Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO
- Autores
- Lemes, Martín; Soba, Alejandro; Daverio, Hernando; Denis, Alicia Catalina
- Año de publicación
- 2017
- Idioma
- inglés
- Tipo de recurso
- artículo
- Estado
- versión publicada
- Descripción
- The simulation of fuel rod behavior is a complex task that demands not only accurate models to describe the numerous phenomena occurring in the pellet, cladding and internal rod atmosphere but also an adequate interconnection between them. In the last years several models have been incorporated to the DIONISIO code with the purpose of increasing its precision and reliability. After the regrettable events at Fukushima, the need for codes capable of simulating nuclear fuels under accident conditions has come forth. Heat removal occurs in a quite different way than during normal operation and this fact determines a completely new set of conditions for the fuel materials. A detailed description of the different regimes the coolant may exhibit in such a wide variety of scenarios requires a thermal-hydraulic formulation not suitable to be included in a fuel performance code. Moreover, there exist a number of reliable and famous codes that perform this task. Nevertheless, and keeping in mind the purpose of building a code focused on the fuel behavior, a subroutine was developed for the DIONISIO code that performs a simplified analysis of the coolant in a PWR, restricted to the more representative situations and provides to the fuel simulation the boundary conditions necessary to reproduce accidental situations. In the present work this subroutine is described and the results of different comparisons with experimental data and with thermal-hydraulic codes are offered. It is verified that, in spite of its comparative simplicity, the predictions of this module of DIONISIO do not differ significantly from those of the specific, complex codes.
Fil: Lemes, Martín. Comisión Nacional de Energía Atómica; Argentina
Fil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Daverio, Hernando. Comisión Nacional de Energía Atómica; Argentina
Fil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina - Materia
-
Loca
Thermal-Hydraulic Boundary Conditions - Nivel de accesibilidad
- acceso abierto
- Condiciones de uso
- https://creativecommons.org/licenses/by-nc-nd/2.5/ar/
- Repositorio
- Institución
- Consejo Nacional de Investigaciones Científicas y Técnicas
- OAI Identificador
- oai:ri.conicet.gov.ar:11336/38501
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Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIOLemes, MartínSoba, AlejandroDaverio, HernandoDenis, Alicia CatalinaLocaThermal-Hydraulic Boundary Conditionshttps://purl.org/becyt/ford/1.3https://purl.org/becyt/ford/1The simulation of fuel rod behavior is a complex task that demands not only accurate models to describe the numerous phenomena occurring in the pellet, cladding and internal rod atmosphere but also an adequate interconnection between them. In the last years several models have been incorporated to the DIONISIO code with the purpose of increasing its precision and reliability. After the regrettable events at Fukushima, the need for codes capable of simulating nuclear fuels under accident conditions has come forth. Heat removal occurs in a quite different way than during normal operation and this fact determines a completely new set of conditions for the fuel materials. A detailed description of the different regimes the coolant may exhibit in such a wide variety of scenarios requires a thermal-hydraulic formulation not suitable to be included in a fuel performance code. Moreover, there exist a number of reliable and famous codes that perform this task. Nevertheless, and keeping in mind the purpose of building a code focused on the fuel behavior, a subroutine was developed for the DIONISIO code that performs a simplified analysis of the coolant in a PWR, restricted to the more representative situations and provides to the fuel simulation the boundary conditions necessary to reproduce accidental situations. In the present work this subroutine is described and the results of different comparisons with experimental data and with thermal-hydraulic codes are offered. It is verified that, in spite of its comparative simplicity, the predictions of this module of DIONISIO do not differ significantly from those of the specific, complex codes.Fil: Lemes, Martín. Comisión Nacional de Energía Atómica; ArgentinaFil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Daverio, Hernando. Comisión Nacional de Energía Atómica; ArgentinaFil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaElsevier Science Sa2017-04info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/38501Lemes, Martín; Soba, Alejandro; Daverio, Hernando; Denis, Alicia Catalina; Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO; Elsevier Science Sa; Nuclear Engineering and Design; 315; 4-2017; 1-100029-5493CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2017.02.015info:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549317300730info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-nd/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-29T10:18:42Zoai:ri.conicet.gov.ar:11336/38501instacron: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:34982025-09-29 10:18:43.031CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse |
dc.title.none.fl_str_mv |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
title |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
spellingShingle |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO Lemes, Martín Loca Thermal-Hydraulic Boundary Conditions |
title_short |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
title_full |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
