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Katsuyama, Jinya; Yamaguchi, Yoshihito; Nemoto, Yoshiyuki; Furuta, Takuya; Kaji, Yoshiyuki
Proceedings of ASME 2022 Pressure Vessels and Piping Conference (PVP 2022) (Internet), 9 Pages, 2022/07
Katsuyama, Jinya; Uno, Shumpei*; Watanabe, Tadashi*; Li, Y.
Frontiers of Mechanical Engineering, 13(4), p.563 - 570, 2018/12
Times Cited Count：2 Percentile：12.01(Engineering, Mechanical)For the structural integrity assessments on reactor pressure vessels (RPVs) under pressurized thermal shock (PTS) events, thermal hydraulic (TH) behavior of coolant water is one of the most important influence factors. Configuration of plant equipment and their dimensions, and operator action have large influences on TH behavior. In this study, to investigate the influence of operator action on TH behavior during a PTS event, we developed an analysis model for a typical Japanese plant, and performed TH and structural analyses. Two different operator action times were assumed based on the Japanese and US' rules. From the analysis results, it was clarified that differences in operator action times have a significant effect on TH behavior and loading conditions, that is, following the Japanese rule may lead to lower stresses compared to that when following the US rule because earlier operator action caused lower pressure in the RPV.
Sato, Takeshi; Tamaki, Hitoshi
JAERI-Data/Code 2000-009, p.120 - 0, 2000/02
JAERI-Data-Code-2000-009.pdf:5.06MB
no abstracts in English
*; Watanabe, Norio; Hirano, Masashi
JAERI-Data/Code 98-037, 193 Pages, 1998/11
JAERI-Data-Code-98-037.pdf:6.14MB
no abstracts in English
Hirano, Masashi; J.Sun*
JAERI-M 92-060, 61 Pages, 1992/04
no abstracts in English
Hirano, Masashi; Watanabe, Tadashi
Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5,Vol. 1, p.165 - 173, 1992/00
no abstracts in English
; ; *
Journal of Nuclear Science and Technology, 23(9), p.779 - 793, 1986/00
Times Cited Count：4 Percentile：48.02(Nuclear Science & Technology)no abstracts in English
Sudo, Yukio; ; Hirano, Masashi;
JAERI-M 84-066, 74 Pages, 1984/03
no abstracts in English
Tanigawa, Hisashi; Nakamura, Makoto; Someya, Yoji; Masui, Akihiro; Watanabe, Kazuhito
no journal, ,
Blanket in fusion nuclear reactor has three functions such as neutron shielding, heat recovery and tritium breeding. The blanket in ITER is called as Shielding blanket because it has only a function of neutron shielding. The blanket with heat recovery and tritium breeding functions will be equipped with fusion DEMO reactor for the first time. Therefore it is important to study event sequences and their effects related to the blanket for understandings of safety characteristics in DEMO plants. For both of ITER and DEMO, it is the same that a vacuum vessel is treated as the first container against radioactive materials. Safety-related events including in-vessel LOCA and in-box LOCA are analyzed and their effects on the vacuum vessel are assessed.
Katsuyama, Jinya; Uno, Shumpei; Li, Y.
no journal, ,
no abstracts in English
Tamaki, Hitoshi; Zheng, X.; Tanaka, Yoichi; Kubo, Kotaro; Sugiyama, Tomoyuki; Maruyama, Yu
no journal, ,
no abstracts in English
Tanaka, Yoichi; Zheng, X.; Tamaki, Hitoshi; Sugiyama, Tomoyuki
no journal, ,
no abstracts in English
