Reprocessing techniques of LWR spent fuel for reutilization in hybrid systems and IV generation reactors

Página do item simplificado
dc.creatorWilmer Aruquipa
dc.creatorCarlos Eduardo Velasquez Cabrera
dc.creatorGraiciany p. Barros
dc.creatorMaria Auxiliadora f. Veloso
dc.creatorAntonella l. Costa
dc.creatorClaubia Pereira
dc.date.accessioned2025-02-14T19:40:36Z
dc.date.accessioned2025-09-08T23:22:39Z
dc.date.available2025-02-14T19:40:36Z
dc.date.issued2017
dc.format.mimetypepdf
dc.identifier.urihttps://hdl.handle.net/1843/80096
dc.languageeng
dc.publisherUniversidade Federal de Minas Gerais
dc.relation.ispartofInternational Nuclear Atlantic Conference
dc.rightsAcesso Aberto
dc.subjectReatores nucleares
dc.subjectIrradiação
dc.subjectCombustíveis nucleares
dc.subject.otherNuclear technology
dc.subject.otherRadiotoxicity
dc.subject.otherNuclear reactors
dc.subject.otherSpent fuel
dc.titleReprocessing techniques of LWR spent fuel for reutilization in hybrid systems and IV generation reactors
dc.typeArtigo de evento
local.citation.epage12
local.citation.spage1
local.description.resumoSince the era of nuclear technology begins, nuclear reactors have been produced spent fuel. This spent fuel contains material that could be recycle and reprocessed by different processes. All these processes aim to reduce the contribution to the final repository through the re-utilization of the nuclear material. Therefore, some new reprocessing options with non-proliferation characteristics have been proposed and the goal is to compare the different techniques used to maximize the effectiveness of the spent fuel utilization and to reduce the volume and long-term radiotoxicity of high-level waste by irradiation with neutron with high energy such as the ones created in hybrid reactors. In order to compare different recovery methods, the cross sections of fuels are calculated with de MCNP code, the first set consists of thorium-232 spiked with the reprocessed material and the second set in depleted uranium that containing 4.5% of U-235 spiked with the reprocessed material; These sets in turn are compared with the cross section of the 𝑈𝑈𝑂𝑂2 in order to evaluate the efficiency of the reprocessed fuel as nuclear fuel.
local.identifier.orcidhttps://orcid.org/0000-0001-6782-8329
local.identifier.orcidhttps://orcid.org/0000-0002-2960-3150
local.identifier.orcidhttps://orcid.org/0000-0001-7909-9063
local.identifier.orcidhttps://orcid.org/0000-0001-8618-8195
local.identifier.orcidhttps://orcid.org/0000-0002-2445-3800
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://inis.iaea.org/records/z5wsj-hxp77

Arquivos

Pacote original

Agora exibindo 1 - 1 de 1
Imagem de Miniatura
Nome:
REPROCESSING TECHNIQUES OF LWR SPENT FUEL FOR (1).pdf
Tamanho:
552 KB
Formato:
Adobe Portable Document Format
Baixar

Licença do pacote

Agora exibindo 1 - 1 de 1
Imagem de Miniatura
Nome:
License.txt
Tamanho:
1.99 KB
Formato:
Plain Text
Descrição:
Baixar

Coleções

Artigo de Evento

Logo UFMG