Interdiffusion studies on hot rolled U-10Mo/AA1050

Detalhes bibliográficos
Autor(a) principal: Saliba-Silva,Adonis Marcelo
Data de Publicação: 2012
Outros Autores: Martins,Ilson Carlos, Carvalho,Elita Fontenelle Urano de, Silva,Davilson Gomes da, Riella,Humberto Gracher, Durazzo,Michelangelo
Tipo de documento: Artigo
Idioma: eng
Título da fonte: Materials research (São Carlos. Online)
Texto Completo: http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1516-14392012000600019
Resumo: The U-Mo alloys are investigated with the goal to become nuclear material to fabricate high-density fuel elements for high performance research reactors. The enrichment level (20% 235U) suggests that the U-Mo alloys should be between 6 to 10 wt. (%), which can reach up to 9 gU.cm-3 in fuel density. Nevertheless, the U-Mo alloys are very reactive with Al. Interdiffusion reaction products are formed since nuclear fission promotes chemical interaction layer during operation, leading to potential structural failure. Present studies were made with treated hot rolled diffusion couples of U-10Mo inserted in Al (AA1050). The U-10Mo/AA1050 pairs were treated in two temperatures (150 ºC and 550 ºC) with three soaking times (5, 40 and 80 hours). From microstructure analyses, rapid diffusion of Al happened inside U-10Mo in the first heating at 540 ºC during 15 minutes, reaching 8 at% Al in a range of 170 μm towards U-10Mo. Longer time at 550 ºC treatment maintain this level of Al-content up to 1000 μm inside U-10Mo. In this study, the results suggested the formation of a barrier made by residual elements, which promoted little interdiffusion phenomena between U-10Mo and alloy AA1050. Silicon co-diffusion with Al, along the interdiffusion line, is thought to be an important indication for this interdiffusion blockage.
id ABMABCABPOL-1_8a0b1b02aa37034768184cfd050061ae
oai_identifier_str oai:scielo:S1516-14392012000600019
network_acronym_str ABMABCABPOL-1
network_name_str Materials research (São Carlos. Online)
repository_id_str
spelling Interdiffusion studies on hot rolled U-10Mo/AA1050U-Monuclear fuelresearch reactorsinteraction layerAl/U-Mo interdiffusion pairThe U-Mo alloys are investigated with the goal to become nuclear material to fabricate high-density fuel elements for high performance research reactors. The enrichment level (20% 235U) suggests that the U-Mo alloys should be between 6 to 10 wt. (%), which can reach up to 9 gU.cm-3 in fuel density. Nevertheless, the U-Mo alloys are very reactive with Al. Interdiffusion reaction products are formed since nuclear fission promotes chemical interaction layer during operation, leading to potential structural failure. Present studies were made with treated hot rolled diffusion couples of U-10Mo inserted in Al (AA1050). The U-10Mo/AA1050 pairs were treated in two temperatures (150 ºC and 550 ºC) with three soaking times (5, 40 and 80 hours). From microstructure analyses, rapid diffusion of Al happened inside U-10Mo in the first heating at 540 ºC during 15 minutes, reaching 8 at% Al in a range of 170 μm towards U-10Mo. Longer time at 550 ºC treatment maintain this level of Al-content up to 1000 μm inside U-10Mo. In this study, the results suggested the formation of a barrier made by residual elements, which promoted little interdiffusion phenomena between U-10Mo and alloy AA1050. Silicon co-diffusion with Al, along the interdiffusion line, is thought to be an important indication for this interdiffusion blockage.ABM, ABC, ABPol2012-12-01info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersiontext/htmlhttp://old.scielo.br/scielo.php?script=sci_arttext&pid=S1516-14392012000600019Materials Research v.15 n.6 2012reponame:Materials research (São Carlos. Online)instname:Universidade Federal de São Carlos (UFSCAR)instacron:ABM ABC ABPOL10.1590/S1516-14392012005000125info:eu-repo/semantics/openAccessSaliba-Silva,Adonis MarceloMartins,Ilson CarlosCarvalho,Elita Fontenelle Urano deSilva,Davilson Gomes daRiella,Humberto GracherDurazzo,Michelangeloeng2012-11-20T00:00:00Zoai:scielo:S1516-14392012000600019Revistahttp://www.scielo.br/mrPUBhttps://old.scielo.br/oai/scielo-oai.phpdedz@power.ufscar.br1980-53731516-1439opendoar:2012-11-20T00:00Materials research (São Carlos. Online) - Universidade Federal de São Carlos (UFSCAR)false
