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

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JAEA Reports

Study on natural convection heat transfer in vertical annular space of a double coaxial cylinder

Inaba, Yoshitomo; Takeda, Tetsuaki

JAERI-Research 2000-062, 73 Pages, 2001/02

JAERI-Research-2000-062.pdf:2.83MB

no abstracts in English

Journal Articles

Neutron streaming evaluation for the DREAM fusion power reactor

Seki, Yasushi; Mori, Seiji*; Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi

Journal of Nuclear Science and Technology, 37(Suppl.1), p.268 - 275, 2000/03

https://doi.org/10.1080/00223131.2000.10874888

no abstracts in English

Journal Articles

Design and evaluation methods for a water cooling panel system for decay heat removal from a high-temperature gas-cooled reactor

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio

Heat Transfer-Jpn. Res., 26(3), p.159 - 175, 1997/00

https://doi.org/10.1002/(SICI)1520-6556(1997)26:3<159::AID-HTJ2>3.0.CO;2-V

no abstracts in English

JAEA Reports

Electron beam irradiation experiments of first wall mock-ups for fusion experimental reactors, I

; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; Ise, Hideo*;

JAERI-M 91-085, 20 Pages, 1991/05

JAERI-M-91-085.pdf:0.98MB

no abstracts in English

Journal Articles

Effect of cooling conditions on fuel failure during fast and slow power transients

Sobajima, Makoto; Katanishi, Shoji

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.249 - 254, 1991/00

no abstracts in English

JAEA Reports

Radiation Loss and Global Energy Balance of Ohmically Heated Divertor Discharge in JT-60 Tokamak

; *; Yoshida, H.; Nakamura, H.; *;

JAERI-M 86-056, 13 Pages, 1986/03

JAERI-M-86-056.pdf:0.5MB

no abstracts in English

Journal Articles

Irradiation test of medium enriched uranium fuel elements in Japan Materials Testing Reactor; Confirmation of integrity of fuel elements by measurement of fission products in water

Yamamoto, Katsumune; ; ; Yokouchi, Iichiro; ;

Nihon Genshiryoku Gakkai-Shi, 28(5), p.425 - 427, 1986/00

https://doi.org/10.3327/jaesj.28.425

Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of detailed temperature analysis model for a scale model of HTGR vessel cooling system

Teramachi, Yuhei*; Sawa, Kazuhiro*; Ishitsuka, Etsuo; Ho, H. Q.

no journal, ,