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Fujimoto, Nozomu; Tachibana, Yukio; Saikusa, Akio*; Shinozaki, Masayuki; Isozaki, Minoru; Iyoku, Tatsuo
Nuclear Engineering and Design, 233(1-3), p.273 - 281, 2004/10
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)From a viewpoint of heat leakage, there were two incidents during HTTR power-rise-tests. One was a temperature rise of the primary upper shielding, and the other was a temperature rise of the core support plate. Causes of the both incidents were small amount of helium flow in structures. For the temperature rise of the primary upper shielding, countermeasures to reduce the small amount of helium flow, enhancement of heat release and installation of thermal insulator were taken. For the temperature rise of the core support plate, temperature evaluations were carried out again considering the small amount of helium flow and design temperature of the core support plate was revised. By these countermeasures, the both temperatures were kept below their limits.
Sumita, Junya; Ishihara, Masahiro; Nakagawa, Shigeaki; Kikuchi, Takayuki; Iyoku, Tatsuo
Nuclear Engineering and Design, 233(1-3), p.81 - 88, 2004/10
Times Cited Count：6 Percentile：39.72(Nuclear Science & Technology)A High Temperature Gas-cooled Reactor is particularly attractive due to its capability of producing high temperature helium gas and its possibility to exploit inherent safety characteristic. To achieve high temperature helium-gas, reactor internals are made of graphite and heat resistant materials, its surroundings are composed of metals. The reactor internals of the HTTR consist of graphite and metallic core support structures and shielding blocks. This paper describes the reactor internal design of the HTTR, especially the core support graphite structures, and the program of an in-service inspection.
Sumita, Junya; Hanawa, Satoshi; Kikuchi, Takayuki; Ishihara, Masahiro
JAERI-Tech 2003-023, 37 Pages, 2003/03
JAERI-Tech-2003-023.pdf:7.79MB
Visual inspection of core support graphite structures using TV camera as in-service inspection and measurement of material characteristics using surveillance test specimens are planned in the High Temperature Engineering Test Reactor (HTTR) to confirm structural integrity of the core support graphite structures. For the visual inspection, in-service inspection system has been developed, and pre-service inspection using the system was carried out. As the result of the pre-service inspection, it was validated that high quality of visual inspection with TV camera can be carried out, and also structural integrity of the core support graphite structures at the initial stage of the HTTR operation was confirmed.
Motoki, Yasuo; Hada, Kazuhiko; ; Baba, Osamu
JAERI-M 91-056, 44 Pages, 1991/03
no abstracts in English
Inagaki, Yoshiyuki; Fujimoto, Nozomu; Motoki, Yasuo; Iyoku, Tatsuo; Maruyama, So; Shiozawa, Shusaku
JAERI-M 90-223, 30 Pages, 1990/12
no abstracts in English
Inagaki, Yoshiyuki; Iyoku, Tatsuo; ; ; Shiozawa, Shusaku
JAERI-M 90-020, 70 Pages, 1990/02
no abstracts in English
