High density fuels using dispersion and monolithic fuel

Detalhes bibliográficos
Autor(a) principal: GOMES, DANIEL S.
Data de Publicação: 2018
Outros Autores: SILVA, ANTONIO T., ABE, ALFREDO Y., MUNIZ, RAFAEL O.R., GIOVEDI, CLAUDIA, INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/28189
Resumo: Fuel plates used in high-performance research reactors need to be converted to low-enrichment uranium fuel; the fuel option based on a monolithic formulation requires alloys to contain 6 ??? 10 wt% Mo. In this case, the fuel plates are composed of the metallic alloy U-10Mo surrounded by a thin zirconium layer encapsulated in aluminum cladding. This study reviewed the physical properties of monolithic forms. The constraints produced during the manufacturing process were analyzed and compared to those of dispersed fuel. The bonding process used for dispersion fuels differs from the techniques applied to foil bonding used for pure alloys. The quality of monolithic plates depends on the fabrication method, which usually involves hot isostatic pressing and the thermal annealing effect of residual stress, which degrades the uranium cubic phase. The preservation of the metastable phase has considerable influence on fuel performance. The physical properties of the foil fuel under irradiation are superior to those of aluminum-dispersed fuels. The fuel meat, using zirconium as the diffusion barrier, prevents the interaction layer from becoming excessively thick. The problem with dispersed fuel is breakaway swelling with a medium fission rate. It has been observed that the fuel dispersed in aluminum was minimized in monolithic forms. The pure alloys exhibited a suitable response from a rate at least twice as much as the fission rate of dispersions. The foils can support fissile material concentration combined with a reduced swelling rate.
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spelling 2018-01-02T13:04:24Z2018-01-02T13:04:24ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28189Fuel plates used in high-performance research reactors need to be converted to low-enrichment uranium fuel; the fuel option based on a monolithic formulation requires alloys to contain 6 ??? 10 wt% Mo. In this case, the fuel plates are composed of the metallic alloy U-10Mo surrounded by a thin zirconium layer encapsulated in aluminum cladding. This study reviewed the physical properties of monolithic forms. The constraints produced during the manufacturing process were analyzed and compared to those of dispersed fuel. The bonding process used for dispersion fuels differs from the techniques applied to foil bonding used for pure alloys. The quality of monolithic plates depends on the fabrication method, which usually involves hot isostatic pressing and the thermal annealing effect of residual stress, which degrades the uranium cubic phase. The preservation of the metastable phase has considerable influence on fuel performance. The physical properties of the foil fuel under irradiation are superior to those of aluminum-dispersed fuels. The fuel meat, using zirconium as the diffusion barrier, prevents the interaction layer from becoming excessively thick. The problem with dispersed fuel is breakaway swelling with a medium fission rate. It has been observed that the fuel dispersed in aluminum was minimized in monolithic forms. The pure alloys exhibited a suitable response from a rate at least twice as much as the fission rate of dispersions. The foils can support fissile material concentration combined with a reduced swelling rate.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-02T13:04:24Z No. of bitstreams: 1 24014.pdf: 603768 bytes, checksum: 7fb9f6358d48a3232120b58f1f5c15ca (MD5)Made available in DSpace on 2018-01-02T13:04:24Z (GMT). No. of bitstreams: 1 24014.pdf: 603768 bytes, checksum: 7fb9f6358d48a3232120b58f1f5c15ca (MD5)Associa????o Brasileira de Energia Nuclearaluminiumcladdingdispersion nuclear fuelsfoilsfuel elementsfuel platesirradiationmolybdenum alloysphysical propertiesswellinguranium alloyszirconiumHigh density fuels using dispersion and monolithic fuelinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGGOMES, DANIEL S.SILVA, ANTONIO T.ABE, ALFREDO Y.MUNIZ, RAFAEL O.R.GIOVEDI, CLAUDIAINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240142017GOMES, DANIEL S.SILVA, ANTONIO T.ABE, ALFREDO Y.MUNIZ, RAFAEL O.R.18-01Proceedings7670108578173487GOMES, DANIEL S.:7670:420:SSILVA, ANTONIO T.:1085:420:NABE, ALFREDO Y.:7817:-1:NMUNIZ, RAFAEL O.R.:3487:420:NORIGINAL24014.pdf24014.pdfapplication/pdf603768http://repositorio.ipen.br/bitstream/123456789/28189/1/24014.pdf7fb9f6358d48a3232120b58f1f5c15caMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28189/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/281892022-08-05 17:54:12.336oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T17:54:12Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv High density fuels using dispersion and monolithic fuel
title High density fuels using dispersion and monolithic fuel
spellingShingle High density fuels using dispersion and monolithic fuel
GOMES, DANIEL S.
