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Katsuyama, Jinya; Uno, Shumpei*; Watanabe, Tadashi*; Li, Y.
Frontiers of Mechanical Engineering, 13(4), p.563 - 570, 2018/12
Times Cited Count：2 Percentile：12.21(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.
Morisaki, Norihiro; Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo*; Maeda, Yukimasa; Mizuno, Sadao*
JAERI-Tech 2005-009, 37 Pages, 2005/03
JAERI-Tech-2005-009.pdf:14.33MB
The breakage of the catalyst dust filter was found at the nozzle flange, which was welded onto the end plate of the filter, by the bubbling test using nitrogen gas of the mock-up model test facility. We investigated the cause of breakage and devised a repairing method. The cause of the breakage was the stress corrosion cracking (SCC) generated from the inside of the filter. The filter was repaired based on the following countermeasures such as reduction of condensed water in the filter, tensile stress and sensitization at welding joints. Furthermore, the inspection was carried out to investigate the structural integrity of the welding joints in the test facility of which structure, material and operating condition were similar to the filter. As the results, it was confirmed that the structural integrity was maintained.
Nishiyama, Yutaka; Onizawa, Kunio; Idei, Yoshio; Suzuki, Masahide
JAERI-Research 2000-047, 32 Pages, 2000/10
JAERI-Research-2000-047.pdf:1.69MB
no abstracts in English
Katsuyama, Jinya
no journal, ,
no abstracts in English
Katsuyama, Jinya; Miyamoto, Yuhei*; Yamaguchi, Yoshihito; Mano, Akihiro; Li, Y.
no journal, ,
Weld residual stress (WRS) is one of the most important factors with a great deal of uncertainty, which is considered as a driving force for crack growth in the structural integrity assessment of piping welds. For more rational assessments, it is important to consider the uncertainty of WRS in probabilistic fracture mechanics (PFM) analysis. In the existing PFM analysis codes, the uncertainty of WRS is set through statistical process of multiple finite element analysis (FEA) results. This process depends on persons who perform PFM analysis, and it may give different uncertainties. In this study, we developed a new WRS evaluation model based on the Fourier transformation, and the model was introduced into PASCAL-SP which has been developed by Japan Atomic Energy Agency. Through these improvements of the code, the uncertainty of WRS can be taken into account automatically and appropriately by inputting multiple WRS analysis results directly as input data of PFM analysis.
