Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor

The increasing deployment of renewable energy sources and greater electrification of demand is requiring more frequent use of load following in pressurised water reactors (PWRs) . A limiting aspect with respect to load following is the thermo-mechanical behaviour of the fuel. Hence a greater use of...

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Authors: Peakman, Aiden, Gregg, Robert, Bennett, Tom, Casamor Vidal, Max|||0000-0001-8570-5365, Martínez Quiroga, Víctor Manuel|||0000-0003-0096-8348, Freixa Terradas, Jordi|||0000-0002-8173-3921, Pericas Casals, Raimon|||0000-0001-7050-1028, Rossiter, Glyn
Format: article
Publication Date:2022
Country:España
Institution:Universitat Politècnica de Catalunya (UPC)
Repository:UPCommons. Portal del coneixement obert de la UPC
Language:English
OAI Identifier:oai:upcommons.upc.edu:2117/374764
Online Access:https://hdl.handle.net/2117/374764
https://dx.doi.org/10.1016/j.anucene.2022.109086
Access Level:Open access
Keyword:Pressurized water reactors
Renewable energy sources
Load following
Extended reduced power operation
ENIGMA
RELAP
PARCS
Fuel performance
Reactors nuclears d'aigua a pressió
Energies renovables
Àrees temàtiques de la UPC::Física
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spelling Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactorPeakman, AidenGregg, RobertBennett, TomCasamor Vidal, Max|||0000-0001-8570-5365Martínez Quiroga, Víctor Manuel|||0000-0003-0096-8348Freixa Terradas, Jordi|||0000-0002-8173-3921Pericas Casals, Raimon|||0000-0001-7050-1028Rossiter, GlynPressurized water reactorsRenewable energy sourcesLoad followingExtended reduced power operationENIGMARELAPPARCSFuel performanceReactors nuclears d'aigua a pressióEnergies renovablesÀrees temàtiques de la UPC::FísicaThe increasing deployment of renewable energy sources and greater electrification of demand is requiring more frequent use of load following in pressurised water reactors (PWRs) . A limiting aspect with respect to load following is the thermo-mechanical behaviour of the fuel. Hence a greater use of best-estimate multi-physics tools that can more accurately capture such behaviour during load following manoeuvres – in particular, extended reduced power operation (ERPO) – has become important in recent years. To this end, we have developed a coupled, whole-core analysis framework and demonstrated it with a new generic PWR model. The demonstration is for uncontrolled RCCA bank withdrawal at power (URWAP) faults following a period of ERPO, since such scenarios are often limiting with respect to fuel integrity. The coupled, whole-core analysis framework that was developed consists of the PARCS neutronics code, the RELAP and CTF thermal–hydraulics codes, the ENIGMA fuel performance code, and the NEXUS platform for whole-core fuel performance. The generic PWR model constructed is for a 1240 MWe plant with a modern core design (maximum assembly burnup of 51.0 GWd/tHM, cycle length of 16 months, and an average fuel residence time of 2.3 cycles per assembly). Previous work in the literature on URWAP faults has focused on coupled neutronics and thermal–hydraulics analysis, with fuel performance assessment and the effects of load following neglected. These shortcomings are therefore addressed here. From a fuel performance perspective no fuel was predicted to fail due to pellet-clad interaction (PCI). Of the remaining failure indicators, margin to clad yield stress was most limiting, although no failure was predicted in all cases under the scenarios considered.Peer Reviewed20222022-08-0120222022-10-20journal articlehttp://purl.org/coar/resource_type/c_6501VoRhttp://purl.org/coar/version/c_970fb48d4fbd8a85info:eu-repo/semantics/articleapplication/pdfapplication/pdfhttps://hdl.handle.net/2117/374764https://dx.doi.org/10.1016/j.anucene.2022.109086reponame:UPCommons. Portal del coneixement obert de la UPCinstname:Universitat Politècnica de Catalunya (UPC)Inglésengopen accesshttp://purl.org/coar/access_right/c_abf2Attribution-NonCommercial-NoDerivatives 4.0 Internationalhttp://creativecommons.org/licenses/by-nc-nd/4.0/info:eu-repo/semantics/openAccessoai:upcommons.upc.edu:2117/3747642026-05-27T15:37:01Z
dc.title.none.fl_str_mv Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
title Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
spellingShingle Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
Peakman, Aiden
Pressurized water reactors
Renewable energy sources
Load following
Extended reduced power operation
ENIGMA
RELAP
PARCS
Fuel performance
Reactors nuclears d'aigua a pressió
Energies renovables
Àrees temàtiques de la UPC::Física
title_short Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
title_full Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
