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dc.contributor.author
Lemes Lapasta, Martín Rodolfo
dc.contributor.author
Denis, Alicia Catalina
dc.contributor.author
Soba, Alejandro
dc.date.available
2021-02-10T17:41:29Z
dc.date.issued
2019-04
dc.identifier.citation
Lemes Lapasta, Martín Rodolfo; Denis, Alicia Catalina; Soba, Alejandro; Simulation of nuclear fuel behavior in accident conditions with the DIONISIO code; American Society of Mechanical Engineers; Journal of Nuclear Engineering and Radiation Science; 5; 2; 4-2019; 1-32
dc.identifier.issn
2332-8983
dc.identifier.uri
http://hdl.handle.net/11336/125342
dc.description.abstract
DIONISIO is a computer code designed to simulate the behavior of one nuclear fuel rod during its permanence within the reactor. Starting from the power history and the external conditions to which the rod is subjected, the code predicts all the meaningful variables of the system. Its application range has been recently extended to include accidental conditions, in particular the so-called loss of coolant accidents (LOCA). In order to make realistic predictions, the conditions in the rod environment have been taken into account since they represent the boundary conditions with which the differential equations describing the fuel phenomena are solved. Without going into the details of the thermalhydraulic modeling, which is the task of the specific codes, a simplified description of the conditions in the cooling channel during a LOCA event has been developed and incorporated as a subroutine of DIONISIO. This has led to an improvement of the fuel behavior simulation, which is evidenced by the considerable number of comparisons with experiments carried out, many of them reported in this paper. Moreover, this work describes a model of high temperature capture and release of hydrogen in the nuclear fuel cladding, in scenarios typical of LOCA events. The corresponding computational model is being separately tested and will be next included in the DIONISIO thermal-hydraulic module.
dc.format
application/pdf
dc.language.iso
eng
dc.publisher
American Society of Mechanical Engineers
dc.rights
info:eu-repo/semantics/restrictedAccess
dc.rights.uri
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
dc.subject
NUCLEAR FUELS
dc.subject
ACCICENTS
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DIONISIO
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FEM
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Ingeniería de los Materiales
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Ingeniería de los Materiales
dc.subject.classification
INGENIERÍAS Y TECNOLOGÍAS
dc.title
Simulation of nuclear fuel behavior in accident conditions with the DIONISIO code
dc.type
info:eu-repo/semantics/article
dc.type
info:ar-repo/semantics/artículo
dc.type
info:eu-repo/semantics/publishedVersion
dc.date.updated
2021-02-09T18:50:10Z
dc.identifier.eissn
2332-8975
dc.journal.volume
5
dc.journal.number
2
dc.journal.pagination
1-32
dc.journal.pais
Estados Unidos
dc.description.fil
Fil: Lemes Lapasta, Martín Rodolfo. Comision Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear; Argentina
dc.description.fil
Fil: Denis, Alicia Catalina. Comision Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear; Argentina
dc.description.fil
Fil: Soba, Alejandro. Comision Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
dc.journal.title
Journal of Nuclear Engineering and Radiation Science
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/url/https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/2/020903/725863/Simulation-of-Nuclear-Fuel-Behavior-in-Accident?redirectedFrom=fulltext
dc.relation.alternativeid
info:eu-repo/semantics/altIdentifier/doi/https://doi.org/10.1115/1.4042705
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