ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses

An experiment on a PWR station blackout transient with the TMLB' scenario and accident management (AM) measures was conducted using the rig of safety assessment/large scale test facility (ROSA/LSTF) at Japan Atomic Energy Agency under an assumption of non-condensable gas inflow to the prima...

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Autores principales:	Takeshi TAKEDA, Iwao OHTSU
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2015
Materias:	pwr rosa/lstf station blackout accident management sg depressurization relap5 code Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/769bd3d892904696b389b561ddac148d
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spelling	oai:doaj.org-article:769bd3d892904696b389b561ddac148d2021-11-26T06:30:10ZROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses2187-974510.1299/mej.15-00132https://doaj.org/article/769bd3d892904696b389b561ddac148d2015-08-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/2/5/2_15-00132/_pdf/-char/enhttps://doaj.org/toc/2187-9745An experiment on a PWR station blackout transient with the TMLB' scenario and accident management (AM) measures was conducted using the rig of safety assessment/large scale test facility (ROSA/LSTF) at Japan Atomic Energy Agency under an assumption of non-condensable gas inflow to the primary system from accumulator (ACC) tanks. The TMLB' scenario involves prolonged complete loss of alternating current power and unavailability of turbine-driven auxiliary feedwater as well as malfunction of relief valves in primary system and steam generator (SG) secondary-side system. The AM measures considered in this study are SG secondary-side depressurization by fully opening the safety valves in both SGs with the start of core uncovery and coolant injection into the secondary-side of both SGs at low pressures. The LSTF test revealed that the primary pressure started to decrease when the SG primary-to-secondary heat removal resumed soon after the coolant injection into the SG secondary-side. The primary depressurization worsened due to the gas accumulation in the SG U-tubes after the completion of ACC coolant injection. The RELAP5 code well predicted the overall trend of the major phenomena observed in the LSTF test, and indicated remaining problems in the predictions of the SG U-tube collapsed liquid level and primary mass flow rate after the gas ingress. The SG coolant injection flow rate was found to significantly affect the peak cladding temperature and the ACC actuation time through the RELAP5 sensitivity analyses.Takeshi TAKEDAIwao OHTSUThe Japan Society of Mechanical Engineersarticlepwrrosa/lstfstation blackoutaccident managementsg depressurizationrelap5 codeMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 2, Iss 5, Pp 15-00132-15-00132 (2015)
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 Iwao OHTSU ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
description	An experiment on a PWR station blackout transient with the TMLB' scenario and accident management (AM) measures was conducted using the rig of safety assessment/large scale test facility (ROSA/LSTF) at Japan Atomic Energy Agency under an assumption of non-condensable gas inflow to the primary system from accumulator (ACC) tanks. The TMLB' scenario involves prolonged complete loss of alternating current power and unavailability of turbine-driven auxiliary feedwater as well as malfunction of relief valves in primary system and steam generator (SG) secondary-side system. The AM measures considered in this study are SG secondary-side depressurization by fully opening the safety valves in both SGs with the start of core uncovery and coolant injection into the secondary-side of both SGs at low pressures. The LSTF test revealed that the primary pressure started to decrease when the SG primary-to-secondary heat removal resumed soon after the coolant injection into the SG secondary-side. The primary depressurization worsened due to the gas accumulation in the SG U-tubes after the completion of ACC coolant injection. The RELAP5 code well predicted the overall trend of the major phenomena observed in the LSTF test, and indicated remaining problems in the predictions of the SG U-tube collapsed liquid level and primary mass flow rate after the gas ingress. The SG coolant injection flow rate was found to significantly affect the peak cladding temperature and the ACC actuation time through the RELAP5 sensitivity analyses.
format	article
author	Takeshi TAKEDA Iwao OHTSU
author_facet	Takeshi TAKEDA Iwao OHTSU
author_sort	Takeshi TAKEDA
title	ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
title_short	ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
title_full	ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
title_fullStr	ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
title_full_unstemmed	ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses
title_sort	rosa/lstf experiment on a pwr station blackout transient with accident management measures and relap5 analyses
publisher	The Japan Society of Mechanical Engineers
publishDate	2015
url	https://doaj.org/article/769bd3d892904696b389b561ddac148d
work_keys_str_mv	AT takeshitakeda rosalstfexperimentonapwrstationblackouttransientwithaccidentmanagementmeasuresandrelap5analyses AT iwaoohtsu rosalstfexperimentonapwrstationblackouttransientwithaccidentmanagementmeasuresandrelap5analyses
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ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses

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