title_fullStr |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
title_full_unstemmed |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
title_sort |
Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO |
dc.creator.none.fl_str_mv |
Lemes, Martín Soba, Alejandro Daverio, Hernando Denis, Alicia Catalina |
author |
Lemes, Martín |
author_facet |
Lemes, Martín Soba, Alejandro Daverio, Hernando Denis, Alicia Catalina |
author_role |
author |
author2 |
Soba, Alejandro Daverio, Hernando Denis, Alicia Catalina |
author2_role |
author author author |
dc.subject.none.fl_str_mv |
Loca Thermal-Hydraulic Boundary Conditions |
topic |
Loca Thermal-Hydraulic Boundary Conditions |
purl_subject.fl_str_mv |
https://purl.org/becyt/ford/1.3 https://purl.org/becyt/ford/1 |
dc.description.none.fl_txt_mv |
The simulation of fuel rod behavior is a complex task that demands not only accurate models to describe the numerous phenomena occurring in the pellet, cladding and internal rod atmosphere but also an adequate interconnection between them. In the last years several models have been incorporated to the DIONISIO code with the purpose of increasing its precision and reliability. After the regrettable events at Fukushima, the need for codes capable of simulating nuclear fuels under accident conditions has come forth. Heat removal occurs in a quite different way than during normal operation and this fact determines a completely new set of conditions for the fuel materials. A detailed description of the different regimes the coolant may exhibit in such a wide variety of scenarios requires a thermal-hydraulic formulation not suitable to be included in a fuel performance code. Moreover, there exist a number of reliable and famous codes that perform this task. Nevertheless, and keeping in mind the purpose of building a code focused on the fuel behavior, a subroutine was developed for the DIONISIO code that performs a simplified analysis of the coolant in a PWR, restricted to the more representative situations and provides to the fuel simulation the boundary conditions necessary to reproduce accidental situations. In the present work this subroutine is described and the results of different comparisons with experimental data and with thermal-hydraulic codes are offered. It is verified that, in spite of its comparative simplicity, the predictions of this module of DIONISIO do not differ significantly from those of the specific, complex codes. Fil: Lemes, Martín. Comisión Nacional de Energía Atómica; Argentina Fil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina Fil: Daverio, Hernando. Comisión Nacional de Energía Atómica; Argentina Fil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina |
description |
The simulation of fuel rod behavior is a complex task that demands not only accurate models to describe the numerous phenomena occurring in the pellet, cladding and internal rod atmosphere but also an adequate interconnection between them. In the last years several models have been incorporated to the DIONISIO code with the purpose of increasing its precision and reliability. After the regrettable events at Fukushima, the need for codes capable of simulating nuclear fuels under accident conditions has come forth. Heat removal occurs in a quite different way than during normal operation and this fact determines a completely new set of conditions for the fuel materials. A detailed description of the different regimes the coolant may exhibit in such a wide variety of scenarios requires a thermal-hydraulic formulation not suitable to be included in a fuel performance code. Moreover, there exist a number of reliable and famous codes that perform this task. Nevertheless, and keeping in mind the purpose of building a code focused on the fuel behavior, a subroutine was developed for the DIONISIO code that performs a simplified analysis of the coolant in a PWR, restricted to the more representative situations and provides to the fuel simulation the boundary conditions necessary to reproduce accidental situations. In the present work this subroutine is described and the results of different comparisons with experimental data and with thermal-hydraulic codes are offered. It is verified that, in spite of its comparative simplicity, the predictions of this module of DIONISIO do not differ significantly from those of the specific, complex codes. |
publishDate |
2017 |
dc.date.none.fl_str_mv |
2017-04 |
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/11336/38501 Lemes, Martín; Soba, Alejandro; Daverio, Hernando; Denis, Alicia Catalina; Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO; Elsevier Science Sa; Nuclear Engineering and Design; 315; 4-2017; 1-10 0029-5493 CONICET Digital CONICET |
url |
http://hdl.handle.net/11336/38501 |
identifier_str_mv |
Lemes, Martín; Soba, Alejandro; Daverio, Hernando; Denis, Alicia Catalina; Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO; Elsevier Science Sa; Nuclear Engineering and Design; 315; 4-2017; 1-10 0029-5493 CONICET Digital CONICET |
dc.language.none.fl_str_mv |
eng |
language |
eng |
dc.relation.none.fl_str_mv |
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2017.02.015 info:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549317300730 |
dc.rights.none.fl_str_mv |
info:eu-repo/semantics/openAccess https://creativecommons.org/licenses/by-nc-nd/2.5/ar/ |
eu_rights_str_mv |
openAccess |
rights_invalid_str_mv |
https://creativecommons.org/licenses/by-nc-nd/2.5/ar/ |
dc.format.none.fl_str_mv |
application/pdf application/pdf application/pdf |
dc.publisher.none.fl_str_mv |
Elsevier Science Sa |
publisher.none.fl_str_mv |
Elsevier Science Sa |
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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1844614151450656768 |
score |
13.070432 |