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Kawasaki, Nobuchika; Hosogai, Hiromi*; Furuhashi, Ichiro*; Kasahara, Naoto
Nihon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, p.959 - 960, 2006/09
Thermal transient stress at core support structure of advanced fast reactor was evaluated using thermal hydraulic-structure total analysis method with experimental design. Maximum thermal stress is calculated 15
18% larger than nominal thermal stress by uncertainty of system parameters. Maximum thermal stress was evaluated 6368% larger than nominal thermal stress when predicted by the past deign method, therefore about 40% excessive imaginary stress could be appropriate by thermal hydraulic-structure total analysis.
Igari, Toshihide*; Takao, Nobuyuki*; Otani, Tomomi*; Shibamoto, Hiroshi; Kasahara, Naoto
Nihon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, p.957 - 958, 2006/09
no abstracts in English
Watanabe, Osamu*; Bubphachot, B.*; Kasahara, Naoto; Kawasaki, Nobuchika
Nihon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, p.117 - 118, 2006/09
This paper is to evaluate the fatigue strength for the perforated plate at elevated temperature based on Stress Redistribution Locus (SRL) method. The test specimens are made of SUS304 stainless steel, and temperature is kept to be 550
C degree, and the geometry of the perforated plate specimens are changed by number of holes and diameter size of the hole. The SRL method is used to predict number of cycle of crack initiation (Nc), and the failure (Nf) for the perforated plate.