Analysis of a pressurized power reactor using thorium mixed fuel under regular operation

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dc.contributor.authorGOMES, DANIEL de S.pt_BR
dc.contributor.authorSTEFANI, GIOVANNI L. dept_BR
dc.contributor.authorOLIVEIRA, FABIO B.V. dept_BR
dc.coverageInternacionalpt_BR
dc.creator.eventoINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEpt_BR
dc.date.accessioned2020-01-15T16:55:54Z
dc.date.available2020-01-15T16:55:54Z
dc.date.eventoOctober 21-25, 2019pt_BR
dc.description.abstractThis work discusses a parametric study applied to nuclear power generation based on a mixed fuel formed by the composition of thorium-uranium oxide (Th-U)O2. Also, approached in this study the physical neutrons models of a fuel system composed of ThO2 75 wt% and UO2 25 wt%, with 19.5% enrichment of U-235. The thermodynamic features of the thorium-uranium fuel system compared with the properties of uranium dioxide. Thorium-based fuel operating extended fuel cycles reach of over 80 GWd/MTU in a pressurized water reactor (PWR). Homogenous distribution of thorium-based fuel, used on the reactor core, could reduce Pu-239, once U-233 production capacity dependent on Th-232 replacing U-238 in the fuel matrix. The mixed oxide fuel has a lower buildup of Pu-239, causing the linear heat rate distribution slope to flatten and lowering fuel porosity. The release of gaseous fission products models for (Th-U)O2 could have different diffusion coefficients when compared to uranium oxide models. Besides, resulting in lower thermal gradients than UO2 and a reduction in fuel swelling. This parametric study reviews the aspects of radioactive decay chains of uranium and thorium. It founded the simulation using approved nuclear codes, such as SERPENT for neutron physics calculations and the FRAPCON code, which defines the licensing process. The results show that thoria based fuel has a higher performance than UO2 fuel in regular operation and can improve safety margins.pt_BR
dc.event.siglaINACpt_BR
dc.format.extent4996-5009pt_BR
dc.identifier.citationGOMES, DANIEL de S.; STEFANI, GIOVANNI L. de; OLIVEIRA, FABIO B.V. de. Analysis of a pressurized power reactor using thorium mixed fuel under regular operation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4996-5009. Disponível em: http://repositorio.ipen.br/handle/123456789/30708.
dc.identifier.orcidhttps://orcid.org/0000-0002-2181-8704
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/30708
dc.localRio de Janeiropt_BR
dc.local.eventoSantos, SPpt_BR
dc.publisherAssociação Brasileira de Energia Nuclear
dc.rightsopenAccesspt_BR
dc.subjectcomparative evaluations
dc.subjectenthalpy
dc.subjectf codes
dc.subjectmixed oxide fuels
dc.subjectperformance
dc.subjectpwr type reactors
dc.subjects codes
dc.subjectthermal conductivity
dc.subjectthorium
dc.subjecturanium oxides
dc.titleAnalysis of a pressurized power reactor using thorium mixed fuel under regular operationpt_BR
dc.typeTexto completo de eventopt_BR
dspace.entity.typePublication
ipen.autorFABIO BRANCO VAZ DE OLIVEIRA
ipen.autorGIOVANNI LARANJO DE STEFANI
ipen.autorDANIEL DE SOUZA GOMES
ipen.codigoautor931
ipen.codigoautor7606
ipen.codigoautor7670
ipen.contributor.ipenauthorFABIO BRANCO VAZ DE OLIVEIRA
ipen.contributor.ipenauthorGIOVANNI LARANJO DE STEFANI
ipen.contributor.ipenauthorDANIEL DE SOUZA GOMES
ipen.date.recebimento20-01
ipen.event.datapadronizada2019pt_BR
ipen.identifier.ipendoc26360pt_BR
ipen.notas.internasProceedingspt_BR
ipen.type.genreArtigo
relation.isAuthorOfPublicationaf1f1f3a-9f5a-48fe-965f-87b6c7e98ad6
relation.isAuthorOfPublicationcfb52090-3a5f-42c9-bf50-e969bca3d779
relation.isAuthorOfPublication090e1d1e-dfb3-4120-8d6f-1374e82feb2b
relation.isAuthorOfPublication.latestForDiscovery090e1d1e-dfb3-4120-8d6f-1374e82feb2b
sigepi.autor.atividadeOLIVEIRA, FABIO B.V. de:931:420:Npt_BR
sigepi.autor.atividadeSTEFANI, GIOVANNI L. de:7606:310:Npt_BR
sigepi.autor.atividadeGOMES, DANIEL de S.:7670:420:Spt_BR
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