Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation

Autores
Vazquez, Carolina; Zelaya, Maria Eugenia; Fortis, Ana Maria; Bozzano, Patricia Beatriz
Año de publicación
2021
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.
Fil: Vazquez, Carolina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
Fil: Zelaya, Maria Eugenia. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; Argentina. Comision Nacional de Energía Atómica. Gerencia de Área Investigaciones y Aplicaciones no Nucleares. Gerencia de Física (Centro Atómico Bariloche). División Física de Metales; Argentina
Fil: Fortis, Ana Maria. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
Fil: Bozzano, Patricia Beatriz. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
Materia
Zirconium alloys
Radiation damage
Hydrogen
Electron microscopy
Tensile tests
Nivel de accesibilidad
acceso abierto
Condiciones de uso
https://creativecommons.org/licenses/by/2.5/ar/
Repositorio
CONICET Digital (CONICET)
Institución
Consejo Nacional de Investigaciones Científicas y Técnicas
OAI Identificador
oai:ri.conicet.gov.ar:11336/167769
Acceder
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network_name_str CONICET Digital (CONICET)
spelling Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron IrradiationVazquez, CarolinaZelaya, Maria EugeniaFortis, Ana MariaBozzano, Patricia BeatrizZirconium alloysRadiation damageHydrogenElectron microscopyTensile testshttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.Fil: Vazquez, Carolina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; ArgentinaFil: Zelaya, Maria Eugenia. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; Argentina. Comision Nacional de Energía Atómica. Gerencia de Área Investigaciones y Aplicaciones no Nucleares. Gerencia de Física (Centro Atómico Bariloche). División Física de Metales; ArgentinaFil: Fortis, Ana Maria. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; ArgentinaFil: Bozzano, Patricia Beatriz. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; ArgentinaTech Reviews Ltd.2021-11info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/167769Vazquez, Carolina; Zelaya, Maria Eugenia; Fortis, Ana Maria; Bozzano, Patricia Beatriz; Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation; Tech Reviews Ltd.; Journal of Materials and Applications; 10; 2; 11-2021; 63-722051-7750CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/http://www.xpublication.com/index.php/jma/article/view/638info:eu-repo/semantics/altIdentifier/doi/10.32732/jma.2021.10.2.63info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-22T11:23:07Zoai:ri.conicet.gov.ar:11336/167769instacron: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:34982025-10-22 11:23:08.019CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
title Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
spellingShingle Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
Vazquez, Carolina
Zirconium alloys
Radiation damage
Hydrogen
Electron microscopy
Tensile tests
title_short Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
title_full Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
title_fullStr Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
title_full_unstemmed Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
title_sort Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
dc.creator.none.fl_str_mv Vazquez, Carolina
Zelaya, Maria Eugenia
Fortis, Ana Maria
Bozzano, Patricia Beatriz
author Vazquez, Carolina
author_facet Vazquez, Carolina
Zelaya, Maria Eugenia
Fortis, Ana Maria
Bozzano, Patricia Beatriz
author_role author
author2 Zelaya, Maria Eugenia
Fortis, Ana Maria
Bozzano, Patricia Beatriz
author2_role author
author
author
dc.subject.none.fl_str_mv Zirconium alloys
Radiation damage
Hydrogen
Electron microscopy
Tensile tests
topic Zirconium alloys
Radiation damage
Hydrogen
Electron microscopy
Tensile tests
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.
Fil: Vazquez, Carolina. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
Fil: Zelaya, Maria Eugenia. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; Argentina. Comision Nacional de Energía Atómica. Gerencia de Área Investigaciones y Aplicaciones no Nucleares. Gerencia de Física (Centro Atómico Bariloche). División Física de Metales; Argentina
Fil: Fortis, Ana Maria. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
Fil: Bozzano, Patricia Beatriz. Universidad Nacional de San Martín. Instituto Sabato; Argentina. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina
description Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.
publishDate 2021
dc.date.none.fl_str_mv 2021-11
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/11336/167769
Vazquez, Carolina; Zelaya, Maria Eugenia; Fortis, Ana Maria; Bozzano, Patricia Beatriz; Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation; Tech Reviews Ltd.; Journal of Materials and Applications; 10; 2; 11-2021; 63-72
2051-7750
CONICET Digital
CONICET
url http://hdl.handle.net/11336/167769
identifier_str_mv Vazquez, Carolina; Zelaya, Maria Eugenia; Fortis, Ana Maria; Bozzano, Patricia Beatriz; Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation; Tech Reviews Ltd.; Journal of Materials and Applications; 10; 2; 11-2021; 63-72
2051-7750
CONICET Digital
CONICET
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/url/http://www.xpublication.com/index.php/jma/article/view/638
info:eu-repo/semantics/altIdentifier/doi/10.32732/jma.2021.10.2.63
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by/2.5/ar/
eu_rights_str_mv openAccess
rights_invalid_str_mv https://creativecommons.org/licenses/by/2.5/ar/
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Tech Reviews Ltd.
publisher.none.fl_str_mv Tech Reviews Ltd.
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 12.982451

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