A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor

Autores
Ramajo, Damian Enrique; Corzo, Santiago Francisco; Nigro, Norberto Marcelo
Año de publicación
2015
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
A Multi-dimensional computational fluid dynamics(CFD) two-phase model was developed with the aim to simulatethe in-core coolant circuit of a pressurized heavy water reactor(PHWR) of a commercial nuclear power plant (NPP). Due to thefact that this PHWR is a Reactor Pressure Vessel type (RPV),three-dimensional (3D) detailed modelling of the large reservoirs ofthe RPV (the upper and lower plenums and the downcomer) werecoupled with an in-house finite volume one-dimensional (1D) codein order to model the 451 coolant channels housing the nuclear fuel.Regarding the 1D code, suitable empirical correlations for taking intoaccount the in-channel distributed (friction losses) and concentrated(spacer grids, inlet and outlet throttles) pressure losses were used.A local power distribution at each one of the coolant channelswas also taken into account. The heat transfer between the coolantand the surrounding moderator was accurately calculated using atwo-dimensional theoretical model. The implementation of subcooledboiling and condensation models in the 1D code along with the useof functions for representing the thermal and dynamic properties ofthe coolant and moderator (heavy water) allow to have estimationsof the in-core steam generation under nominal flow conditions for ageneric fission power distribution. The in-core mass flow distributionresults for steady state nominal conditions are in agreement with theexpected from design, thus getting a first assessment of the coupled1/3D model. Results for nominal condition were compared withthose obtained with a previous 1/3D single-phase model getting morerealistic temperature patterns, also allowing visualize low values ofvoid fraction inside the upper plenum. It must be mentioned that thecurrent results were obtained by imposing prescribed fission powerfunctions from literature. Therefore, results are showed with the aimof point out the potentiality of the developed model.
Fil: Ramajo, Damian Enrique. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
Fil: Corzo, Santiago Francisco. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
Fil: Nigro, Norberto Marcelo. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
Materia
CFD
PHWR
Thermo-hydraulic
Two-phase flow
Nivel de accesibilidad
acceso abierto
Condiciones de uso
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
Repositorio
CONICET Digital (CONICET)
Institución
Consejo Nacional de Investigaciones Científicas y Técnicas
OAI Identificador
oai:ri.conicet.gov.ar:11336/40262
Acceder
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oai_identifier_str oai:ri.conicet.gov.ar:11336/40262
network_acronym_str CONICETDig
repository_id_str 3498
network_name_str CONICET Digital (CONICET)
spelling A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel ReactorRamajo, Damian EnriqueCorzo, Santiago FranciscoNigro, Norberto MarceloCFDPHWRThermo-hydraulicTwo-phase flowhttps://purl.org/becyt/ford/2.3https://purl.org/becyt/ford/2A Multi-dimensional computational fluid dynamics(CFD) two-phase model was developed with the aim to simulatethe in-core coolant circuit of a pressurized heavy water reactor(PHWR) of a commercial nuclear power plant (NPP). Due to thefact that this PHWR is a Reactor Pressure Vessel type (RPV),three-dimensional (3D) detailed modelling of the large reservoirs ofthe RPV (the upper and lower plenums and the downcomer) werecoupled with an in-house finite volume one-dimensional (1D) codein order to model the 451 coolant channels housing the nuclear fuel.Regarding the 1D code, suitable empirical correlations for taking intoaccount the in-channel distributed (friction losses) and concentrated(spacer grids, inlet and outlet throttles) pressure losses were used.A local power distribution at each one of the coolant channelswas also taken into account. The heat transfer between the coolantand the surrounding moderator was accurately calculated using atwo-dimensional theoretical model. The implementation of subcooledboiling and condensation models in the 1D code along with the useof functions for representing the thermal and dynamic properties ofthe coolant and moderator (heavy water) allow to have estimationsof the in-core steam generation under nominal flow conditions for ageneric fission power distribution. The in-core mass flow distributionresults for steady state nominal conditions are in agreement with theexpected from design, thus getting a first assessment of the coupled1/3D model. Results for nominal condition were compared withthose obtained with a previous 1/3D single-phase model getting morerealistic temperature patterns, also allowing visualize low values ofvoid fraction inside the upper plenum. It must be mentioned that thecurrent results were obtained by imposing prescribed fission powerfunctions from literature. Therefore, results are showed with the aimof point out the potentiality of the developed model.Fil: Ramajo, Damian Enrique. