TRISO fuel thermal simulations in the LS-VHTR

dc.creatorMario Cerrogrande Ramos
dc.creatorMaria Elizabeth Scari
dc.creatorAntonella Lombardi Costa
dc.creatorClaubia Pereira Bezerra Lima
dc.creatorMaria Auxiliadora Fortini Veloso
dc.date.accessioned2022-06-15T18:46:09Z
dc.date.accessioned2025-09-08T23:22:00Z
dc.date.available2022-06-15T18:46:09Z
dc.date.issued2019-06
dc.format.mimetypepdf
dc.identifier.doihttps://doi.org/10.15392/bjrs.v7i2B.648
dc.identifier.issn2319-0612
dc.identifier.urihttps://hdl.handle.net/1843/42546
dc.languageeng
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofBrazilian Journal of Radiation Sciences
dc.rightsAcesso Aberto
dc.subjectEnergia nuclear
dc.subject.otherTriso
dc.subject.otherLS-VHTR
dc.subject.otherRelap5-3D
dc.subject.otherLi2BeF4
dc.titleTRISO fuel thermal simulations in the LS-VHTR
dc.typeArtigo de periódico
local.citation.epage17
local.citation.issue2B
local.citation.spage1
local.citation.volume7
local.description.resumoThe liquid-salt-cooled very high-temperature reactor (LS-VHTR) is a reactor that presents very good characteristics in terms of energy production and safety aspects. It uses as fuel the TRISO particles immersed in a graphite matrix with a cylindrical shape called fuel compact, as moderator graphite and as coolant liquid salt Li2BeF4 called Flibe. This work evaluates the thermal hydraulic performance of the heat removal system and the reactor core by performing different simplifications to represent the reactor core and the fuel compact under steady-state conditions, starting the modeling from a single fuel element, until complete the studies with the entire core model developed in the RELAP5-3D code. Two models were considered for representation of the fuel compact, homogeneous and non-homogeneous models, as well as different geometries of the heat structures was considered. The aim to develop several models was to compare the thermal hydraulic characteristics resulting from the construction of a more economical and less discretized model with much more refined models that can lead to more complexes analyzes to representing TRISO effect particles in the fuel compact. The different results found, mainly, for the core temperature distributions are presented and discussed.
local.publisher.countryBrasil
local.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
local.publisher.initialsUFMG
local.url.externahttps://www.bjrs.org.br/revista/index.php/REVISTA/article/view/648

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