Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures

In order to precisely investigate molten core relocation behavior in severe accidents, we have been developing the detailed and phenomenological numerical simulation code named JUPITER for predicting the molten core behavior with melting and solidification based on computational fluid dynamics (CFD)...

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Autores principales:	Susumu YAMASHITA, Kazuyuki TOKUSHIMA, Masaki KURATA, Hiroyuki YOSHIDA
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2017
Materias:	computational fluid dynamics (cfd) multiphase flow melt relocation behavior severe accident boiling water reactor (bwr) Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/d178026975bc4670a03e617894c96a4a
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spelling	oai:doaj.org-article:d178026975bc4670a03e617894c96a4a2021-11-26T07:03:57ZDevelopment of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures2187-974510.1299/mej.16-00567https://doaj.org/article/d178026975bc4670a03e617894c96a4a2017-02-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/4/3/4_16-00567/_pdf/-char/enhttps://doaj.org/toc/2187-9745In order to precisely investigate molten core relocation behavior in severe accidents, we have been developing the detailed and phenomenological numerical simulation code named JUPITER for predicting the molten core behavior with melting and solidification based on computational fluid dynamics (CFD) including the three-dimensional multiphase thermal-hydraulic simulation models. In order to treat complicated core structures, e.g., boron carbide (absorber), stainless steel (control rod, fuel support structure, etc.), Zircaloy (channel box and fuel cladding) and to deal with complicated melt relocation behaviors, high accuracy, efficient, stable and robust numerical schemes are implemented. In this paper, in order to evaluate the validity and applicability of the JUPITER for actual core structures, we perform the preliminary melt relocation analysis in the control rod and fuel support piece and also verify the validity of the JUPITER regarding the melt relocation and solidification processes by the fundamental numerical problem and the experimental analysis. As a result, the preliminary analysis showed that multicomponent melt flow and its melt and solidification were stably worked in the melt relocation simulation. In the validation analysis, the numerical results were in the reasonably agreement with experimental results. Therefore, it was confirmed that the JUPITER has a potential to calculate the core melt relocation behavior in RPVs.Susumu YAMASHITAKazuyuki TOKUSHIMAMasaki KURATAHiroyuki YOSHIDAThe Japan Society of Mechanical Engineersarticlecomputational fluid dynamics (cfd)multiphase flowmelt relocation behaviorsevere accidentboiling water reactor (bwr)Mechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 4, Iss 3, Pp 16-00567-16-00567 (2017)
institution	DOAJ
collection	DOAJ
language	EN
topic	computational fluid dynamics (cfd) multiphase flow melt relocation behavior severe accident boiling water reactor (bwr) Mechanical engineering and machinery TJ1-1570
spellingShingle	computational fluid dynamics (cfd) multiphase flow melt relocation behavior severe accident boiling water reactor (bwr) Mechanical engineering and machinery TJ1-1570 Susumu YAMASHITA Kazuyuki TOKUSHIMA Masaki KURATA Hiroyuki YOSHIDA Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
description	In order to precisely investigate molten core relocation behavior in severe accidents, we have been developing the detailed and phenomenological numerical simulation code named JUPITER for predicting the molten core behavior with melting and solidification based on computational fluid dynamics (CFD) including the three-dimensional multiphase thermal-hydraulic simulation models. In order to treat complicated core structures, e.g., boron carbide (absorber), stainless steel (control rod, fuel support structure, etc.), Zircaloy (channel box and fuel cladding) and to deal with complicated melt relocation behaviors, high accuracy, efficient, stable and robust numerical schemes are implemented. In this paper, in order to evaluate the validity and applicability of the JUPITER for actual core structures, we perform the preliminary melt relocation analysis in the control rod and fuel support piece and also verify the validity of the JUPITER regarding the melt relocation and solidification processes by the fundamental numerical problem and the experimental analysis. As a result, the preliminary analysis showed that multicomponent melt flow and its melt and solidification were stably worked in the melt relocation simulation. In the validation analysis, the numerical results were in the reasonably agreement with experimental results. Therefore, it was confirmed that the JUPITER has a potential to calculate the core melt relocation behavior in RPVs.
format	article
author	Susumu YAMASHITA Kazuyuki TOKUSHIMA Masaki KURATA Hiroyuki YOSHIDA
author_facet	Susumu YAMASHITA Kazuyuki TOKUSHIMA Masaki KURATA Hiroyuki YOSHIDA
author_sort	Susumu YAMASHITA
title	Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
title_short	Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
title_full	Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
title_fullStr	Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
title_full_unstemmed	Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
title_sort	development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures
publisher	The Japan Society of Mechanical Engineers
publishDate	2017
url	https://doaj.org/article/d178026975bc4670a03e617894c96a4a
work_keys_str_mv	AT susumuyamashita developmentofnumericalsimulationmethodformeltrelocationbehaviorinnuclearreactorsvalidationandapplicabilityforactualcorestructures AT kazuyukitokushima developmentofnumericalsimulationmethodformeltrelocationbehaviorinnuclearreactorsvalidationandapplicabilityforactualcorestructures AT masakikurata developmentofnumericalsimulationmethodformeltrelocationbehaviorinnuclearreactorsvalidationandapplicabilityforactualcorestructures AT hiroyukiyoshida developmentofnumericalsimulationmethodformeltrelocationbehaviorinnuclearreactorsvalidationandapplicabilityforactualcorestructures
_version_	1718409746443141120

Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures

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