Establishment of numerical model to investigate heat transfer and flow characteristics by using scale model of vessel cooling system for HTTR

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 200C 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.

Preliminary numerical investigation of turbulence behavior in a spallation target

Takase, Kazuyuki; Kitamura, Tatsuaki*; Kume, Etsuo; Ichimiya, Koichi*; Komada, Ichiro*

Nihon Kikai Gakkai Kanto Shibu Yamanashi Koenkai (2003) Koen Rombunshu, No.030-4, p.77 - 78, 2003/00

no abstracts in English

Impinging jet experiments and analyses for a cold moderator vessel design

Aso, Tomokazu; Terada, Atsuhiko*; Kaminaga, Masanori; Hino, Ryutaro

Kashika Joho Gakkai-Shi, 21(Suppl.2), p.119 - 122, 2001/09

no abstracts in English

Three-dimensional numerical simulations of dust mobilization and air ingress characteristics in a fusion reactor during a LOVA event

Takase, Kazuyuki

Fusion Engineering and Design, 54(3-4), p.605 - 615, 2001/04

https://doi.org/10.1016/S0920-3796(00)00573-1

no abstracts in English

Three-dimensional numerical simulations of heat transfer in an annular fuel channel with periodic spacer ribs under a fully developed turbulent flow

Takase, Kazuyuki

Nuclear Technology, 118(2), p.175 - 185, 1997/05

https://doi.org/10.13182/NT97-A35377

no abstracts in English

Experimental and theoretical investigations on heat transfer of strongly heated turbulent gas flow in an annular duct

Fujii, Sadao*; Akino, Norio; Hishida, Makoto; *; Sanokawa, Konomo

JSME Int. J., Ser. 2, 34(3), p.348 - 354, 1991/00

no abstracts in English

A numerical analysis on heat transfer and fluid dynamics used 3 dimensional analysis code STREAM

Genshiro Niokeru Netsu Ryudo Suchi Kaiseki No Genjo, II, p.167 - 180, 1987/00

no abstracts in English