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; ArgentinaFil: Corzo, Santiago Francisco. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; ArgentinaFil: Nigro, Norberto Marcelo. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; ArgentinaWorld Academy of Science, Engineering and Technology-WASET2015-11info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/40262Ramajo, Damian Enrique; Corzo, Santiago Francisco; Nigro, Norberto Marcelo; A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor; World Academy of Science, Engineering and Technology-WASET; International Journal of Mathematical, Computational, Physical, Electrical and Computer Engineering; 9; 11; 11-2015; 623-6281307-6892CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/http://waset.org/Publications/?path=Publications&p=107info:eu-repo/semantics/altIdentifier/url/http://scholar.waset.org/1999.7/10002904info:eu-repo/semantics/altIdentifier/url/https://waset.org/Publication/a-coupled-model-for-two-phase-simulation-of-a-heavy-water-pressure-vessel-reactor/10002904info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-15T15:08:46Zoai:ri.conicet.gov.ar:11336/40262instacron:CONICETInstitucionalhttp://ri.conicet.gov.ar/Organismo científico-tecnológicoNo correspondehttp://ri.conicet.gov.ar/oai/requestdasensio@conicet.gov.ar; lcarlino@conicet.gov.arArgentinaNo correspondeNo correspondeNo correspondeopendoar:34982025-10-15 15:08:47.183CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
title A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
spellingShingle A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
Ramajo, Damian Enrique
CFD
PHWR
Thermo-hydraulic
Two-phase flow
title_short A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
title_full A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
title_fullStr A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
title_full_unstemmed A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
title_sort A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor
dc.creator.none.fl_str_mv Ramajo, Damian Enrique
Corzo, Santiago Francisco
Nigro, Norberto Marcelo
author Ramajo, Damian Enrique
author_facet Ramajo, Damian Enrique
Corzo, Santiago Francisco
Nigro, Norberto Marcelo
author_role author
author2 Corzo, Santiago Francisco
Nigro, Norberto Marcelo
author2_role author
author
dc.subject.none.fl_str_mv CFD
PHWR
Thermo-hydraulic
Two-phase flow
topic CFD
PHWR
Thermo-hydraulic
Two-phase flow
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.3
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv A Multi-dimensional computational fluid dynamics(CFD) two-phase model was developed with the aim to simulatethe in-core coolant circuit of a pressurized heavy water reactor(PHWR) of a commercial nuclear power plant (NPP). Due to thefact that this PHWR is a Reactor Pressure Vessel type (RPV),three-dimensional (3D) detailed modelling of the large reservoirs ofthe RPV (the upper and lower plenums and the downcomer) werecoupled with an in-house finite volume one-dimensional (1D) codein order to model the 451 coolant channels housing the nuclear fuel.Regarding the 1D code, suitable empirical correlations for taking intoaccount the in-channel distributed (friction losses) and concentrated(spacer grids, inlet and outlet throttles) pressure losses were used.A local power distribution at each one of the coolant channelswas also taken into account. The heat transfer between the coolantand the surrounding moderator was accurately calculated using atwo-dimensional theoretical model. The implementation of subcooledboiling and condensation models in the 1D code along with the useof functions for representing the thermal and dynamic properties ofthe coolant and moderator (heavy water) allow to have estimationsof the in-core steam generation under nominal flow conditions for ageneric fission power distribution. The in-core mass flow distributionresults for steady state nominal conditions are in agreement with theexpected from design, thus getting a first assessment of the coupled1/3D model. Results for nominal condition were compared withthose obtained with a previous 1/3D single-phase model getting morerealistic temperature patterns, also allowing visualize low values ofvoid fraction inside the upper plenum. It must be mentioned that thecurrent results were obtained by imposing prescribed fission powerfunctions from literature. Therefore, results are showed with the aimof point out the potentiality of the developed model.
