VHTR, ADS, and PWR Spent Nuclear Fuel Analysis

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dc.creatorJean Anderson Dias Salomé
dc.creatorFabiano Cardoso da Silva
dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorFernando Pereira Faria
dc.creatorGraiciany de Paula Barros
dc.creatorClaubia Pereira Bezerra Lima
dc.date.accessioned2023-07-21T17:46:15Z
dc.date.accessioned2025-09-09T01:33:28Z
dc.date.available2023-07-21T17:46:15Z
dc.date.issued2016
dc.identifier.doihttps://doi.org/10.1016/j.proche.2016.10.036
dc.identifier.issn1876-6196
dc.identifier.urihttps://hdl.handle.net/1843/56849
dc.languagepor
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofInternational atalante conference on nuclear chemistry for sustainable fuel cycles
dc.rightsAcesso Aberto
dc.subjectCombustivel
dc.subjectReatores nucleares
dc.subject.otherReactors VHTR
dc.subject.otherADS
dc.subject.otherPWR
dc.subject.otherReprocessing fuel
dc.subject.otherNuclear fuel cycle
dc.subject.otherSCALE 6.0
dc.subject.otherMONTEBURNS and ORIGEN 2.1
dc.titleVHTR, ADS, and PWR Spent Nuclear Fuel Analysis
dc.typeArtigo de evento
local.citation.epage262
local.citation.issue5
local.citation.spage255
local.description.resumoThe aim of this study is to analyze and compare the discharged-spent fuel of three types of nuclear systems: a Very High-Temperature Gas Reactor (VHTR), a lead-cooled Accelerator-Driven System (ADS) and a standard Pressurized Water Reactor (PWR). The two first systems, VHTR, and ADS were designed to use reprocessed fuels. UREX+ and GANEX techniques were used for the reprocessing processes respectively. The fuel burnup simulated for the systems in other works have been used to obtain the final composition of the spent fuel discharged. After discharge, the radioactivity, the radiotoxicity, and the decay heat were evaluated through the ORIGEN 2.1 code until 107 years and compared to the literature.
local.identifier.orcidhttps://orcid.org/0000-0002-2960-3150
local.identifier.orcidhttps://orcid.org/0000-0001-7909-9063
local.identifier.orcidhttps://orcid.org/0000-0001-5999-9961
local.publisher.countryBrasil
local.publisher.departmentENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR
local.publisher.initialsUFMG
local.url.externahttps://www.sciencedirect.com/science/article/pii/S187661961630078X?via%3Dihub

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