The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention

The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the co...
Ausführliche Beschreibung

Gespeichert in:

Autor*in:	Hu, Qiang [verfasserIn] Yan, Xiao [verfasserIn] Huang, Shanfang [verfasserIn] Yu, Junchong [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2018

Schlagwörter:	Natural circulation Critical heat flux In-vessel retention ERVC

Übergeordnetes Werk:	Enthalten in: Annals of nuclear energy - Amsterdam [u.a.] : Elsevier Science, 1975, 120, Seite 296-303
Übergeordnetes Werk:	volume:120 ; pages:296-303

DOI / URN:	10.1016/j.anucene.2018.05.048

Katalog-ID:	ELV000127884

Internformat


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245	1	0	\|a The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
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520			\|a The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied.
650		4	\|a Natural circulation
650		4	\|a Critical heat flux
650		4	\|a In-vessel retention
650		4	\|a ERVC
700	1		\|a Yan, Xiao \|e verfasserin \|4 aut
700	1		\|a Huang, Shanfang \|e verfasserin \|4 aut
700	1		\|a Yu, Junchong \|e verfasserin \|4 aut
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author_variant	q h qh x y xy s h sh j y jy
matchkey_str	article:03064549:2018----::hcmrhnienlssfolbltlmtopsiexenlecovsec
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publishDate	2018
allfields	10.1016/j.anucene.2018.05.048 doi (DE-627)ELV000127884 (ELSEVIER)S0306-4549(18)30285-8 DE-627 ger DE-627 rda eng 530 DE-600 33.00 bkl 52.55 bkl Hu, Qiang verfasserin aut The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied. Natural circulation Critical heat flux In-vessel retention ERVC Yan, Xiao verfasserin aut Huang, Shanfang verfasserin aut Yu, Junchong verfasserin aut Enthalten in Annals of nuclear energy Amsterdam [u.a.] : Elsevier Science, 1975 120, Seite 296-303 Online-Ressource (DE-627)320406679 (DE-600)2000768-1 (DE-576)120883511 0306-4549 nnns volume:120 pages:296-303 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 33.00 Physik: Allgemeines 52.55 Kerntechnik Reaktortechnik AR 120 296-303
spelling	10.1016/j.anucene.2018.05.048 doi (DE-627)ELV000127884 (ELSEVIER)S0306-4549(18)30285-8 DE-627 ger DE-627 rda eng 530 DE-600 33.00 bkl 52.55 bkl Hu, Qiang verfasserin aut The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied. Natural circulation Critical heat flux In-vessel retention ERVC Yan, Xiao verfasserin aut Huang, Shanfang verfasserin aut Yu, Junchong verfasserin aut Enthalten in Annals of nuclear energy Amsterdam [u.a.] : Elsevier Science, 1975 120, Seite 296-303 Online-Ressource (DE-627)320406679 (DE-600)2000768-1 (DE-576)120883511 0306-4549 nnns volume:120 pages:296-303 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 33.00 Physik: Allgemeines 52.55 Kerntechnik Reaktortechnik AR 120 296-303
allfields_unstemmed	10.1016/j.anucene.2018.05.048 doi (DE-627)ELV000127884 (ELSEVIER)S0306-4549(18)30285-8 DE-627 ger DE-627 rda eng 530 DE-600 33.00 bkl 52.55 bkl Hu, Qiang verfasserin aut The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied. Natural circulation Critical heat flux In-vessel retention ERVC Yan, Xiao verfasserin aut Huang, Shanfang verfasserin aut Yu, Junchong verfasserin aut Enthalten in Annals of nuclear energy Amsterdam [u.a.] : Elsevier Science, 1975 120, Seite 296-303 Online-Ressource (DE-627)320406679 (DE-600)2000768-1 (DE-576)120883511 0306-4549 nnns volume:120 pages:296-303 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 33.00 Physik: Allgemeines 52.55 Kerntechnik Reaktortechnik AR 120 296-303
allfieldsGer	10.1016/j.anucene.2018.05.048 doi (DE-627)ELV000127884 (ELSEVIER)S0306-4549(18)30285-8 DE-627 ger DE-627 rda eng 530 DE-600 33.00 bkl 52.55 bkl Hu, Qiang verfasserin aut The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied. Natural circulation Critical heat flux In-vessel retention ERVC Yan, Xiao verfasserin aut Huang, Shanfang verfasserin aut Yu, Junchong verfasserin aut Enthalten in Annals of nuclear energy Amsterdam [u.a.] : Elsevier Science, 1975 120, Seite 296-303 Online-Ressource (DE-627)320406679 (DE-600)2000768-1 (DE-576)120883511 0306-4549 nnns volume:120 pages:296-303 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 33.00 Physik: Allgemeines 52.55 Kerntechnik Reaktortechnik AR 120 296-303
