Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility

The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolant using a light water test facility. A large nuclear power reactor (like the BN-1200 project) was selected as a reactor installation to be modeled. To validate the model, the similarity theory and the...

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Egile nagusia: Slobodchuk, V.I. (author)
Beste egile batzuk: Avramova, E.A. (author), Shchennikova, E.M. (author), Shal'kov, D.A. (author)
Formatua: article
Hizkuntza:ingelesa
Argitaratua: 2018
Sarrera elektronikoa:https://knepublishing.com/index.php/KnE-Engineering/article/view/1627
http://ridda2.utp.ac.pa/handle/123456789/4343
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author Slobodchuk, V.I.
author2 Avramova, E.A.
Shchennikova, E.M.
Shal'kov, D.A.
author2_role author
author
author
author_browse Avramova, E.A.
Shal'kov, D.A.
Shchennikova, E.M.
Slobodchuk, V.I.
author_facet Slobodchuk, V.I.
Avramova, E.A.
Shchennikova, E.M.
Shal'kov, D.A.
author_role author
collection Repositorio Institucional de documento digitales de acceso abierto de la UTP
dc.contributor.none.fl_str_mv
dc.creator.none.fl_str_mv Slobodchuk, V.I.
Avramova, E.A.
Shchennikova, E.M.
Shal'kov, D.A.
Slobodchuk, V.I.
Avramova, E.A.
Shchennikova, E.M.
Shal'kov, D.A.
dc.date.none.fl_str_mv 2018-02-21
2018-02-23T17:16:28Z
2018-02-23T17:16:28Z
dc.format.none.fl_str_mv application/msword
application/pdf
application/xml
dc.identifier.none.fl_str_mv https://knepublishing.com/index.php/KnE-Engineering/article/view/1627
10.18502/keg.v3i3.1627
http://ridda2.utp.ac.pa/handle/123456789/4343
dc.language.none.fl_str_mv eng
dc.publisher.none.fl_str_mv KnE Publishing
dc.relation.none.fl_str_mv https://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3845
https://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3846
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by/4.0/
dc.source.none.fl_str_mv 2518-6841
KnE Engineering; XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"; 279-290
reponame:Repositorio Institucional de documento digitales de acceso abierto de la UTP
instname:Universidad Tecnológica de Panamá
instacron:U Tecnológica de Panamá
dc.title.none.fl_str_mv Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
description The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolant using a light water test facility. A large nuclear power reactor (like the BN-1200 project) was selected as a reactor installation to be modeled. To validate the model, the similarity theory and the “black box” method were used. The paper uses the experience of a number of researchers in this field, in particular, the accepted assumptions which do not result in serious loss in modeling accuracy. The governing criteria of similarity were estimated based on the fundamental differential equations of convective heat transfer, so were the conditions under which it is possible to model sodium coolant by using  light water with adequate accuracy. The paper presents the scales of the parameters used for the model - reactor comparison. Dependence curves of certain scales with regard to others are constructed, and the possibility of achieving similarity of certain parameters in modeling was estimated. Recommendations are provided on designing a water test model of the BN reactor and on carrying out experiments using this test model.
eu_rights_str_mv openAccess
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identifier_str_mv 10.18502/keg.v3i3.1627
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instname_str Universidad Tecnológica de Panamá
language eng
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publishDate 2018
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reponame_str Repositorio Institucional de documento digitales de acceso abierto de la UTP
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spelling Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test FacilitySlobodchuk, V.I.Avramova, E.A.Shchennikova, E.M.Shal'kov, D.A.Slobodchuk, V.I.Avramova, E.A.Shchennikova, E.M.Shal'kov, D.A.The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolant using a light water test facility. A large nuclear power reactor (like the BN-1200 project) was selected as a reactor installation to be modeled. To validate the model, the similarity theory and the “black box” method were used. The paper uses the experience of a number of researchers in this field, in particular, the accepted assumptions which do not result in serious loss in modeling accuracy. The governing criteria of similarity were estimated based on the fundamental differential equations of convective heat transfer, so were the conditions under which it is possible to model sodium coolant by using  light water with adequate accuracy. The paper presents the scales of the parameters used for the model - reactor comparison. Dependence curves of certain scales with regard to others are constructed, and the possibility of achieving similarity of certain parameters in modeling was estimated. Recommendations are provided on designing a water test model of the BN reactor and on carrying out experiments using this test model.KnE Publishing2018-02-212018-02-23T17:16:28Z2018-02-23T17:16:28Zinfo:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionapplication/mswordapplication/pdfapplication/xmlhttps://knepublishing.com/index.php/KnE-Engineering/article/view/162710.18502/keg.v3i3.1627http://ridda2.utp.ac.pa/handle/123456789/43432518-6841KnE Engineering; XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"; 279-290reponame:Repositorio Institucional de documento digitales de acceso abierto de la UTPinstname:Universidad Tecnológica de Panamáinstacron:U Tecnológica de Panamáenghttps://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3845https://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3846info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by/4.0/oai:ridda2.utp.ac.pa:123456789/43432021-07-06T16:47:38Z
spellingShingle Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
Slobodchuk, V.I.
status_str publishedVersion
title Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
title_full Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
title_fullStr Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
title_full_unstemmed Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
title_short Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
title_sort Possibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facility
url https://knepublishing.com/index.php/KnE-Engineering/article/view/1627
http://ridda2.utp.ac.pa/handle/123456789/4343