CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE

Calculating the energy release in fuel elements is an important aspect of the modeling and design of nuclear reactors. Most of the energy is produced by fission, but a non-negligible percentage is coming from neutron capture reactions, such as (n, γ) or (n, α). We implement a previously developed me...

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1. Verfasser: R. B, Bahdanovich (author)
Weitere Verfasser: K., Pázmán (author), G. V., Tikhomirov (author)
Format: article
Sprache:Englisch
Veröffentlicht: 2018
Online-Zugang:https://knepublishing.com/index.php/KnE-Engineering/article/view/1648
http://ridda2.utp.ac.pa/handle/123456789/4333
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author R. B, Bahdanovich
author2 K., Pázmán
G. V., Tikhomirov
author2_role author
author
author_browse G. V., Tikhomirov
K., Pázmán
R. B, Bahdanovich
author_facet R. B, Bahdanovich
K., Pázmán
G. V., Tikhomirov
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 R. B, Bahdanovich
K., Pázmán
G. V., Tikhomirov
R. B, Bahdanovich
K., Pázmán
G. V., Tikhomirov
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/1648
10.18502/keg.v3i3.1648
http://ridda2.utp.ac.pa/handle/123456789/4333
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/1648/3887
https://knepublishing.com/index.php/KnE-Engineering/article/view/1648/3888
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"; 473-480
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 CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
description Calculating the energy release in fuel elements is an important aspect of the modeling and design of nuclear reactors. Most of the energy is produced by fission, but a non-negligible percentage is coming from neutron capture reactions, such as (n, γ) or (n, α). We implement a previously developed method for the calculation of effective energy release using Serpent Monte Carlo code. We investigate the percentage of capture component in effective energy release for various models of VVER-1000 fuel: firstly, an equivalent cell, then fresh fuel assemblies of different compositions, differing in fuel enrichment and the presence of burnable absorbers. The results are compared to similar calculations previously done in MCNP 4 and MCU 5.
eu_rights_str_mv openAccess
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identifier_str_mv 10.18502/keg.v3i3.1648
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publishDate 2018
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publisher.none.fl_str_mv KnE Publishing
reponame_str Repositorio Institucional de documento digitales de acceso abierto de la UTP
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spelling CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODER. B, BahdanovichK., PázmánG. V., TikhomirovR. B, BahdanovichK., PázmánG. V., TikhomirovCalculating the energy release in fuel elements is an important aspect of the modeling and design of nuclear reactors. Most of the energy is produced by fission, but a non-negligible percentage is coming from neutron capture reactions, such as (n, γ) or (n, α). We implement a previously developed method for the calculation of effective energy release using Serpent Monte Carlo code. We investigate the percentage of capture component in effective energy release for various models of VVER-1000 fuel: firstly, an equivalent cell, then fresh fuel assemblies of different compositions, differing in fuel enrichment and the presence of burnable absorbers. The results are compared to similar calculations previously done in MCNP 4 and MCU 5.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/164810.18502/keg.v3i3.1648http://ridda2.utp.ac.pa/handle/123456789/43332518-6841KnE Engineering; XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"; 473-480reponame: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/1648/3887https://knepublishing.com/index.php/KnE-Engineering/article/view/1648/3888info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by/4.0/oai:ridda2.utp.ac.pa:123456789/43332021-07-06T16:47:38Z
spellingShingle CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
R. B, Bahdanovich
status_str publishedVersion
title CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
title_full CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
title_fullStr CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
title_full_unstemmed CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
title_short CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
title_sort CALCULATION OF NEUTRON-CAPTURE REACTIONS CONTRIBUTION TO ENERGY RELEASE IN VVER-1000 USING SERPENT CODE
url https://knepublishing.com/index.php/KnE-Engineering/article/view/1648
http://ridda2.utp.ac.pa/handle/123456789/4333