allfieldsSound	10.1016/j.anucene.2018.05.048 doi (DE-627)ELV000127884 (ELSEVIER)S0306-4549(18)30285-8 DE-627 ger DE-627 rda eng 530 DE-600 33.00 bkl 52.55 bkl Hu, Qiang verfasserin aut The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied. Natural circulation Critical heat flux In-vessel retention ERVC Yan, Xiao verfasserin aut Huang, Shanfang verfasserin aut Yu, Junchong verfasserin aut Enthalten in Annals of nuclear energy Amsterdam [u.a.] : Elsevier Science, 1975 120, Seite 296-303 Online-Ressource (DE-627)320406679 (DE-600)2000768-1 (DE-576)120883511 0306-4549 nnns volume:120 pages:296-303 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 33.00 Physik: Allgemeines 52.55 Kerntechnik Reaktortechnik AR 120 296-303
language	English
source	Enthalten in Annals of nuclear energy 120, Seite 296-303 volume:120 pages:296-303
sourceStr	Enthalten in Annals of nuclear energy 120, Seite 296-303 volume:120 pages:296-303
format_phy_str_mv	Article
bklname	Physik: Allgemeines Kerntechnik Reaktortechnik
institution	findex.gbv.de
topic_facet	Natural circulation Critical heat flux In-vessel retention ERVC
dewey-raw	530
isfreeaccess_bool	false
container_title	Annals of nuclear energy
authorswithroles_txt_mv	Hu, Qiang @@aut@@ Yan, Xiao @@aut@@ Huang, Shanfang @@aut@@ Yu, Junchong @@aut@@
publishDateDaySort_date	2018-01-01T00:00:00Z
hierarchy_top_id	320406679
dewey-sort	3530
id	ELV000127884
language_de	englisch
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author	Hu, Qiang
spellingShingle	Hu, Qiang ddc 530 bkl 33.00 bkl 52.55 misc Natural circulation misc Critical heat flux misc In-vessel retention misc ERVC The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
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topic_title	530 DE-600 33.00 bkl 52.55 bkl The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention Natural circulation Critical heat flux In-vessel retention ERVC
topic	ddc 530 bkl 33.00 bkl 52.55 misc Natural circulation misc Critical heat flux misc In-vessel retention misc ERVC
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title	The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
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title_full	The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
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title_sort	the comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
title_auth	The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
abstract	The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied.
abstractGer	The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied.
abstract_unstemmed	The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident. In this work combined with the two-phase drift flux model, an analysis program for the induced two-phase circulation flow has been established based on one-dimensional steady-state mass, momentum and energy conservation equations. The calculation results are compared with the simulation results using RELAP5 within the same geometric parameters to verify the rationality and correctness of the analysis program. Combining the analysis program with the SULTAN CHF correlation, the characteristics of induced two-phase flow and the CHF on the outer surface of lower head are studied comprehensively to analyze the coolability limits of ERVC under in-vessel retention. The effects of concerned parameters including subcooling of water, decay power of molten corium, flooding levels, height of riser channel, loss coefficient at the inlet and gap clearance between the reactor pressure vessel and thermal insulation are studied.
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title_short	The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention
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up_date	2024-07-06T16:57:08.915Z
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The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention

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