aluminium
cladding
dispersion nuclear fuels
foils
fuel elements
fuel plates
irradiation
molybdenum alloys
physical properties
swelling
uranium alloys
zirconium
title_short High density fuels using dispersion and monolithic fuel
title_full High density fuels using dispersion and monolithic fuel
title_fullStr High density fuels using dispersion and monolithic fuel
title_full_unstemmed High density fuels using dispersion and monolithic fuel
title_sort High density fuels using dispersion and monolithic fuel
author GOMES, DANIEL S.
author_facet GOMES, DANIEL S.
SILVA, ANTONIO T.
ABE, ALFREDO Y.
MUNIZ, RAFAEL O.R.
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 SILVA, ANTONIO T.
ABE, ALFREDO Y.
MUNIZ, RAFAEL O.R.
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
author
author
dc.contributor.author.fl_str_mv GOMES, DANIEL S.
SILVA, ANTONIO T.
ABE, ALFREDO Y.
MUNIZ, RAFAEL O.R.
GIOVEDI, CLAUDIA
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv aluminium
cladding
dispersion nuclear fuels
foils
fuel elements
fuel plates
irradiation
molybdenum alloys
physical properties
swelling
uranium alloys
zirconium
topic aluminium
cladding
dispersion nuclear fuels
foils
fuel elements
fuel plates
irradiation
molybdenum alloys
physical properties
swelling
uranium alloys
zirconium
description Fuel plates used in high-performance research reactors need to be converted to low-enrichment uranium fuel; the fuel option based on a monolithic formulation requires alloys to contain 6 ??? 10 wt% Mo. In this case, the fuel plates are composed of the metallic alloy U-10Mo surrounded by a thin zirconium layer encapsulated in aluminum cladding. This study reviewed the physical properties of monolithic forms. The constraints produced during the manufacturing process were analyzed and compared to those of dispersed fuel. The bonding process used for dispersion fuels differs from the techniques applied to foil bonding used for pure alloys. The quality of monolithic plates depends on the fabrication method, which usually involves hot isostatic pressing and the thermal annealing effect of residual stress, which degrades the uranium cubic phase. The preservation of the metastable phase has considerable influence on fuel performance. The physical properties of the foil fuel under irradiation are superior to those of aluminum-dispersed fuels. The fuel meat, using zirconium as the diffusion barrier, prevents the interaction layer from becoming excessively thick. The problem with dispersed fuel is breakaway swelling with a medium fission rate. It has been observed that the fuel dispersed in aluminum was minimized in monolithic forms. The pure alloys exhibited a suitable response from a rate at least twice as much as the fission rate of dispersions. The foils can support fissile material concentration combined with a reduced swelling rate.
publishDate 2018
dc.date.evento.pt_BR.fl_str_mv October 22-27, 2017
dc.date.accessioned.fl_str_mv 2018-01-02T13:04:24Z
dc.date.available.fl_str_mv 2018-01-02T13:04:24Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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dc.identifier.uri.fl_str_mv http://repositorio.ipen.br/handle/123456789/28189
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
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