Safety-informed design of lead-cooled reactors on mobile platforms

Nuclear power has a prominent role to play in the energy landscape of the 21st century. To- gether with large reactor designs that make the most out of economies of scale, small, modular reactors (SMR) may also play a role thanks to their potential modular, factory-based and fast deployment, which h...

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Detalles Bibliográficos
Autor: Sanchis Ramírez, Guillem
Tipo de recurso: tesis de maestría
Fecha de publicación:2022
País:España
Institución:Universitat Politècnica de Catalunya (UPC)
Repositorio:UPCommons. Portal del coneixement obert de la UPC
Idioma:inglés
OAI Identifier:oai:upcommons.upc.edu:2117/367434
Acceso en línea:https://hdl.handle.net/2117/367434
Access Level:acceso abierto
Palabra clave:Nuclear reactors
Cooling
Reactors nuclears
Refrigeració
Àrees temàtiques de la UPC::Energies::Energia nuclear
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spelling Safety-informed design of lead-cooled reactors on mobile platformsSanchis Ramírez, GuillemNuclear reactorsCoolingReactors nuclearsRefrigeracióÀrees temàtiques de la UPC::Energies::Energia nuclearNuclear power has a prominent role to play in the energy landscape of the 21st century. To- gether with large reactor designs that make the most out of economies of scale, small, modular reactors (SMR) may also play a role thanks to their potential modular, factory-based and fast deployment, which have the potential to minimize the capital cost of nuclear, which is one of its main drawbacks. Among such designs, lead-cooled fast reactors (LFR) present some unique strengths, among others their lack of pressurization of the primary system and their potential to passively remove decay heat by means of natural convection. The SUNRISE project, in Sweden, is an effort by, among others, KTH to prove the feasability of this technology. In that context, the analytical design tool ADELE, which draws from the BELLA code produced at KTH, is developed. Its goal is to provide a fast-to-iterate algorithm that uses basic physics constraints to obtain the core design without relying on more computationally costly methods, like Monte Carlo simulations, which are regularly used for that purpose. Specifically, a system that is capable of removing all the residual heat via convective cooling is obtained from a short list of basic input values. This algorithm is implemented into a mobile application, with the goal of being available to Nuclear Engineering students. The resulting code is capable of replicating reference core designs with a reasonable degree of accuracy, given the simplicity of the assumptions used in the process.Universitat Politècnica de CatalunyaWallenius, JanneBatet Miracle, Lluís20222022-05-1320222022-05-17master thesishttp://purl.org/coar/resource_type/c_bdccNAhttp://purl.org/coar/version/c_be7fb7dd8ff6fe43info:eu-repo/semantics/masterThesisapplication/pdfhttps://hdl.handle.net/2117/367434reponame:UPCommons. Portal del coneixement obert de la UPCinstname:Universitat Politècnica de Catalunya (UPC)Inglésengopen accesshttp://purl.org/coar/access_right/c_abf2http://creativecommons.org/licenses/by-nc-sa/3.0/es/info:eu-repo/semantics/openAccessoai:upcommons.upc.edu:2117/3674342026-05-27T15:37:01Z
dc.title.none.fl_str_mv Safety-informed design of lead-cooled reactors on mobile platforms
title Safety-informed design of lead-cooled reactors on mobile platforms
spellingShingle Safety-informed design of lead-cooled reactors on mobile platforms
Sanchis Ramírez, Guillem
Nuclear reactors
Cooling
Reactors nuclears
Refrigeració
Àrees temàtiques de la UPC::Energies::Energia nuclear
title_short Safety-informed design of lead-cooled reactors on mobile platforms
title_full Safety-informed design of lead-cooled reactors on mobile platforms
title_fullStr Safety-informed design of lead-cooled reactors on mobile platforms
title_full_unstemmed Safety-informed design of lead-cooled reactors on mobile platforms
title_sort Safety-informed design of lead-cooled reactors on mobile platforms
dc.creator.none.fl_str_mv Sanchis Ramírez, Guillem
author Sanchis Ramírez, Guillem
author_facet Sanchis Ramírez, Guillem
author_role author
dc.contributor.none.fl_str_mv Wallenius, Janne
Batet Miracle, Lluís
dc.subject.none.fl_str_mv Nuclear reactors
Cooling
Reactors nuclears
Refrigeració
Àrees temàtiques de la UPC::Energies::Energia nuclear
topic Nuclear reactors
Cooling
Reactors nuclears
Refrigeració
Àrees temàtiques de la UPC::Energies::Energia nuclear
description Nuclear power has a prominent role to play in the energy landscape of the 21st century. To- gether with large reactor designs that make the most out of economies of scale, small, modular reactors (SMR) may also play a role thanks to their potential modular, factory-based and fast deployment, which have the potential to minimize the capital cost of nuclear, which is one of its main drawbacks. Among such designs, lead-cooled fast reactors (LFR) present some unique strengths, among others their lack of pressurization of the primary system and their potential to passively remove decay heat by means of natural convection. The SUNRISE project, in Sweden, is an effort by, among others, KTH to prove the feasability of this technology. In that context, the analytical design tool ADELE, which draws from the BELLA code produced at KTH, is developed. Its goal is to provide a fast-to-iterate algorithm that uses basic physics constraints to obtain the core design without relying on more computationally costly methods, like Monte Carlo simulations, which are regularly used for that purpose. Specifically, a system that is capable of removing all the residual heat via convective cooling is obtained from a short list of basic input values. This algorithm is implemented into a mobile application, with the goal of being available to Nuclear Engineering students. The resulting code is capable of replicating reference core designs with a reasonable degree of accuracy, given the simplicity of the assumptions used in the process.
publishDate 2022
dc.date.none.fl_str_mv 2022
2022-05-13
2022
2022-05-17
dc.type.none.fl_str_mv master thesis
http://purl.org/coar/resource_type/c_bdcc
NA
http://purl.org/coar/version/c_be7fb7dd8ff6fe43
dc.type.openaire.fl_str_mv info:eu-repo/semantics/masterThesis
format masterThesis
dc.identifier.none.fl_str_mv https://hdl.handle.net/2117/367434
url https://hdl.handle.net/2117/367434
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

http://creativecommons.org/licenses/by-nc-sa/3.0/es/
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

http://creativecommons.org/licenses/by-nc-sa/3.0/es/
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
dc.publisher.none.fl_str_mv Universitat Politècnica de Catalunya
publisher.none.fl_str_mv Universitat Politècnica de Catalunya
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
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