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Goto, Minoru; Okumura, Keisuke; Nakagawa, Shigeaki; Inaba, Yoshitomo; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*
Fusion Engineering and Design, 136(Part A), p.357 - 361, 2018/11
Times Cited Count：6 Percentile：52.24(Nuclear Science & Technology)A High Temperature Gas-cooled Reactor (HTGR) is proposed as a tritium production device, which has the potential to produce a large amount of tritium using 
Li(n,
)T reaction. In the HTGR design, generally, boron is loaded into the core as a burnable poison to suppress excess reactivity. In this study, lithium is loaded into the HTGR core instead of boron and is used as a burnable poison aiming to produce thermal energy and tritium simultaneously. The nuclear characteristics and the fuel temperature were calculated to confirm the feasibility of the lithium-loaded HTGR. It was shown that the calculation results satisfied the design requirements and hence the feasibility was confirmed for the lithium-loaded HTGR, which produce thermal energy and tritium.
Onuki, Akira; Takase, Kazuyuki; Kureta, Masatoshi; Yoshida, Hiroyuki; Tamai, Hidesada; Liu, W.; Akimoto, Hajime
Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.247 - 248, 2003/08
We start R&D project to develop the predictable technology for thermal-hydraulic performance of Reduced-Moderation Water Reactor (RMWR) in collaboration with power company/reactor vendor/university since 2002. The RMWR can attain the favorable characteristics such as effective utilization of uranium resources, multiple recycling of plutonium, high burn-up and long operation cycle, based on matured BWR technologies. MOX fuel assemblies with tight lattice arrangement are used to increase the conversion ratio by reducing the moderation of neutron energy. Increasing the in-core void fraction also contributes to the reduction of neutron moderation. The confirmation of thermal-hydraulic feasibility is one of the most important R&D items for the RMWR because of the tight lattice configuration. This series presentation focuses on the feasibility study and shows the R&D plan using large-scale test facility and advanced numerical simulation technology.
Araya, Fumimasa; Kureta, Masatoshi; Akimoto, Hajime
Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.309 - 314, 2000/00
no abstracts in English
Onuki, Akira; Yoshida, Hiroyuki; Akimoto, Hajime
Proceedings of ANS International Meeting on Best Estimate Methods in Nuclear Installations Safety Analysis (BE-2000) (CD-ROM), 17 Pages, 2000/00
no abstracts in English
Seki, Yasushi
New Energy Systems and Conversions, p.355 - 359, 1999/00
no abstracts in English
Onuki, Akira; Okubo, Tsutomu; Akimoto, Hajime
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Takeda, Takeshi; Kunitomi, Kazuhiko; *; *
Nucl. Eng. Des., 168, p.11 - 21, 1997/00
Times Cited Count：46 Percentile：93.78(Nuclear Science & Technology)no abstracts in English
*; *; *; *; *; Matoba, Toru
JAERI-Tech 95-041, 12 Pages, 1995/08
no abstracts in English
Shibata, Taiju
JAERI-Review 95-005, 81 Pages, 1995/03
JAERI-Review-95-005.pdf:2.53MB
no abstracts in English
Araya, Fumimasa; Iwamura, Takamichi; Okubo, Tsutomu; ; Murao, Yoshio
Nihon Genshiryoku Gakkai-Shi, 34(8), p.776 - 786, 1992/08
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
JAERI-M 90-090, 94 Pages, 1990/06
no abstracts in English
Minehara, Eisuke; *; *; *
J. Supercond., 3(3), p.277 - 280, 1990/00
no abstracts in English
; *; ; *
Nihon Genshiryoku Gakkai-Shi, 23(2), p.34 - 42, 1981/00
no abstracts in English
; ;
JAERI-M 8364, 129 Pages, 1979/08
no abstracts in English
Yoshida, Hidekazu*; Yamamoto, Koshi*; Karukaya, Koichi*; Matsui, Hiroya
no journal, ,
no abstracts in English
