Study and simulations of quick diffusion in Zr-based alloys

Autores
Corvalán Moya, Carolina del Huerto; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.
Año de publicación
2015
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys are polycrystalline and contain a high density of grain and interphase boundaries. These boundaries function as paths for accelerated matter movement. The movement of fast diffusing elements (Co, Fe, Cr, Ni) in Zr alloys along boundaries produces technologically important changes in the materials in nuclear reactors at normal temperatures (∼550 K) e.g.: segregation, phase precipitation, hydrogen absorption, etc. In this work, diffusion parameters for fast diffusion in Zr at low temperature were assessed for Co and Cr. An improved database for DICTRA (DIffusion-Controlled-TRAnsformation) software for fast diffusion was obtained. The diffusion parameters in grain boundaries of α-Zr for Cr and Co were used from a particular kinetic diffusion model [1]. Simulated profiles were compared with previous experimental work [2]. The results of the comparison and the adequacy of the improved database are discussed. Diffusion profiles on grain boundaries in α-Zr for Cr and Co are presented in the temperature range of 380-460 K.
Fil: Corvalán Moya, Carolina del Huerto. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Lucía, A.. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Iribarren, Manuel José. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Servant, Colette. Université Paris Sud; Francia
Fil: Costa E Silva, A.. Universidade Federal Fluminense; Brasil
Materia
DICTRA
DIFFUSION
NUCLEAR MATERIALS
ZIRCONIUM
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:11336/98524
Acceder
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network_name_str CONICET Digital (CONICET)
spelling Study and simulations of quick diffusion in Zr-based alloysCorvalán Moya, Carolina del HuertoLucía, A.Iribarren, Manuel JoséServant, ColetteCosta E Silva, A.DICTRADIFFUSIONNUCLEAR MATERIALSZIRCONIUMhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys are polycrystalline and contain a high density of grain and interphase boundaries. These boundaries function as paths for accelerated matter movement. The movement of fast diffusing elements (Co, Fe, Cr, Ni) in Zr alloys along boundaries produces technologically important changes in the materials in nuclear reactors at normal temperatures (∼550 K) e.g.: segregation, phase precipitation, hydrogen absorption, etc. In this work, diffusion parameters for fast diffusion in Zr at low temperature were assessed for Co and Cr. An improved database for DICTRA (DIffusion-Controlled-TRAnsformation) software for fast diffusion was obtained. The diffusion parameters in grain boundaries of α-Zr for Cr and Co were used from a particular kinetic diffusion model [1]. Simulated profiles were compared with previous experimental work [2]. The results of the comparison and the adequacy of the improved database are discussed. Diffusion profiles on grain boundaries in α-Zr for Cr and Co are presented in the temperature range of 380-460 K.Fil: Corvalán Moya, Carolina del Huerto. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Lucía, A.. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; ArgentinaFil: Iribarren, Manuel José. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; ArgentinaFil: Servant, Colette. Université Paris Sud; FranciaFil: Costa E Silva, A.. Universidade Federal Fluminense; BrasilElsevier Science2015-08info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/98524Corvalán Moya, Carolina del Huerto; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.; Study and simulations of quick diffusion in Zr-based alloys; Elsevier Science; Journal of Nuclear Materials; 466; 8-2015; 80-840022-3115CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0022311515301100info:eu-repo/semantics/altIdentifier/doi/10.1016/j.jnucmat.2015.07.024info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-nd/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-03T10:00:03Zoai:ri.conicet.gov.ar:11336/98524instacron: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:34982025-09-03 10:00:03.878CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Study and simulations of quick diffusion in Zr-based alloys
title Study and simulations of quick diffusion in Zr-based alloys
spellingShingle Study and simulations of quick diffusion in Zr-based alloys
Corvalán Moya, Carolina del Huerto
DICTRA
DIFFUSION
NUCLEAR MATERIALS
ZIRCONIUM
title_short Study and simulations of quick diffusion in Zr-based alloys
title_full Study and simulations of quick diffusion in Zr-based alloys
title_fullStr Study and simulations of quick diffusion in Zr-based alloys
title_full_unstemmed Study and simulations of quick diffusion in Zr-based alloys
title_sort Study and simulations of quick diffusion in Zr-based alloys
dc.creator.none.fl_str_mv Corvalán Moya, Carolina del Huerto
Lucía, A.