title_fullStr Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
title_full_unstemmed Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
title_sort Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
dc.creator.none.fl_str_mv Peakman, Aiden
Gregg, Robert
Bennett, Tom
Casamor Vidal, Max|||0000-0001-8570-5365
Martínez Quiroga, Víctor Manuel|||0000-0003-0096-8348
Freixa Terradas, Jordi|||0000-0002-8173-3921
Pericas Casals, Raimon|||0000-0001-7050-1028
Rossiter, Glyn
author Peakman, Aiden
author_facet Peakman, Aiden
Gregg, Robert
Bennett, Tom
Casamor Vidal, Max|||0000-0001-8570-5365
Martínez Quiroga, Víctor Manuel|||0000-0003-0096-8348
Freixa Terradas, Jordi|||0000-0002-8173-3921
Pericas Casals, Raimon|||0000-0001-7050-1028
Rossiter, Glyn
author_role author
author2 Gregg, Robert
Bennett, Tom
Casamor Vidal, Max|||0000-0001-8570-5365
Martínez Quiroga, Víctor Manuel|||0000-0003-0096-8348
Freixa Terradas, Jordi|||0000-0002-8173-3921
Pericas Casals, Raimon|||0000-0001-7050-1028
Rossiter, Glyn
author2_role author
author
author
author
author
author
author
dc.subject.none.fl_str_mv Pressurized water reactors
Renewable energy sources
Load following
Extended reduced power operation
ENIGMA
RELAP
PARCS
Fuel performance
Reactors nuclears d'aigua a pressió
Energies renovables
Àrees temàtiques de la UPC::Física
topic Pressurized water reactors
Renewable energy sources
Load following
Extended reduced power operation
ENIGMA
RELAP
PARCS
Fuel performance
Reactors nuclears d'aigua a pressió
Energies renovables
Àrees temàtiques de la UPC::Física
description The increasing deployment of renewable energy sources and greater electrification of demand is requiring more frequent use of load following in pressurised water reactors (PWRs) . A limiting aspect with respect to load following is the thermo-mechanical behaviour of the fuel. Hence a greater use of best-estimate multi-physics tools that can more accurately capture such behaviour during load following manoeuvres – in particular, extended reduced power operation (ERPO) – has become important in recent years. To this end, we have developed a coupled, whole-core analysis framework and demonstrated it with a new generic PWR model. The demonstration is for uncontrolled RCCA bank withdrawal at power (URWAP) faults following a period of ERPO, since such scenarios are often limiting with respect to fuel integrity. The coupled, whole-core analysis framework that was developed consists of the PARCS neutronics code, the RELAP and CTF thermal–hydraulics codes, the ENIGMA fuel performance code, and the NEXUS platform for whole-core fuel performance. The generic PWR model constructed is for a 1240 MWe plant with a modern core design (maximum assembly burnup of 51.0 GWd/tHM, cycle length of 16 months, and an average fuel residence time of 2.3 cycles per assembly). Previous work in the literature on URWAP faults has focused on coupled neutronics and thermal–hydraulics analysis, with fuel performance assessment and the effects of load following neglected. These shortcomings are therefore addressed here. From a fuel performance perspective no fuel was predicted to fail due to pellet-clad interaction (PCI). Of the remaining failure indicators, margin to clad yield stress was most limiting, although no failure was predicted in all cases under the scenarios considered.
publishDate 2022
dc.date.none.fl_str_mv 2022
2022-08-01
2022
2022-10-20
dc.type.none.fl_str_mv journal article
http://purl.org/coar/resource_type/c_6501
VoR
http://purl.org/coar/version/c_970fb48d4fbd8a85
dc.type.openaire.fl_str_mv info:eu-repo/semantics/article
format article
dc.identifier.none.fl_str_mv https://hdl.handle.net/2117/374764
https://dx.doi.org/10.1016/j.anucene.2022.109086
url https://hdl.handle.net/2117/374764
https://dx.doi.org/10.1016/j.anucene.2022.109086
dc.language.none.fl_str_mv Inglés
eng
language_invalid_str_mv Inglés
language eng
dc.rights.none.fl_str_mv open access
http://purl.org/coar/access_right/c_abf2
Attribution-NonCommercial-NoDerivatives 4.0 International
http://creativecommons.org/licenses/by-nc-nd/4.0/
dc.rights.openaire.fl_str_mv info:eu-repo/semantics/openAccess
rights_invalid_str_mv open access
http://purl.org/coar/access_right/c_abf2
Attribution-NonCommercial-NoDerivatives 4.0 International
http://creativecommons.org/licenses/by-nc-nd/4.0/
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.source.none.fl_str_mv reponame:UPCommons. Portal del coneixement obert de la UPC
instname:Universitat Politècnica de Catalunya (UPC)
instname_str Universitat Politècnica de Catalunya (UPC)
reponame_str UPCommons. Portal del coneixement obert de la UPC
collection UPCommons. Portal del coneixement obert de la UPC
repository.name.fl_str_mv
repository.mail.fl_str_mv
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