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Kinoshita, Takahiro*; Okamura, Shigeki*; Nishino, Hiroyuki; Yamano, Hidemasa; Kurisaka, Kenichi; Futagami, Satoshi; Fukasawa, Tsuyoshi*
Transactions of the 26th International Conference on Structural Mechanics in Reactor Technology (SMiRT-26) (Internet), 7 Pages, 2022/07
The seismic evaluation of key components such as reactor vessel is important for the Seismic Probabilistic Risk Assessment (S-PRA) in a Sodium-Cooled Fast Reactor (SFR). Many components were damaged by cumulative damage like fatigue damage during seismic ground motion. However, general evaluation method for key components under seismic ground motion has been based on static loads and elastic region of materials. More accurate evaluation method for S-PRA, which can evaluate the failure of key components such as reactor vessels, has been actually required. In this study, failure probability evaluation method with integrated energy was developed by comparing the energy with vibration tests and fatigue tests. Vibration tests were performed to evaluate integrated vibration energy at failure by energy balance equation and fatigue tests were performed to evaluate integrated vibration energy at failure based on experimental results of fatigue tests.
Yamano, Hidemasa; Nishida, Akemi; Choi, B.; Takada, Tsuyoshi*
Transactions of the 25th International Conference on Structural Mechanics in Reactor Technology (SMiRT-25) (USB Flash Drive), 10 Pages, 2019/08
The objective of this study is to assess cliff edge effects, which are greatly important for nuclear power plants. Through assessments of failure probabilities (fragility), this study examined seismic margins of simulated two kinds of thin- and thick-walled reactor vessels by using response waveforms of the reactor building with/without a seismic isolation system obtained by seismic response analyses. The fragility analyses showed that the seismic isolation technology largely reduced the structural response effects nearly twice as much as that of the non-isolated plant. In focusing on uncertainty of response factor of components, the seismic isolation plant has a significant margin compared to the non-isolated plant even if factors from 0.5 to 2.0 are taken into account. This study concluded that the seismic isolation technology is effective to avoid cliff-edge effects.
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
JAERI-Research 99-035, 314 Pages, 1999/05
JAERI-Research-99-035.pdf:14.99MB
no abstracts in English
Ebisawa, Katsumi; Shibata, Katsuyuki; Muramatsu, Ken; Umemoto, Michitaka
Chikyu Wakusei Kagaku Knren Gakkai 1998-Nen Godo Taikai Yokousyu, p.22 - 23, 1998/00
no abstracts in English
Muramatsu, Ken
Proc. of 10th Sino-Jananese Seminar on Nuclear Safety, 0, p.1.3.1 - 1.3.16, 1995/00
no abstracts in English
Kondo, Masaaki
Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.53 - 59, 1993/01
no abstracts in English
*; Tobioka, Toshiaki; Soda, Kunihisa; Abe, Kiyoharu
Proc. of the 8th Pacific Basin Nuclear Conf., p.3-A-1 - 3-A-9, 1992/00
no abstracts in English
; *; *; Abe, Kiyoharu
Doboku Gakkai Rombunshu, 0(437), p.143 - 152, 1991/10
no abstracts in English
*; ; *; Abe, Kiyoharu
IAE-R-8807, p.89 - 95, 1988/00
no abstracts in English
Abe, Kiyoharu; *; ; ; *
Proc. Int. ENS/ANS Conf. on Thermal Reactor Safety, Vol. 2, p.69-1 - 69-10, 1988/00
no abstracts in English
Choi, B.; Nishida, Akemi; Takada, Tsuyoshi*
no journal, ,
In this paper, in order to clarify the influence of difference due to modeling methods on the results of seismic response analysis for a nuclear facility, seismic response analysis using various earthquake events was conducted and the findings obtained from the uncertainty assessment of the response result due to the difference in modeling methods are reported.
