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JAEA Reports

Report of summer holiday practical training 2018; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design

Ishitsuka, Etsuo; Matsunaka, Kazuaki*; Ishida, Hiroki*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Takamatsu, Kuniyoshi; Kenzhina, I.*; Chikhray, Y.*; Kondo, Atsushi*; et al.

JAEA-Technology 2019-008, 12 Pages, 2019/07

JAEA-Technology-2019-008.pdf:2.37MB

As a summer holiday practical training 2018, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out. As a result, it is become clear that the continuous operations for about 30 years at 2 MW, about 25 years at 3 MW, about 18 years at 4 MW, about 15 years at 5 MW are possible. As an image of thermal design, the image of the nuclear battery consisting a cooling system with natural convection and a power generation system with no moving equipment is proposed. Further feasibility study to confirm the feasibility of nuclear battery will be carried out in training of next fiscal year.

Journal Articles

Modeling for evaluation of debris coolability in lower plenum of reactor pressure vessel

Maruyama, Yu*; Moriyama, Kiyofumi; Nakamura, Hideo; Hirano, Masashi; Nakajima, K.*

Journal of Nuclear Science and Technology, 40(1), p.12 - 21, 2003/01

 Times Cited Count:6 Percentile:43.28(Nuclear Science & Technology)

no abstracts in English

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

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

no abstracts in English

Journal Articles

Heat transfer by natural convection in a half-sphere heated from below

;

Journal of Nuclear Science and Technology, 23(6), p.568 - 570, 1986/00

 Times Cited Count:1 Percentile:28.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core thermohydraulic design with 20% LEU fuel for upgraded research reactor,JRR-3

Sudo, Yukio; ; ;

Journal of Nuclear Science and Technology, 22(7), p.551 - 564, 1985/00

 Times Cited Count:16 Percentile:85.77(Nuclear Science & Technology)

no abstracts in English

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