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
- Institución
- Consejo Nacional de Investigaciones Científicas y Técnicas
- OAI Identificador
- oai:ri.conicet.gov.ar:11336/170661
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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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1842980894381441024 |
score |
12.993085 |