Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system

A three-dimensional seismic isolation system has been developed for the conceptual design of a sodium-cooled fast reactor (SFR) in Japan. Between the reactor building equipped with the isolation system and the turbine building with no isolation system, there are main steam crossover piping systems,...

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Main Authors: Tomoyoshi WATAKABE, Takahiro OKUDA, Satoshi OKAJIMA
Format: Article
Language:English
Published: The Japan Society of Mechanical Engineers 2024-02-01
Series:Mechanical Engineering Journal
Subjects:
Online Access:https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00395/_pdf/-char/en
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author Tomoyoshi WATAKABE
Takahiro OKUDA
Satoshi OKAJIMA
author_facet Tomoyoshi WATAKABE
Takahiro OKUDA
Satoshi OKAJIMA
author_sort Tomoyoshi WATAKABE
collection DOAJ
description A three-dimensional seismic isolation system has been developed for the conceptual design of a sodium-cooled fast reactor (SFR) in Japan. Between the reactor building equipped with the isolation system and the turbine building with no isolation system, there are main steam crossover piping systems, in which a large displacement would occur, and this is a challenge for developing an SFR with the isolation system. Existing studies of the seismic design of crossover piping were performed on the piping, considering the conditions of light water reactors (LWRs). However, because the SFR operates at elevated temperatures compared with LWRs, the design of crossover piping systems must comply with the design code for elevated temperature components. It must be also considered that the advanced material, Mod.9Cr-1Mo steel, is employed as a material of the crossover piping in the SFR. In this study, we performed seismic evaluation using an example of a crossover piping layout to refer to existing codes on piping. The evaluation results and insight obtained from existing dynamic failure tests of piping components show the knowledge on seismic evaluation of the crossover piping systems in the SFR with the three-dimensional isolation system to achieve the SFR with the three-dimensional isolation system.
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spelling doaj.art-de219100dab1441a9cc9df6bbccab9822024-04-16T01:29:36ZengThe Japan Society of Mechanical EngineersMechanical Engineering Journal2187-97452024-02-0111223-0039523-0039510.1299/mej.23-00395mejSeismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation systemTomoyoshi WATAKABE0Takahiro OKUDA1Satoshi OKAJIMA2Japan Atomic Energy AgencyJapan Atomic Energy AgencyJapan Atomic Energy AgencyA three-dimensional seismic isolation system has been developed for the conceptual design of a sodium-cooled fast reactor (SFR) in Japan. Between the reactor building equipped with the isolation system and the turbine building with no isolation system, there are main steam crossover piping systems, in which a large displacement would occur, and this is a challenge for developing an SFR with the isolation system. Existing studies of the seismic design of crossover piping were performed on the piping, considering the conditions of light water reactors (LWRs). However, because the SFR operates at elevated temperatures compared with LWRs, the design of crossover piping systems must comply with the design code for elevated temperature components. It must be also considered that the advanced material, Mod.9Cr-1Mo steel, is employed as a material of the crossover piping in the SFR. In this study, we performed seismic evaluation using an example of a crossover piping layout to refer to existing codes on piping. The evaluation results and insight obtained from existing dynamic failure tests of piping components show the knowledge on seismic evaluation of the crossover piping systems in the SFR with the three-dimensional isolation system to achieve the SFR with the three-dimensional isolation system.https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00395/_pdf/-char/encrossover pipingseismic isolationfatigueductile rupturefinite element analysis
spellingShingle Tomoyoshi WATAKABE
Takahiro OKUDA
Satoshi OKAJIMA
Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
Mechanical Engineering Journal
crossover piping
seismic isolation
fatigue
ductile rupture
finite element analysis
title Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
title_full Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
title_fullStr Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
title_full_unstemmed Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
title_short Seismic qualification of crossover piping systems on a sodium-cooled fast reactor with a seismic isolation system
title_sort seismic qualification of crossover piping systems on a sodium cooled fast reactor with a seismic isolation system
topic crossover piping
seismic isolation
fatigue
ductile rupture
finite element analysis
url https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00395/_pdf/-char/en
work_keys_str_mv AT tomoyoshiwatakabe seismicqualificationofcrossoverpipingsystemsonasodiumcooledfastreactorwithaseismicisolationsystem
AT takahirookuda seismicqualificationofcrossoverpipingsystemsonasodiumcooledfastreactorwithaseismicisolationsystem
AT satoshiokajima seismicqualificationofcrossoverpipingsystemsonasodiumcooledfastreactorwithaseismicisolationsystem