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Journal Articles

Development of numerical simulation method to evaluate heat transfer performance of air around fuel debris, 2; Validation of JUPITER for free convection heat transfer

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

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 7 Pages, 2017/07

Journal Articles

Performance of passive heat removal by an air cooling panel from a high-temperature gas-cooled reactor

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 65(633), p.248 - 254, 1999/05

no abstracts in English

Journal Articles

Study on cooling performance of air-cooling panel system for HTGR

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Sudo, Yukio

Transactions of the American Nuclear Society, 79, p.160 - 161, 1998/00

no abstracts in English

Journal Articles

Benchmark problem for International Atomic Energy Agency (IAEA) Coordinated Research Program (CRP) on Gas-Cooled Reactor (GCR) afterheat removal

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

JAEA Reports

Study of air vent design for inverted U-tube type heat exchanger

Takada, Shoji; Shibata, Mitsuhiko; ; Fujisaki, Katsuo; Ota, Yukimaru; ;

JAERI-M 94-013, 89 Pages, 1994/02

JAERI-M-94-013.pdf:2.77MB

no abstracts in English

Oral presentation

Development of numerical simulation method to evaluate heat transfer of fuel debris in air cooling, 3; Validation of porous model in JUPITER for forced convection

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

no journal, , 

To estimate the heat transfer of fuel debris in the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Station, JAEA has developed a numerical simulation method with JUPITER. In the previous report, JUPITER underestimated the heat transfer of a porous body in comparison with a natural convective heat transfer experiment. In this report, we report a forced convection experiment with a porous body in a rectangular tube for the validation of flow. As a result, the measured differential pressure of the porous body was in good agreement with the simulation result, and the same velocity distributions as the experiment were obtained with JUPITER. Therefore, the numerical simulation method is correct for the flow with a porous body.

Oral presentation

Development of numerical simulation method to evaluate heat transfer of fuel debris in air cooling, 4; Application of effective thermal conductivity models of porous medium

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

no journal, , 

To evaluate the heat transfer of fuel debris in the primary containment vessel of the Fukushima Daiichi Nuclear Power Station, JAEA has developed a numerical simulation method with JUPITER. The previous work reported that JUPITER was appropriate for flow analysis of a porous medium. In this report, we report experimental and numerical results for natural convection in a system containing the porous medium to validate effective thermal conductivity models of the porous medium in JUPITER. The comparison result indicated that the use of a geometric mean model rather than a series model and a parallel model as an effective thermal conductivity model is appropriate for the natural convective heat transfer analysis in the systems containing the porous medium.

Oral presentation

Numerical simulation for cooling by natural convection in a closed space containing porous materials

Ito, Koki*; Sano, Yoshihiko*; Kuwahara, Fujio*; Uesawa, Shinichiro; Yoshida, Hiroyuki

no journal, , 

To estimate the thermal behavior of fuel debris in the primary containment vessel of the Fukushima Daiichi Nuclear Power Station, we have developed a numerical simulation method for analyzing the thermal behavior of fuel debris during air cooling. Since fuel debris is assumed to be a porous material, by using a porous medium model, the numerical simulation was conducted to simulate the natural convection in a closed vessel with porous materials. The simulation was validated by comparing it with the experiment in JAEA.

Oral presentation

Development of numerical simulation method to evaluate heat transfer of fuel debris in air cooling, 5; Preliminary analysis of thermal behavior in PCV

Uesawa, Shinichiro; Ono, Ayako; Yamashita, Susumu; Yoshida, Hiroyuki

no journal, , 

To evaluate the thermal behavior of fuel debris in PCVs of TEPCO's Fukushima Daiichi Nuclear Power Station for air cooling, JAEA has developed a numerical simulation method with JUPITER. The previous work reported JUPITER with a porous medium model was capable to calculate thermal behavior of a porous medium. In this report, we report the result of the preliminary numerical analysis of thermal behavior in the PCV of Fukushima Daiichi Nuclear Power Station Unit 2. The numerical result showed air in the RPV and the pedestal was heated with fuel debris, and natural convection was generated. Therefore, the numerical simulation method is expected to evaluate the thermal behavior in the PCV for air cooling.

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