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Yamamoto, Tomohiko; Matsubara, Shinichiro*; Harada, Hidenori*; Saunier, P.*; Martin, L.*; Gentet, D.*; Dirat, J.-F.*; Collignon, C.*
Nuclear Engineering and Design, 383, p.111406_1 - 111406_14, 2021/11
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Japan-France collaboration on ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project is launched in 2014. In this project, Japan-France evaluates core assemblies with interferences on seismic event. The object of this study is to verify the seismic evaluation method on core assemblies between Japan and France by comparing the results. The analysis of this benchmark calculation shows a satisfactory agreement between the Japanese and French tools and the figures show a good behavior of the core in horizontal direction under French seismic condition.
Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori
JAEA-Technology 2020-022, 32 Pages, 2021/02
JAEA-Technology-2020-022.pdf:4.04MB
Among the canal underwater equipment of HR-1, seismic evaluations of the canal side wall parts and the canal bottom surface parts were carried out for the insertion device, take-out device and decay tank. As a result, it was confirmed that the equipments have sufficient seismic resistances because the maximum stress of the canal side wall joint, the bolt portion of the canal bottom joint, and the fillet weld are within the allowable stress.
Yamamoto, Tomohiko; Matsubara, Shinichiro*; Harada, Hidenori*; Saunier, P.*; Martin, L.*; Gentet, D.*; Dirat, J.-F.*; Collignon, C.*
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05
Japan-France collaboration on ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project is launched in 2014. In this project, Japan-France evaluates core assemblies with interferences on seismic event. The object of this study is to verify the seismic evaluation method on core assemblies between Japan and France by comparing the results. The analysis of this benchmark calculation shows a satisfactory agreement between the Japanese and French tools and the figures show a good behavior of the core in horizontal direction under French seismic condition.
Abe, Masato; Watakabe, Tomoyoshi; Moriizumi, Makoto*; Tsukimori, Kazuyuki
no journal, ,
The seismic load which occurs to the equipment and piping at the time of an earthquake in nuclear power plants has the various conditions. As for the load direction, it is not certain when earthquake condition. In this paper, a result of analytical evaluation of impact on structural strength of a thin wall elbow is reported, for the purpose of contribute to structural integrity evaluation of the thin wall piping.
Okuda, Takahiro; Miyazaki, Masashi; Kitamura, Seiji
no journal, ,
The equipment and piping in nuclear power plants receive loads from various directions during earthquakes. Understanding the load direction that most affects the structural strength of piping is an important for evaluating the seismic integrity of piping. In this paper, focusing on thin wall tee applied in fast reactor, a result of analytical evaluation of impact on structural strength of a thin wall tee is reported.
Okuda, Takahiro; Takahashi, Hideki*; Morishita, Masaki
no journal, ,
This study describes the results of a series of seismic analyses conducted to clarify how plastic deformation of a pipe and its support structures affects the seismic response of the entire piping system. The analyses conducted include; plasticity is considered for (1)the support structure only, (2)the piping only and (3)both the piping and the support structure.
