operate with low cost and high performance. The purpose of this study was to develop MCNP model for the HTTR by using the explicit random model, namely Realized Random Packing (RRP), to improve the accuracy of the benchmark assessment. The RRP model was validated by comparing with the conventional uniform model as well as the experimental data. The neutronic and criticality calculations were performed by using MCNP6 code with ENDF/B-VII.1 nuclear data library.
Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji
no journal, ,