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Tanaka, Masaaki; Doda, Norihiro; Yokoyama, Kenji; Mori, Takero; Okajima, Satoshi; Hashidate, Ryuta; Yada, Hiroki; Oki, Shigeo; Miyazaki, Masashi; Takaya, Shigeru
Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/07
To assist conceptual studies of various reactor systems conducted by private sectors in nuclear power innovation, development of an innovative design system named ARKADIA (Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle) is undergoing to achieve the design of an advanced nuclear reactor as a safe, economic, and sustainable carbon-free energy source. In this paper, focusing on the ARKADIA-Design as a part of it, the progress in the development of optimization processes on the representative problems in the fields of the core design, the plant structure design, and the maintenance schedule planning are introduced.
Watanabe, Sota*; Kubo, Koji*; Okajima, Satoshi; Wakai, Takashi
Nihon Kikai Gakkai M&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), p.581 - 585, 2017/10
no abstracts in English
Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.
Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12
Times Cited Count：101 Percentile：93.45(Physics, Fluids & Plasmas)no abstracts in English
Kogawa, Hiroyuki; Ishikura, Shuichi*; Hino, Ryutaro; Kato, Takashi; Aso, Tomokazu; Sato, Hiroshi; Harada, Masahide; Kai, Tetsuya; Teshigawara, Makoto; Maekawa, Fujio; et al.
Proceedings of ICANS-XVI, Volume 2, p.635 - 644, 2003/07
no abstracts in English
Teraoku, Takuji*; Terada, Atsuhiko*; Maekawa, Fujio; Meigo, Shinichiro; Kaminaga, Masanori; Ishikura, Shuichi*; Hino, Ryutaro
JAERI-Tech 2003-026, 77 Pages, 2003/03
JAERI-Tech-2003-026.pdf:19.78MB
A 1-MW spallation neutron source aiming at materials and life science researches will be constructed under the JAERI-KEK Proton Accelerator Project(J-PARC). The proton beam window functions as a boundary wall between a high vacuum area and a helium atmosphere and it is cooled by light water because high heat-density is generated in the window material by interactions with the proton beam. Then, uniformity of the water flow is requested at the window to suppress a hot-spot that causes excessive thermal stress and cooling water boiling. Also, the window has to be strong enough in its structure for inner stress due to water pressure and thermal stress due to heat generation. In this report, we propose two types of proton beam windows, flat-type and curved-type. We evaluated the strength of structure and thermal hydraulic analysis. As a result, it was found that sufficient heat removal was assured with uniform water flow at the window, and the stress could be maintained below allowable stress values. Accordingly, it was confirmed that the proton beam window designs were feasible.
Ohira, Shigeru; Tada, Eisuke; Hada, Kazuhiko; Neyatani, Yuzuru; Maruo, Takeshi; Hashimoto, Masayoshi*; Araki, Takao*; Nomoto, Kazuhiro*; Tsuru, Daigo; Ishida, Toshikatsu*; et al.
Fusion Engineering and Design, 54(3-4), p.515 - 522, 2001/04
Times Cited Count：3 Percentile：27.1(Nuclear Science & Technology)no abstracts in English
Federation of Electric Power Companies of Japan*
JNC TY1400 2000-001, 464 Pages, 2000/03
JNC-TY1400-2000-001.pdf:16.87MB
None
*; *; Tanai, Kenji
JNC TN8400 99-047, 54 Pages, 1999/11
This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.
Takizuka, Takakazu; Tsujimoto, Kazufumi; Sasa, Toshinobu; Takano, Hideki
Proceedings of the 3rd International Conference on Accelerator Driven Transmutation Technologies and Applications (CD-ROM), 12 Pages, 1999/06
no abstracts in English
Sakurai, Shinji; Hosogane, Nobuyuki; Masaki, Kei; ; ; *; *; Shimizu, Katsuhiro; Akino, Noboru; Miyo, Yasuhiko; et al.
Fusion Engineering and Design, 39-40, p.371 - 376, 1998/00
Times Cited Count：5 Percentile：44.27(Nuclear Science & Technology)no abstracts in English
Ishikura, Shuichi*; Kikuchi, Kenji; Futakawa, Masatoshi; Hino, Ryutaro
JAERI-Tech 97-037, 36 Pages, 1997/08
no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni
23nd Biennial Conference on Carbon (CARBON '97) Extended Abstracts and Program, Vol,2, p.232 - 233, 1997/00
no abstracts in English
Miya, Kenzo*; ; Takatsu, Hideyuki; Hada, Kazuhiko; Koizumi, Koichi; Jitsukawa, Shiro; ; Okawa, Yoshinao; Shimakawa, T.*; Aoto, Kazumi*; et al.
Fusion Engineering and Design, 31, p.145 - 165, 1996/00
Times Cited Count：3 Percentile：32.72(Nuclear Science & Technology)no abstracts in English
Sakurai, Shinji; Hosogane, Nobuyuki; ; Masaki, Kei; ; *; *; Takahashi, Shoryu*; Saido, Masahiro; Inoue, Masahiko*; et al.
Fusion Technology 1996, 0, 4 Pages, 1996/00
no abstracts in English
Miya, Kenzo*; ; Takatsu, Hideyuki
Kikai No Kenkyu, 47(1), p.179 - 184, 1995/00
no abstracts in English
Tsuji, Hirokazu; *; *; Nakajima, Hajime
Journal of Nuclear Science and Technology, 31(4), p.274 - 278, 1994/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *
Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00
no abstracts in English
Tsuji, Hirokazu; *; Nakanishi, Tsuneo*; *; Nakajima, Hajime
JAERI-M 93-209, 64 Pages, 1993/10
no abstracts in English
Tsuji, Hirokazu; *; *; Nakajima, Hajime
JAERI-M 93-144, 69 Pages, 1993/07
no abstracts in English
