RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient

RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995. The TMLB' scenario involves prolonged complete loss of alterna...

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Autores principales: Takeshi TAKEDA, Hideo NAKAMURA
Formato: article
Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2014
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pwr
Acceso en línea:https://doaj.org/article/261ca252596049adb15532250d642623
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spelling oai:doaj.org-article:261ca252596049adb15532250d6426232021-11-26T06:09:52ZRELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient2187-974510.1299/mej.2014tep0015https://doaj.org/article/261ca252596049adb15532250d6426232014-08-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/1/4/1_2014tep0015/_pdf/-char/enhttps://doaj.org/toc/2187-9745RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995. The TMLB' scenario involves prolonged complete loss of alternating current power and unavailability of turbine-driven auxiliary feedwater as well as malfunction of primary- and secondary-system relief valves. The LSTF test revealed core uncovery by core boil-off took place a little after hot leg became empty of liquid while the primary pressure was kept high. The RELAP5 code predicted well the overall trend of the major phenomena observed in the LSTF test, and indicated remaining problems in the predictions of reverse flow U-tubes in steam generator (SG) during long-term single-phase liquid natural circulation. Sensitivity analyses were performed further to clarify effectiveness of depressurization of and coolant injection into SG secondary-side as accident management measures for core cooling, based on the RELAP5 post-test analysis. SG secondary-side depressurization was initiated by fully opening the safety valve in one of two SGs with the incipience of core uncovery. Coolant injection was done into the secondary-side of the same SG at low pressures considering availability of fire engines. The peak cladding temperature was dependent on the onset timing and flow rate of the SG coolant injection as well as the onset timing of the SG depressurization after core uncovery. The SG depressurization with the SG coolant injection was found to well contribute to maintain core cooling by the actuation of accumulator system during a PWR SBO (TMLB') transient.Takeshi TAKEDAHideo NAKAMURAThe Japan Society of Mechanical Engineersarticlepwrrosa/lstfstation blackoutaccident managementsg depressurizationrelap5 codeMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 1, Iss 4, Pp TEP0015-TEP0015 (2014)
institution DOAJ
collection DOAJ
language EN
topic pwr
rosa/lstf
station blackout
accident management
sg depressurization
relap5 code
Mechanical engineering and machinery
TJ1-1570
spellingShingle pwr
rosa/lstf
station blackout
accident management
sg depressurization
relap5 code
Mechanical engineering and machinery
TJ1-1570
Takeshi TAKEDA
Hideo NAKAMURA
RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
description RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995. The TMLB' scenario involves prolonged complete loss of alternating current power and unavailability of turbine-driven auxiliary feedwater as well as malfunction of primary- and secondary-system relief valves. The LSTF test revealed core uncovery by core boil-off took place a little after hot leg became empty of liquid while the primary pressure was kept high. The RELAP5 code predicted well the overall trend of the major phenomena observed in the LSTF test, and indicated remaining problems in the predictions of reverse flow U-tubes in steam generator (SG) during long-term single-phase liquid natural circulation. Sensitivity analyses were performed further to clarify effectiveness of depressurization of and coolant injection into SG secondary-side as accident management measures for core cooling, based on the RELAP5 post-test analysis. SG secondary-side depressurization was initiated by fully opening the safety valve in one of two SGs with the incipience of core uncovery. Coolant injection was done into the secondary-side of the same SG at low pressures considering availability of fire engines. The peak cladding temperature was dependent on the onset timing and flow rate of the SG coolant injection as well as the onset timing of the SG depressurization after core uncovery. The SG depressurization with the SG coolant injection was found to well contribute to maintain core cooling by the actuation of accumulator system during a PWR SBO (TMLB') transient.
format article
author Takeshi TAKEDA
Hideo NAKAMURA
author_facet Takeshi TAKEDA
Hideo NAKAMURA
author_sort Takeshi TAKEDA
title RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
title_short RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
title_full RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
title_fullStr RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
title_full_unstemmed RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
title_sort relap5 code study of rosa/lstf experiment on a pwr station blackout (tmlb') transient
publisher The Japan Society of Mechanical Engineers
publishDate 2014
url https://doaj.org/article/261ca252596049adb15532250d642623
work_keys_str_mv AT takeshitakeda relap5codestudyofrosalstfexperimentonapwrstationblackouttmlbapostransient
AT hideonakamura relap5codestudyofrosalstfexperimentonapwrstationblackouttmlbapostransient
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