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Journal Articles

Research and development on passive cooling system

Takada, Shoji

Nuclear Engineering and Design, 233(1-3), p.185 - 195, 2004/10

 Times Cited Count:6 Percentile:40.63(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.

Journal Articles

Analysis for performance of passive heat removal by a water cooling panel from a high-temperature gas-cooled reactor

Takada, Shoji; *; Inagaki, Yoshiyuki; Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 65(635), p.303 - 311, 1999/07

no abstracts in English

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

Journal Articles

Design and evaluation methods of a water cooling panel system for decay heat removal from a high-temperature gas-cooled reactor

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

Nihon Kikai Gakkai Rombunshu, B, 62(600), p.3109 - 3117, 1996/00

no abstracts in English

JAEA Reports

Benchmark problem for IAEA coordinated research program (CRP-3) on GCR afterheat removal, I

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

JAEA Reports

Study on the cooling characteristics of the water cooling panel system; Pressure vessel without stand pipes

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

Journal Articles

Cooling peformance of a water-cooling panel system for modular high-temperature gas-cooled reactors

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

Transactions of the American Nuclear Society, 73, p.477 - 478, 1995/00

no abstracts in English

Journal Articles

Cooling performance of cooling panel system of modular high temperature gas cooled reactor

Takada, Shoji; Inagaki, Yoshiyuki;

Doryoku, Enerugi Gijutsu No Saizensen : Shimpojiumu Koen Rombunshu 1994, 0, p.317 - 322, 1994/00

no abstracts in English

Journal Articles

Cooling performance of cooling panel in modular HTGR

Takada, Shoji; Inagaki, Yoshiyuki; Suzuki, Kunihiro; ; Wada, Hozumi*; *

Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants, p.P1.2-1 - P1.2-7, 1993/00

no abstracts in English

JAEA Reports

Test apparatus for ITER blanket cooling water distributor design

Yoshida, Hiroshi; Enoeda, Mikio; Hirata, Shingo*; Ito, H.*

JAERI-M 92-070, 45 Pages, 1992/05

JAERI-M-92-070.pdf:1.34MB

no abstracts in English

Journal Articles

Visualization of natural convection outside of VHTR pressure vessel model using thermo sensitive liquid crystal suspension

Akino, Norio; ; Seki, Masahiro; ; Okamoto, Yoshizo

Nagare No Kashika Shashinshu, p.34 - 35, 1986/00

no abstracts in English

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