Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques

Autores
Lucía, Andrés; Iribarren, Manuel José; Corvalán Moya, Carolina del Huerto
Año de publicación
2020
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Zirconium and its alloys are widely used in nuclear industry (nuclear fuel cladding tubes, structural materials, etc.) for its adequate properties under hostile conditions (corrosive environment, radiation damage, etc.) in the core of nuclear reactors. In normal operating conditions, these materials present an important density of grain and interphase boundaries which act as quick paths for the movement of matter and can be in structural contact with Fe based alloys. The movement of fast diffusing elements (Fe, Co, Cr, Ni) in these short-circuit paths in Zr alloys [1] can produce technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K) like nucleation and growth of new phases [2] or complexions [3] and as a consequence, changes in their properties. Particularly, such diffusion process is fundamental for the development of Fe rich compounds in the alloy [4] as can affect its corrosion resistance [5] and mechanical properties. In this work we present Fe diffusion measurements made on pure zirconium: volume, B and C kinetics in grain boundaries (GB) between 368 and 600 K. The movement of fast diffusing elements (like Fe, Co, Cr, Ni) produces microstructural changes and technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K). In this work, volume and grain boundaries (GB) diffusion of Fe in polycrystalline high purity Zr is measured using sectioning and LIBS technique between 368 and 600 K. Diffusion profiles, diffusion kinetics, segregation factor, Arrhenius plot, diffusion mechanisms and LIBS technique are discussed and, when possible, validated with existing data.
Fil: Lucía, Andrés. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina
Fil: Iribarren, Manuel José. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina
Fil: Corvalán Moya, Carolina del Huerto. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; Argentina
Materia
DIFFUSION
FE.
GRAIN BOUNDARY DIFFUSION
LIBS
ZR
Nivel de accesibilidad
acceso abierto
Condiciones de uso
https://creativecommons.org/licenses/by-nc-nd/2.5/ar/
Repositorio
CONICET Digital (CONICET)
Institución
Consejo Nacional de Investigaciones Científicas y Técnicas
OAI Identificador
oai:ri.conicet.gov.ar:11336/170661

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spelling Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniquesLucía, AndrésIribarren, Manuel JoséCorvalán Moya, Carolina del HuertoDIFFUSIONFE.GRAIN BOUNDARY DIFFUSIONLIBSZRhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Zirconium and its alloys are widely used in nuclear industry (nuclear fuel cladding tubes, structural materials, etc.) for its adequate properties under hostile conditions (corrosive environment, radiation damage, etc.) in the core of nuclear reactors. In normal operating conditions, these materials present an important density of grain and interphase boundaries which act as quick paths for the movement of matter and can be in structural contact with Fe based alloys. The movement of fast diffusing elements (Fe, Co, Cr, Ni) in these short-circuit paths in Zr alloys [1] can produce technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K) like nucleation and growth of new phases [2] or complexions [3] and as a consequence, changes in their properties. Particularly, such diffusion process is fundamental for the development of Fe rich compounds in the alloy [4] as can affect its corrosion resistance [5] and mechanical properties. In this work we present Fe diffusion measurements made on pure zirconium: volume, B and C kinetics in grain boundaries (GB) between 368 and 600 K. The movement of fast diffusing elements (like Fe, Co, Cr, Ni) produces microstructural changes and technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K). In this work, volume and grain boundaries (GB) diffusion of Fe in polycrystalline high purity Zr is measured using sectioning and LIBS technique between 368 and 600 K. Diffusion profiles, diffusion kinetics, segregation factor, Arrhenius plot, diffusion mechanisms and LIBS technique are discussed and, when possible, validated with existing data.Fil: Lucía, Andrés. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; ArgentinaFil: Iribarren, Manuel José. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; ArgentinaFil: Corvalán Moya, Carolina del Huerto. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; ArgentinaElsevier2020-07info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/170661Lucía, Andrés; Iribarren, Manuel José; Corvalán Moya, Carolina del Huerto; Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques; Elsevier; Journal of Materials Research and Technology; 9; 4; 7-2020; 7318-73262238-7854CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S223878542031228Xinfo:eu-repo/semantics/altIdentifier/doi/10.1016/j.jmrt.2020.04.063info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-nd/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-10T13:16:26Zoai:ri.conicet.gov.ar:11336/170661instacron:CONICETInstitucionalhttp://ri.conicet.gov.ar/Organismo científico-tecnológicoNo correspondehttp://ri.conicet.gov.ar/oai/requestdasensio@conicet.gov.ar; lcarlino@conicet.gov.arArgentinaNo correspondeNo correspondeNo correspondeopendoar:34982025-09-10 13:16:26.61CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
title Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
spellingShingle Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
Lucía, Andrés
DIFFUSION
FE.
GRAIN BOUNDARY DIFFUSION
LIBS
ZR
title_short Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
title_full Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
title_fullStr Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
title_full_unstemmed Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
title_sort Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques
dc.creator.none.fl_str_mv Lucía, Andrés
Iribarren, Manuel José
Corvalán Moya, Carolina del Huerto
author Lucía, Andrés
author_facet Lucía, Andrés
Iribarren, Manuel José
Corvalán Moya, Carolina del Huerto
author_role author
author2 Iribarren, Manuel José
Corvalán Moya, Carolina del Huerto
author2_role author
author
dc.subject.none.fl_str_mv DIFFUSION
FE.
