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Watanabe, Yuichi*; Muramatsu, Ken; Oikawa, Tetsukuni
Nuclear Engineering and Design, 235(23), p.2495 - 2512, 2005/12
Times Cited Count：2 Percentile：17.25(Nuclear Science & Technology)This paper presents an evaluation of seismic capacity of a group of vertical U-tube type heat exchangers(HXs) with support frames for residual heat removal systems of BWRs for seismic Probabilistic Safety Assessment in Japan. The median capacity was evaluated by a time history response analysis with a detailed model for a representative HX selected from four HXs. The logarithmic standard deviation(LSD) for uncertainty due to lack of knowledge was evaluated with consideration of the variabilities in three influential parameters, i.e., diameter of anchor bolt, weight of HX and position of center of gravity of HX. The dominant failure mode of HXs was the failure of anchor bolts of lugs mainly due to shearing stress. The capacity expressed in terms of zero period acceleration on the foundation of HX was evaluated to be 4,180 Gal(4.3 g) for median, LSD for uncertainty due to randomness was 0.11 from the variability in material property and LSD due to lack of knowledge was 0.21 to 0.53 depending on combination of the variability in design parameters to be considered.
Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Watanabe, Yuichi*; Tamura, Kazuo*
JAERI-Data/Code 2002-011, 205 Pages, 2002/03
JAERI-Data-Code-2002-011.pdf:8.52MB
This report is a user's manual of seismic system reliability analysis code SECOM2 developed at the JAERI for system reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as calculation of component and system failure probabilities for given seismic motion levels at the site of an NPP based on the response factor method, calculation of accident sequence frequencies and the core damage frequency (CDF), importance analysis using various indicators, uncertainty analysis, and calculation of the CDF taking into account the effect of the correlations of responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about responses and capacities of the components which compose the FT, and seismic hazard curve for the NPP site as input. This report presents calculation method used in the SECOM2 code and how to use those functions in the SECOM2 code.
Yokobayashi, Masao; Oikawa, Tetsukuni; Muramatsu, Ken
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(1), p.95 - 105, 2002/03
no abstracts in English
Oikawa, Tetsukuni; Fukushima, Seiichiro*; Takase, Hidekazu*; Uchiyama, Tomoaki*; Muramatsu, Ken
Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08
no abstracts in English
Muramatsu, Ken; Hirose, Jiro*; Oikawa, Tetsukuni; Kondo, Masaaki
Proceedings of 15th KAIF/JAERI Annual Meeting, p.229 - 238, 2000/00
no abstracts in English
Oikawa, Tetsukuni; Muramatsu, Ken; Kasahara, Takeo*; Kawamata, Kazuhiko*; Morota, Hidetsugu*
Proceedings of 5th International Conference on Probabilistic Safety Assessment and Management (PSAM-5), p.2119 - 2125, 2000/00
no abstracts in English
