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Wang, Z.; Duan, G.*; Matsunaga, Takuya*; Sugiyama, Tomoyuki
International Journal of Heat and Mass Transfer, 157, p.119919_1 - 119919_20, 2020/08
Times Cited Count：6 Percentile：67.73(Thermodynamics)Takada, Shoji; Ngarayana, I. W.*; Nakatsuru, Yukihiro*; Terada, Atsuhiko; Murakami, Kenta*; Sawa, Kazuhiro*
Mechanical Engineering Journal (Internet), 7(3), p.19-00536_1 - 19-00536_12, 2020/06
In this study reasonable 2D model was established by using FLUENT for start-up of analysis and evaluation of heat transfer flow characteristics in 1/6 scale model of VCS for HTTR. By setting up pressure vessel temperature around 200
C about relatively high ratio of heat transfer via natural convection in total heat removal around 20-30%, which is useful for code to experiment benchmark in the aspect to confirm accuracy to predict temperature distribution of components which is heated up by natural convection flow. The numerical results of upper head of pressure vessel by the 
-
-SST intermittency transition model, which can adequately reproduce the separation, re-adhesion and transition, reproduced the test results including temperature distribution well in contrast to those by the -
model in both cases that helium gas is evacuated or filled in the pressure vessel. It was emerged that any local hot spot did not appear on the top of upper head of pressure vessel where natural convection flow of air is separated in both cases. In addition, the plume of high temperature helium gas generated by the heating of heater was well mixed in the upper head and uniformly heated the inner surface of upper head without generating hot spots.
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.
Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*
Annals of Nuclear Energy, 96, p.137 - 147, 2016/10
Times Cited Count：5 Percentile：49.98(Nuclear Science & Technology)After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Specifically, emergency power generators are not necessary and the decay heat can be passively removed for a long time, even forever if the heat removal capacity of the RCCS is sufficient. We can also define the experimental conditions on radiation and natural convection for the scale-down heat removal test facility.
Inaba, Yoshitomo; Zhang, Y.*; Takeda, Tetsuaki; Shiina, Yasuaki
Heat Transfer-Asian Research, 34(5), p.293 - 308, 2005/07
Water cooling panels have been adopted as the vessel cooling system of the HTTR to cool the reactor core indirectly by natural convection and thermal radiation. In order to investigate the heat transfer characteristics of high temperature gas in a vertical annular space between the reactor pressure vessel and cooling panels of the HTTR, we carried out experiments and numerical analyses on natural convection heat transfer coupled with thermal radiation heat transfer in an annulus between two vertical concentric cylinders with the inner cylinder heated and the outer cylinder cooled. In the present experiments, Rayleigh number based on the height of the annulus ranged from 2.0
10
to 5.410 for helium gas and from 1.210
to 3.510 for nitrogen gas. The numerical results were in good agreement with the experimental ones regarding the surface temperatures of the heating and cooling walls. As a result of the experiments and the numerical analyses, the heat transfer coefficient of natural convection coupled with thermal radiation was obtained.
Fumizawa, Motoo; Tanaka, Gaku*; Zhao, H.*; Hishida, Makoto*; Shiina, Yasuaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.313 - 322, 2004/12
This paper deals with a computer simulation of a helium-air counter flow in a rectangular channel. The inclination angle is varied from 0(horizontal) to 90(vertical). Velocity profiles and concentration profiles are calculated with a computer program VSOP sub-module. Following main features of the counter flow are discussed. (1) Time required to establish a quasi-steady state counter flow. (2) The relationship between the inclination angle and the flow patterns of the counter flow (3) The developing process of velocity profiles and concentration profiles (4) The relationship between the inclination angle of the channel and the velocity profiles of upwards flow and the downwards flow (5) The relationship between the concentration profile and the inclination angle (6) The relationship between the net in-flow rate and the inclination angle We compared the computed velocity profile and the net in-flow rate with experimental data. A good agreement is obtained between the calculation and the experiment.
Inaba, Yoshitomo; Zhang, Y.*; Takeda, Tetsuaki; Shiina, Yasuaki
Nihon Kikai Gakkai Rombunshu, B, 70(694), p.1518 - 1525, 2004/06
no abstracts in English
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：42.72(Nuclear Science & Technology)no abstracts in English
Inaba, Yoshitomo; Takeda, Tetsuaki
JAERI-Research 2000-062, 73 Pages, 2001/02
JAERI-Research-2000-062.pdf:2.83MB
no abstracts in English
Maruyama, Yu; Moriyama, Kiyofumi; Nakamura, Hideo; Hashimoto, Kazuichiro; Hirano, Masashi; Nakajima, K.*
Proceedings of RASPLAV Seminar 2000 (CD-ROM), 8 Pages, 2000/11
no abstracts in English
Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka*; Mishima, Kaichiro*; Hibiki, Takashi*
Nuclear Technology, 125(2), p.213 - 224, 1999/02
Times Cited Count：8 Percentile：54.48(Nuclear Science & Technology)no abstracts in English
Kubo, Shinji; Akino, Norio; *; *
Nihon Kikai Gakkai Rombunshu, B, 64(625), p.3013 - 3020, 1998/09
no abstracts in English
Takase, Kazuyuki; Kunugi, Tomoaki; ; Seki, Yasushi
Fusion Engineering and Design, 42, p.83 - 88, 1998/00
Times Cited Count：12 Percentile：69.6(Nuclear Science & Technology)no abstracts in English
Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio
Heat Transfer-Jpn. Res., 26(3), p.159 - 175, 1997/00
no abstracts in English
*; *; Kubo, Shinji; Akino, Norio; *; Takase, Kazuyuki
Kashika Joho Gakkai-Shi, 18(68), p.1 - 8, 1997/00
no abstracts in English
Maruyama, Yu; Igarashi, Minoru; Nakamura, Naohiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun; Nakajima, Kengo*
JAERI-memo 08-127, p.233 - 238, 1996/06
no abstracts in English
Akino, Norio; Kubo, Shinji; K.-S.Choi*
Proc. of ASME Fluid Engineering Division Summer Meeting 1996 (FED-Vol. 239), 4, p.439 - 445, 1996/00
no abstracts in English
Kaminaga, Masanori
RIST News, (21), p.42 - 47, 1996/00
no abstracts in English
*; Kunugi, Tomoaki; *
Therm. Sci. Eng., 4(3), p.17 - 25, 1996/00
no abstracts in English
Sugimoto, Jun; Uetsuka, Hiroshi; Hidaka, Akihide; Maruyama, Yu; Yamano, N.; Hashimoto, Kazuichiro
Thermophysical Properties 17 (17th Japan Symp. 1996), 0, p.163 - 166, 1996/00
no abstracts in English