dc.title.none.fl_str_mv Interdiffusion studies on hot rolled U-10Mo/AA1050
title Interdiffusion studies on hot rolled U-10Mo/AA1050
spellingShingle Interdiffusion studies on hot rolled U-10Mo/AA1050
Saliba-Silva,Adonis Marcelo
U-Mo
nuclear fuel
research reactors
interaction layer
Al/U-Mo interdiffusion pair
title_short Interdiffusion studies on hot rolled U-10Mo/AA1050
title_full Interdiffusion studies on hot rolled U-10Mo/AA1050
title_fullStr Interdiffusion studies on hot rolled U-10Mo/AA1050
title_full_unstemmed Interdiffusion studies on hot rolled U-10Mo/AA1050
title_sort Interdiffusion studies on hot rolled U-10Mo/AA1050
author Saliba-Silva,Adonis Marcelo
author_facet Saliba-Silva,Adonis Marcelo
Martins,Ilson Carlos
Carvalho,Elita Fontenelle Urano de
Silva,Davilson Gomes da
Riella,Humberto Gracher
Durazzo,Michelangelo
author_role author
author2 Martins,Ilson Carlos
Carvalho,Elita Fontenelle Urano de
Silva,Davilson Gomes da
Riella,Humberto Gracher
Durazzo,Michelangelo
author2_role author
author
author
author
author
dc.contributor.author.fl_str_mv Saliba-Silva,Adonis Marcelo
Martins,Ilson Carlos
Carvalho,Elita Fontenelle Urano de
Silva,Davilson Gomes da
Riella,Humberto Gracher
Durazzo,Michelangelo
dc.subject.por.fl_str_mv U-Mo
nuclear fuel
research reactors
interaction layer
Al/U-Mo interdiffusion pair
topic U-Mo
nuclear fuel
research reactors
interaction layer
Al/U-Mo interdiffusion pair
description The U-Mo alloys are investigated with the goal to become nuclear material to fabricate high-density fuel elements for high performance research reactors. The enrichment level (20% 235U) suggests that the U-Mo alloys should be between 6 to 10 wt. (%), which can reach up to 9 gU.cm-3 in fuel density. Nevertheless, the U-Mo alloys are very reactive with Al. Interdiffusion reaction products are formed since nuclear fission promotes chemical interaction layer during operation, leading to potential structural failure. Present studies were made with treated hot rolled diffusion couples of U-10Mo inserted in Al (AA1050). The U-10Mo/AA1050 pairs were treated in two temperatures (150 ºC and 550 ºC) with three soaking times (5, 40 and 80 hours). From microstructure analyses, rapid diffusion of Al happened inside U-10Mo in the first heating at 540 ºC during 15 minutes, reaching 8 at% Al in a range of 170 μm towards U-10Mo. Longer time at 550 ºC treatment maintain this level of Al-content up to 1000 μm inside U-10Mo. In this study, the results suggested the formation of a barrier made by residual elements, which promoted little interdiffusion phenomena between U-10Mo and alloy AA1050. Silicon co-diffusion with Al, along the interdiffusion line, is thought to be an important indication for this interdiffusion blockage.
publishDate 2012
dc.date.none.fl_str_mv 2012-12-01
dc.type.driver.fl_str_mv info:eu-repo/semantics/article
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
format article
status_str publishedVersion
dc.identifier.uri.fl_str_mv http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1516-14392012000600019
url http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1516-14392012000600019
dc.language.iso.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv 10.1590/S1516-14392012005000125
dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv text/html
dc.publisher.none.fl_str_mv ABM, ABC, ABPol
publisher.none.fl_str_mv ABM, ABC, ABPol
dc.source.none.fl_str_mv Materials Research v.15 n.6 2012
reponame:Materials research (São Carlos. Online)
instname:Universidade Federal de São Carlos (UFSCAR)
instacron:ABM ABC ABPOL
instname_str Universidade Federal de São Carlos (UFSCAR)
instacron_str ABM ABC ABPOL
institution ABM ABC ABPOL
reponame_str Materials research (São Carlos. Online)
collection Materials research (São Carlos. Online)
repository.name.fl_str_mv Materials research (São Carlos. Online) - Universidade Federal de São Carlos (UFSCAR)
repository.mail.fl_str_mv dedz@power.ufscar.br
_version_ 1754212661667561472