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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Format: | Article |
Language: | English |
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The Japan Society of Mechanical Engineers
2024-02-01
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Series: | Mechanical Engineering Journal |
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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. |
first_indexed | 2024-04-24T09:01:13Z |
format | Article |
id | doaj.art-de219100dab1441a9cc9df6bbccab982 |
institution | Directory Open Access Journal |
issn | 2187-9745 |
language | English |
last_indexed | 2024-04-24T09:01:13Z |
publishDate | 2024-02-01 |
publisher | The Japan Society of Mechanical Engineers |
record_format | Article |
series | Mechanical Engineering Journal |
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 |