Thermal stability test of UO2-doped pellet manufactured at INB
Autor(a) principal: | |
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Data de Publicação: | 2018 |
Outros Autores: | , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/28366 |
Resumo: | The thermal stability test of UO2-doped pellet manufactured at INB was carried out in order to analyze the resintering behavior. This analysis is fundamental for predicting dimensional behavior during irradiation. INB commonly performs resintering test to qualify its production lots, and the same methodology was applied to UO2-doped pellets. In this preliminary study, three sets of experiments have been made: 1) without any chemical additive (Z test, the standard UO2 pellets - undoped); 2) UO2 pellets doped with 0.1, 0.2 and 0.3 wt% of Al2O3; and 3) 0.1, 0.2 and 0.3 wt% of Nb2O5. The preliminary results showed an increase in sintered density in all resintering experiments. So as to obtain the percentage increase, the theoretical densities (g/cm3 and %TD) were calculated based on the undoped UO2 pellets. All samples increased in a range of 0.27 to 0.32 %TD the out-pile densification during the resintering process. However, the Z(Nb)3 test showed the lowest value of 0.08 %TD, which is not in agreement with the INB specification limits. The sintered density of this test (0.3 wt% niobia) was 96.15% TD. This fact might be related to the competitive mechanism between Kirkendall effect, forming porosity owing to niobium solubilization on UO2 matrix, and densification process as a result of uranium diffusivity. Thus, the densification was only 0.08 %TD in Z(Nb)3 sample. All the other samples were in agreement with INB specification. |
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2018-01-18T10:43:45Z2018-01-18T10:43:45ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28366The thermal stability test of UO2-doped pellet manufactured at INB was carried out in order to analyze the resintering behavior. This analysis is fundamental for predicting dimensional behavior during irradiation. INB commonly performs resintering test to qualify its production lots, and the same methodology was applied to UO2-doped pellets. In this preliminary study, three sets of experiments have been made: 1) without any chemical additive (Z test, the standard UO2 pellets - undoped); 2) UO2 pellets doped with 0.1, 0.2 and 0.3 wt% of Al2O3; and 3) 0.1, 0.2 and 0.3 wt% of Nb2O5. The preliminary results showed an increase in sintered density in all resintering experiments. So as to obtain the percentage increase, the theoretical densities (g/cm3 and %TD) were calculated based on the undoped UO2 pellets. All samples increased in a range of 0.27 to 0.32 %TD the out-pile densification during the resintering process. However, the Z(Nb)3 test showed the lowest value of 0.08 %TD, which is not in agreement with the INB specification limits. The sintered density of this test (0.3 wt% niobia) was 96.15% TD. This fact might be related to the competitive mechanism between Kirkendall effect, forming porosity owing to niobium solubilization on UO2 matrix, and densification process as a result of uranium diffusivity. Thus, the densification was only 0.08 %TD in Z(Nb)3 sample. All the other samples were in agreement with INB specification.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-18T10:43:45Z No. of bitstreams: 1 24201.pdf: 822616 bytes, checksum: 5d1be5faf89b68b6b21c7cf45c99e362 (MD5)Made available in DSpace on 2018-01-18T10:43:45Z (GMT). No. of bitstreams: 1 24201.pdf: 822616 bytes, checksum: 5d1be5faf89b68b6b21c7cf45c99e362 (MD5)Associa????o Brasileira de Energia Nuclearaluminium oxideschemical propertiesdoped materialsfuel densificationfuel pelletsheat treatmentsniobium oxidesperformance testingphysical propertiessinteringstabilityuranium oxidesThermal stability test of UO2-doped pellet manufactured at INBinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGCOSTA, DIOGO R.FREITAS, ARTUR C.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN242012017FREITAS, ARTUR C.18-01Proceedings14109FREITAS, ARTUR C.:14109:410:NORIGINAL24201.pdf24201.pdfapplication/pdf822616http://repositorio.ipen.br/bitstream/123456789/28366/1/24201.pdf5d1be5faf89b68b6b21c7cf45c99e362MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28366/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/283662022-08-05 17:51:42.232oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T17:51:42Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Thermal stability test of UO2-doped pellet manufactured at INB |
title |
Thermal stability test of UO2-doped pellet manufactured at INB |
spellingShingle |
Thermal stability test of UO2-doped pellet manufactured at INB COSTA, DIOGO R. aluminium oxides chemical properties doped materials fuel densification fuel pellets heat treatments niobium oxides performance testing physical properties sintering stability uranium oxides |
title_short |
Thermal stability test of UO2-doped pellet manufactured at INB |
title_full |
Thermal stability test of UO2-doped pellet manufactured at INB |
title_fullStr |
Thermal stability test of UO2-doped pellet manufactured at INB |
title_full_unstemmed |
Thermal stability test of UO2-doped pellet manufactured at INB |
title_sort |
Thermal stability test of UO2-doped pellet manufactured at INB |
author |
COSTA, DIOGO R. |
author_facet |
COSTA, DIOGO R. FREITAS, ARTUR C. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
FREITAS, ARTUR C. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author |
dc.contributor.author.fl_str_mv |
COSTA, DIOGO R. FREITAS, ARTUR C. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
aluminium oxides chemical properties doped materials fuel densification fuel pellets heat treatments niobium oxides performance testing physical properties sintering stability uranium oxides |
topic |
aluminium oxides chemical properties doped materials fuel densification fuel pellets heat treatments niobium oxides performance testing physical properties sintering stability uranium oxides |
description |
The thermal stability test of UO2-doped pellet manufactured at INB was carried out in order to analyze the resintering behavior. This analysis is fundamental for predicting dimensional behavior during irradiation. INB commonly performs resintering test to qualify its production lots, and the same methodology was applied to UO2-doped pellets. In this preliminary study, three sets of experiments have been made: 1) without any chemical additive (Z test, the standard UO2 pellets - undoped); 2) UO2 pellets doped with 0.1, 0.2 and 0.3 wt% of Al2O3; and 3) 0.1, 0.2 and 0.3 wt% of Nb2O5. The preliminary results showed an increase in sintered density in all resintering experiments. So as to obtain the percentage increase, the theoretical densities (g/cm3 and %TD) were calculated based on the undoped UO2 pellets. All samples increased in a range of 0.27 to 0.32 %TD the out-pile densification during the resintering process. However, the Z(Nb)3 test showed the lowest value of 0.08 %TD, which is not in agreement with the INB specification limits. The sintered density of this test (0.3 wt% niobia) was 96.15% TD. This fact might be related to the competitive mechanism between Kirkendall effect, forming porosity owing to niobium solubilization on UO2 matrix, and densification process as a result of uranium diffusivity. Thus, the densification was only 0.08 %TD in Z(Nb)3 sample. All the other samples were in agreement with INB specification. |
publishDate |
2018 |
dc.date.evento.pt_BR.fl_str_mv |
October 22-27, 2017 |
dc.date.accessioned.fl_str_mv |
2018-01-18T10:43:45Z |
dc.date.available.fl_str_mv |
2018-01-18T10:43:45Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/conferenceObject |
format |
conferenceObject |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/28366 |
url |
http://repositorio.ipen.br/handle/123456789/28366 |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.coverage.pt_BR.fl_str_mv |
I |
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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reponame:Repositório Institucional do IPEN instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN) instacron:IPEN |
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Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
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IPEN |
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IPEN |
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Repositório Institucional do IPEN |
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Repositório Institucional do IPEN |
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