Research and development on passive cooling system

Takada, Shoji

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

https://doi.org/10.1016/j.nucengdes.2004.08.008

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.

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

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

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

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

Thermal analysis code for test of passive cooling system by helium engineering demonstration loop (HENDEL) in-core structure test section (T): THANPACST2

Takada, 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