Development of numerical simulation method of natural convection around heated porous medium by using JUPITER

Uesawa, Shinichiro; Yamashita, Susumu; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9 Pages, 2023/05

For contaminated water management in decommissioning Fukushima Daiichi Nuclear Power Stations, reduction in water injection, intermittent injection water and air cooling are considered. However, since there are uncertainties of fuel debris in the PCV, it is necessary to examine and evaluate optimal cooling methods according to the distribution state of the fuel debris and the progress of the fuel debris retrieval work in advance. We have developed a method for estimating the thermal behavior in the air cooling, including the influence of the position, heat generation and the porosity of fuel debris. Since a large-scale thermal-hydraulics analysis of natural convection is necessary for the method, JUPITER developed independently by JAEA is used. It is however difficult to perform the large-scale thermal-hydraulics analysis with JUPITER by modeling the internal structure of the debris which may consist of a porous medium. Therefore, it is possible to analyze the heat transfer of the porous medium by adding porous models to JUPITER. In this study, we report the validation of JUPITER applied the porous model and discuss which heat transfer models are most effective in porous models such as series, parallel and geometric mean models. To obtain validation data of JUPITER for the natural convective heat transfer analysis around the porous medium, we performed the heat transfer and the flow visualization experiments of the natural convection in the experimental system including the porous medium. In the comparison between the experiment and the numerical analysis with each model, the numerical result with the geometric mean model was the closest of the models to the experimental results. However, the numerical results of the temperature and the velocity were overestimated for those experimental results. In particular, the temperature near the interface between the porous medium and air was more overestimated.

Numerical analysis of natural convection behavior in density stratification induced by external cooling of a containment vessel

Ishigaki, Masahiro*; Abe, Satoshi; Hamdani, A.; Hirose, Yoshiyasu

Annals of Nuclear Energy, 168, p.108867_1 - 108867_20, 2022/04

https://doi.org/10.1016/j.anucene.2021.108867

Establishment of reasonable 2-D 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, Kazuhiro*

Mechanical Engineering Journal (Internet), 7(3), p.19-00536_1 - 19-00536_12, 2020/06

https://doi.org/10.1299/mej.19-00536

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 200C 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.

New reactor cavity cooling system (RCCS) with passive safety features; A Comparative methodology between a real RCCS and a scaled-down heat-removal test facility

Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*

Annals of Nuclear Energy, 96, p.137 - 147, 2016/10

https://doi.org/10.1016/j.anucene.2016.05.012

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.

Helium-air counter flow in rectangular channels

Fumizawa, Motoo; Tanaka, Gaku*; Zhao, H.*; Hishida, Makoto*; Shiina, Yasuaki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.313 - 322, 2004/12

https://doi.org/10.3327/taesj2002.3.313

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.

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

https://doi.org/10.3327/jnst.40.12

no abstracts in English

Validation of CAMP code for thermo-fluiddynamics of molten debris in lower Plenum

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

Natural convection heat transfer from a heated horizontal cylinder with microencapsulated phase-change-material slurries

Kubo, Shinji; Akino, Norio; *; *

Nihon Kikai Gakkai Rombunshu, B, 64(625), p.3013 - 3020, 1998/09

https://doi.org/10.1299/kikaib.64.3013

no abstracts in English

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

Three-dimensional analysis on thermo-fluiddynamics in piping with WINDFLOW

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