JOPSS - Search Results

Search Results: Records 1-8 displayed on this page of 8

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Journal Articles

Numerical analysis on ingress of coolant event in vacuum vessel using modified TRAC-BF1

Kurihara, Ryoichi; Ajima, Toshio*; Ueda, Shuzo; Seki, Yasushi

Journal of Nuclear Science and Technology, 38(7), p.571 - 576, 2001/07

https://doi.org/10.3327/jnst.38.571

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Physics design of advanced steady-state tokamak reactor A-SSTR 2

Nishio, Satoshi; Ushigusa, Kenkichi; Ueda, Shuzo; Polevoi, A.*; Kurita, Genichi; Tobita, Kenji; Kurihara, Ryoichi; Hu, G.; Okada, Hidetoshi*; Murakami, Yoshiki*; et al.

JAERI-Research 2000-029, 105 Pages, 2000/10

JAERI-Research-2000-029.pdf:4.19MB

no abstracts in English

Journal Articles

Control of fusion power in a steady-state tokamak reactor

Kurihara, Ryoichi; Nishio, Satoshi; Ueda, Shuzo; Polevoi, A. R.; Aoki, Isao; Ajima, Toshio*; Okada, Hidetoshi*; Hasegawa, Mitsuru*; Ushigusa, Kenkichi

Journal of Plasma and Fusion Research SERIES, Vol.3, p.553 - 557, 2000/00

no abstracts in English

JAEA Reports

Analysis for ingress of coolant event in vacuum vessel using modified TRAC-BF1 code

Ajima, Toshio*; Kurihara, Ryoichi; Seki, Yasushi

JAERI-Data/Code 99-040, 84 Pages, 1999/08

JAERI-Data-Code-99-040.pdf:2.75MB

no abstracts in English

Journal Articles

Safety scenario and integrated thermofluid test

Seki, Yasushi; Kurihara, Ryoichi; Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko

Fusion Engineering and Design, 42(1-4), p.37 - 44, 1998/09

https://doi.org/10.1016/S0920-3796(98)00123-9

Times Cited Count：1 Percentile：15.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis and experimental results on ingress of coolant event in vacuum vessel

Kurihara, Ryoichi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko; Seki, Yasushi; *; Yamauchi, Michinori*; *; *

Fusion Engineering and Design, 42, p.61 - 66, 1998/00

https://doi.org/10.1016/S0920-3796(97)00182-8

Times Cited Count：7 Percentile：53.8(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Improvement of TRAC-BF1 code to analyze the ingress of coolant event (ICE)

Ajima, Toshio*; Kurihara, Ryoichi; Seki, Yasushi; *; Yamauchi, Michinori*

JAERI-Data/Code 97-034, 77 Pages, 1997/08

JAERI-Data-Code-97-034.pdf:1.71MB

no abstracts in English

Journal Articles

Proposal of integrated test facility for in-vessel thermofluid safety of fusion reactors

Kurihara, Ryoichi; Seki, Yasushi; Ueda, Shuzo; Aoki, Isao; Nishio, Satoshi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Yamauchi, Michinori*; *; et al.

Journal of Fusion Energy, 16(3), p.225 - 230, 1997/00

https://doi.org/10.1023/A:1021895304522

Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)

no abstracts in English