Fil: Ramajo, Damian Enrique. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
Fil: Corzo, Santiago Francisco. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
Fil: Nigro, Norberto Marcelo. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Santa Fe. Centro de Investigaciones en Métodos Computacionales. Universidad Nacional del Litoral. Centro de Investigaciones en Métodos Computacionales; Argentina
description A Multi-dimensional computational fluid dynamics(CFD) two-phase model was developed with the aim to simulatethe in-core coolant circuit of a pressurized heavy water reactor(PHWR) of a commercial nuclear power plant (NPP). Due to thefact that this PHWR is a Reactor Pressure Vessel type (RPV),three-dimensional (3D) detailed modelling of the large reservoirs ofthe RPV (the upper and lower plenums and the downcomer) werecoupled with an in-house finite volume one-dimensional (1D) codein order to model the 451 coolant channels housing the nuclear fuel.Regarding the 1D code, suitable empirical correlations for taking intoaccount the in-channel distributed (friction losses) and concentrated(spacer grids, inlet and outlet throttles) pressure losses were used.A local power distribution at each one of the coolant channelswas also taken into account. The heat transfer between the coolantand the surrounding moderator was accurately calculated using atwo-dimensional theoretical model. The implementation of subcooledboiling and condensation models in the 1D code along with the useof functions for representing the thermal and dynamic properties ofthe coolant and moderator (heavy water) allow to have estimationsof the in-core steam generation under nominal flow conditions for ageneric fission power distribution. The in-core mass flow distributionresults for steady state nominal conditions are in agreement with theexpected from design, thus getting a first assessment of the coupled1/3D model. Results for nominal condition were compared withthose obtained with a previous 1/3D single-phase model getting morerealistic temperature patterns, also allowing visualize low values ofvoid fraction inside the upper plenum. It must be mentioned that thecurrent results were obtained by imposing prescribed fission powerfunctions from literature. Therefore, results are showed with the aimof point out the potentiality of the developed model.
publishDate 2015
dc.date.none.fl_str_mv 2015-11
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
http://purl.org/coar/resource_type/c_6501
info:ar-repo/semantics/articulo
format article
status_str publishedVersion
dc.identifier.none.fl_str_mv http://hdl.handle.net/11336/40262
Ramajo, Damian Enrique; Corzo, Santiago Francisco; Nigro, Norberto Marcelo; A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor; World Academy of Science, Engineering and Technology-WASET; International Journal of Mathematical, Computational, Physical, Electrical and Computer Engineering; 9; 11; 11-2015; 623-628
1307-6892
CONICET Digital
CONICET
url http://hdl.handle.net/11336/40262
identifier_str_mv Ramajo, Damian Enrique; Corzo, Santiago Francisco; Nigro, Norberto Marcelo; A Coupled Model for Two-Phase Simulation of a Heavy Water Pressure Vessel Reactor; World Academy of Science, Engineering and Technology-WASET; International Journal of Mathematical, Computational, Physical, Electrical and Computer Engineering; 9; 11; 11-2015; 623-628
1307-6892
CONICET Digital
CONICET
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/url/http://waset.org/Publications/?path=Publications&p=107
info:eu-repo/semantics/altIdentifier/url/http://scholar.waset.org/1999.7/10002904
info:eu-repo/semantics/altIdentifier/url/https://waset.org/Publication/a-coupled-model-for-two-phase-simulation-of-a-heavy-water-pressure-vessel-reactor/10002904
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
eu_rights_str_mv openAccess
rights_invalid_str_mv https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv World Academy of Science, Engineering and Technology-WASET
publisher.none.fl_str_mv World Academy of Science, Engineering and Technology-WASET
dc.source.none.fl_str_mv reponame:CONICET Digital (CONICET)
instname:Consejo Nacional de Investigaciones Científicas y Técnicas
reponame_str CONICET Digital (CONICET)
collection CONICET Digital (CONICET)
instname_str Consejo Nacional de Investigaciones Científicas y Técnicas
repository.name.fl_str_mv CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicas
repository.mail.fl_str_mv dasensio@conicet.gov.ar; lcarlino@conicet.gov.ar
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score 13.22299

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