Iribarren, Manuel José
Servant, Colette
Costa E Silva, A.
author Corvalán Moya, Carolina del Huerto
author_facet Corvalán Moya, Carolina del Huerto
Lucía, A.
Iribarren, Manuel José
Servant, Colette
Costa E Silva, A.
author_role author
author2 Lucía, A.
Iribarren, Manuel José
Servant, Colette
Costa E Silva, A.
author2_role author
author
author
author
dc.subject.none.fl_str_mv DICTRA
DIFFUSION
NUCLEAR MATERIALS
ZIRCONIUM
topic DICTRA
DIFFUSION
NUCLEAR MATERIALS
ZIRCONIUM
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 the nuclear industry. Under normal conditions, Zr-alloys are polycrystalline and contain a high density of grain and interphase boundaries. These boundaries function as paths for accelerated matter movement. The movement of fast diffusing elements (Co, Fe, Cr, Ni) in Zr alloys along boundaries produces technologically important changes in the materials in nuclear reactors at normal temperatures (∼550 K) e.g.: segregation, phase precipitation, hydrogen absorption, etc. In this work, diffusion parameters for fast diffusion in Zr at low temperature were assessed for Co and Cr. An improved database for DICTRA (DIffusion-Controlled-TRAnsformation) software for fast diffusion was obtained. The diffusion parameters in grain boundaries of α-Zr for Cr and Co were used from a particular kinetic diffusion model [1]. Simulated profiles were compared with previous experimental work [2]. The results of the comparison and the adequacy of the improved database are discussed. Diffusion profiles on grain boundaries in α-Zr for Cr and Co are presented in the temperature range of 380-460 K.
Fil: Corvalán Moya, Carolina del Huerto. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Lucía, A.. Universidad Nacional de Tres de Febrero; Argentina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Iribarren, Manuel José. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica; Argentina
Fil: Servant, Colette. Université Paris Sud; Francia
Fil: Costa E Silva, A.. Universidade Federal Fluminense; Brasil
description Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys are polycrystalline and contain a high density of grain and interphase boundaries. These boundaries function as paths for accelerated matter movement. The movement of fast diffusing elements (Co, Fe, Cr, Ni) in Zr alloys along boundaries produces technologically important changes in the materials in nuclear reactors at normal temperatures (∼550 K) e.g.: segregation, phase precipitation, hydrogen absorption, etc. In this work, diffusion parameters for fast diffusion in Zr at low temperature were assessed for Co and Cr. An improved database for DICTRA (DIffusion-Controlled-TRAnsformation) software for fast diffusion was obtained. The diffusion parameters in grain boundaries of α-Zr for Cr and Co were used from a particular kinetic diffusion model [1]. Simulated profiles were compared with previous experimental work [2]. The results of the comparison and the adequacy of the improved database are discussed. Diffusion profiles on grain boundaries in α-Zr for Cr and Co are presented in the temperature range of 380-460 K.
publishDate 2015
dc.date.none.fl_str_mv 2015-08
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/11336/98524
Corvalán Moya, Carolina del Huerto; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.; Study and simulations of quick diffusion in Zr-based alloys; Elsevier Science; Journal of Nuclear Materials; 466; 8-2015; 80-84
0022-3115
CONICET Digital
CONICET
url http://hdl.handle.net/11336/98524
identifier_str_mv Corvalán Moya, Carolina del Huerto; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.; Study and simulations of quick diffusion in Zr-based alloys; Elsevier Science; Journal of Nuclear Materials; 466; 8-2015; 80-84
0022-3115
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://www.sciencedirect.com/science/article/pii/S0022311515301100
info:eu-repo/semantics/altIdentifier/doi/10.1016/j.jnucmat.2015.07.024
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
application/pdf
dc.publisher.none.fl_str_mv Elsevier Science
publisher.none.fl_str_mv Elsevier Science
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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score 13.13397

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