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Kawano, Takahiro*; Mizuta, Naoki; Ueta, Shohei; Tachibana, Yukio; Yoshida, Katsumi*
JAEA-Technology 2023-014, 37 Pages, 2023/08
JAEA-Technology-2023-014.pdf:2.35MB
Fuel compact for High Temperature Gas-cooled Reactor (HTGR) is fabricated by calcinating a matrix consisting of graphite and binder with the coated fuel particle. The SiC-matrixed fuel compact uses a new matrix made of silicon carbide (SiC) replacing the conventional graphite. Applying the SiC-matrixed fuel compact for HTGRs is expected to improve their performance such as power densities. In this study, the sintering conditions for applying SiC as the matrix of fuel compacts for HTGR are selected, and the density and thermal conductivity of the prototype SiC are measured.
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.
Mizuta, Naoki; Aoki, Takeshi; Ueta, Shohei; Ohashi, Hirofumi; Yan, X.
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05
Enhancement of safety and cooling performance of fuel elements are desired for a commercial High Temperature Gas-cooled Reactor (HTGR). Applying sleeveless fuel elements and dual side directly cooling structures with oxidation resistant SiC-matrix fuel compact has a possibility of improving safety and cooling performance at the pin-in-block type HTGR. The irradiated effective thermal conductivity of a fuel compact is an important physical property for core thermal design of the pin-in-block type HTGR. In order to discuss the irradiated effective thermal conductivity of the SiC-matrix fuel compact which could improve the cooling performance of the reactor, the maximum fuel temperature during normal operation of the pin-in-block type HTGR with dual side directly cooling structures are analytically evaluated. From these results, the desired irradiated thermal conductivity of SiC matrix are discussed. In addition, the suitable fabrication method of SiC-matrix fuel compact is examined from viewpoints of the sintering temperature, the purity and the mass productivity.
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
JAERI-Research-98-070.pdf:2.18MB
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：75.26(Nuclear Science & Technology)no abstracts in English
Sawa, Kazuhiro; Fukuda, Kosaku; R.Acharya*
JAERI-Tech 94-038, 46 Pages, 1995/01
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
; ; Ikawa, Katsuichi
Journal of Nuclear Science and Technology, 21(2), p.126 - 132, 1984/00
Times Cited Count：9 Percentile：67.69(Nuclear Science & Technology)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：52.35(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
Ikawa, Katsuichi; Tobita, Tsutomu; Iwamoto, K.
JAERI-M 7477, 9 Pages, 1978/01
no abstracts in English
