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Takada, Shoji; Ngarayana, I. W.*; Nakatsuru, Yukihiro*; Terada, Atsuhiko; Murakami, Kenta*; Sawa, Kazuhiko*
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 13 Pages, 2019/05
In the loss of core cooling test using HTTR, a technical issue is to improve prediction accuracy of temperature distribution of components in vessel cooling system (VCS). An establishment of reasonable 2D model was started by using numerical code FLUENT, which was validated using the test data by 1/6 scale model of VCS for HTTR. The pressure vessel (PV) temperature was set around 200
C attributed to relatively high ratio of natural convection heat transfer around 20% in total heat removal, which is useful for code to experiment benchmark to improve prediction accuracy. It is necessary to confirm heat transfer flow characteristics around the top of PV which is heated up by natural convection flow which was considered to be affected by separation, re-adhesion and transition flow. The k-
-SST model was selected for turbulent calculation attributed to predict the effects mentioned above adequately. The numerical results using the k--SST model reproduced the temperature distribution of PV especially the top region which is considered to be affected by separation, re-adhesion and transition flow in contract to that using k-
model which does not account the effects.
Takada, Shoji
Nuclear Engineering and Design, 233(1-3), p.185 - 195, 2004/10
Times Cited Count：6 Percentile：40.72(Nuclear Science & Technology)Experiments are carried out to investigate the effects of the natural convection of superheated gas as well as of the stand pipes on the temperature distributions of the components and the heat removal performance in the water-cooling panel system for the MHTGR for decay heat removal, and to verify the design and evaluation methods. The numerical results of the code THANPACST2 are compared with the experimental data to verify the numerical methods and axi-symmetric model proposed, which can simulate the three-dimensional configuration of the stand pipes on the upper head of the pressure vessel by using porous body cells. The experiments revealed that temperatures increased with elevation on the upper head, because the stand pipes restrict radiation heat transfer to the upper cooling panel and reduce the heat transfer area on the upper head which was superheated by natural convection of helium gas in the pressure vessel. The numerical methods were able to closely duplicate the pattern of the rising temperature profile with elevation around the top of the upper head.
Takeda, Tetsuaki
Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.199 - 202, 2002/00
There are several methods for enhancement of heat transfer such as attaching various type fins on a channel surface of a heat exchanger tube and a steam reforming tube. The objective of this study is to clarify characteristics of heat transfer and pressure drop in the channel inserted metallic wire with high porosity. A heat transfer experiment was performed using a horizontal circular tube to obtain the heat transfer characteristics of the channel inserted copper wire. From the results obtained in this experiment, it seems to be probable that an enhancement of heat transfer method using metallic wire inserts is further improved under the high temperature conditions in efficiency as compared with the other methods.
Takada, Shoji; *; Inagaki, Yoshiyuki; Sudo, Yukio
Nihon Kikai Gakkai Rombunshu, B, 65(635), p.303 - 311, 1999/07
no abstracts in English
Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio
Nihon Kikai Gakkai Rombunshu, B, 65(633), p.248 - 254, 1999/05
no abstracts in English
Takada, Shoji; Shiina, Yasuaki; Inagaki, Yoshiyuki; Hishida, Makoto*; Sudo, Yukio
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 1, p.323 - 332, 1997/00
no abstracts in English
Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio
Nihon Kikai Gakkai Rombunshu, B, 62(600), p.3109 - 3117, 1996/00
no abstracts in English
Takada, Shoji; Shiina, Yasuaki; Inagaki, Yoshiyuki; Hishida, Makoto; Sudo, Yukio
JAERI-Research 95-056, 40 Pages, 1995/08
JAERI-Research-95-056.pdf:1.17MB
no abstracts in English
Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio
JAERI-Research 95-049, 36 Pages, 1995/07
JAERI-Research-95-049.pdf:1.18MB
no abstracts in English
) of the helium engineering demonstration loop (HENDEL)Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Ioka, Ikuo; Sudo, Yukio
JAERI-Research 95-048, 41 Pages, 1995/07
JAERI-Research-95-048.pdf:1.22MB
no abstracts in English
): THANPACST2Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Ioka, Ikuo
JAERI-Data/Code 95-005, 203 Pages, 1995/06
JAERI-Data-Code-95-005.pdf:4.7MB
no abstracts in English