GRAIN BOUNDARY DIFFUSION
LIBS
ZR
topic DIFFUSION
FE.
GRAIN BOUNDARY DIFFUSION
LIBS
ZR
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv Zirconium and its alloys are widely used in nuclear industry (nuclear fuel cladding tubes, structural materials, etc.) for its adequate properties under hostile conditions (corrosive environment, radiation damage, etc.) in the core of nuclear reactors. In normal operating conditions, these materials present an important density of grain and interphase boundaries which act as quick paths for the movement of matter and can be in structural contact with Fe based alloys. The movement of fast diffusing elements (Fe, Co, Cr, Ni) in these short-circuit paths in Zr alloys [1] can produce technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K) like nucleation and growth of new phases [2] or complexions [3] and as a consequence, changes in their properties. Particularly, such diffusion process is fundamental for the development of Fe rich compounds in the alloy [4] as can affect its corrosion resistance [5] and mechanical properties. In this work we present Fe diffusion measurements made on pure zirconium: volume, B and C kinetics in grain boundaries (GB) between 368 and 600 K. The movement of fast diffusing elements (like Fe, Co, Cr, Ni) produces microstructural changes and technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K). In this work, volume and grain boundaries (GB) diffusion of Fe in polycrystalline high purity Zr is measured using sectioning and LIBS technique between 368 and 600 K. Diffusion profiles, diffusion kinetics, segregation factor, Arrhenius plot, diffusion mechanisms and LIBS technique are discussed and, when possible, validated with existing data.
Fil: Lucía, Andrés. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina
Fil: Iribarren, Manuel José. Comisión Nacional de Energía Atómica; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina
Fil: Corvalán Moya, Carolina del Huerto. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional de Tres de Febrero; Argentina. Comisión Nacional de Energía Atómica; Argentina
description Zirconium and its alloys are widely used in nuclear industry (nuclear fuel cladding tubes, structural materials, etc.) for its adequate properties under hostile conditions (corrosive environment, radiation damage, etc.) in the core of nuclear reactors. In normal operating conditions, these materials present an important density of grain and interphase boundaries which act as quick paths for the movement of matter and can be in structural contact with Fe based alloys. The movement of fast diffusing elements (Fe, Co, Cr, Ni) in these short-circuit paths in Zr alloys [1] can produce technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K) like nucleation and growth of new phases [2] or complexions [3] and as a consequence, changes in their properties. Particularly, such diffusion process is fundamental for the development of Fe rich compounds in the alloy [4] as can affect its corrosion resistance [5] and mechanical properties. In this work we present Fe diffusion measurements made on pure zirconium: volume, B and C kinetics in grain boundaries (GB) between 368 and 600 K. The movement of fast diffusing elements (like Fe, Co, Cr, Ni) produces microstructural changes and technologically important inconveniences in nuclear reactors at normal service condition temperatures (low temperatures <600 K). In this work, volume and grain boundaries (GB) diffusion of Fe in polycrystalline high purity Zr is measured using sectioning and LIBS technique between 368 and 600 K. Diffusion profiles, diffusion kinetics, segregation factor, Arrhenius plot, diffusion mechanisms and LIBS technique are discussed and, when possible, validated with existing data.
publishDate 2020
dc.date.none.fl_str_mv 2020-07
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
http://purl.org/coar/resource_type/c_6501
info:ar-repo/semantics/articulo
format article
status_str publishedVersion
dc.identifier.none.fl_str_mv http://hdl.handle.net/11336/170661
Lucía, Andrés; Iribarren, Manuel José; Corvalán Moya, Carolina del Huerto; Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques; Elsevier; Journal of Materials Research and Technology; 9; 4; 7-2020; 7318-7326
2238-7854
CONICET Digital
CONICET
url http://hdl.handle.net/11336/170661
identifier_str_mv Lucía, Andrés; Iribarren, Manuel José; Corvalán Moya, Carolina del Huerto; Study of quick diffusion of Fe on α-Zr by sectioning and LIBS techniques; Elsevier; Journal of Materials Research and Technology; 9; 4; 7-2020; 7318-7326
2238-7854
CONICET Digital
CONICET
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S223878542031228X
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.jmrt.2020.04.063
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by-nc-nd/2.5/ar/
eu_rights_str_mv openAccess
rights_invalid_str_mv https://creativecommons.org/licenses/by-nc-nd/2.5/ar/
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Elsevier
publisher.none.fl_str_mv Elsevier
dc.source.none.fl_str_mv reponame:CONICET Digital (CONICET)
instname:Consejo Nacional de Investigaciones Científicas y Técnicas
reponame_str CONICET Digital (CONICET)
collection CONICET Digital (CONICET)
instname_str Consejo Nacional de Investigaciones Científicas y Técnicas
repository.name.fl_str_mv CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicas
repository.mail.fl_str_mv dasensio@conicet.gov.ar; lcarlino@conicet.gov.ar
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