Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging

Autores
Grosse, M.; Santisteban, Javier Roberto; Bertsch, J.; Schillinger, B.; Kaestner, A.; Daymond, M. R.; Kardjilov, N.
Año de publicación
2018
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Absorbed hydrogen degrades the mechanical properties of zirconium alloys used for nuclear fuel claddings. Not only the total amount of hydrogen absorbed in the cladding tube but also the zirconium hydride orientation and its distribution influence the toughness of the material. For instance, the so-called delayed hydride cracking is caused by the diffusive re-distribution of hydrogen into the dilative elastic strain field ahead of crack tips. The paper presents in-situ and ex-situ neutron imaging investigations of hydrogen uptake, diffusion and distribution in zirconium alloys used for claddings. An overview about results of in-situ experiments studying the hydrogen uptake in strained Zircaloy-4, as well as ex-situ investigations of the diffusion of hydrogen in cold rolled Zircaloy-2 and Zr-2.5 % Nb alloy depending on temperature, rolling direction and thermal treatment and of the hydrogen re-distribution in the b-phase of Zircaloy-4 during a Three-Point-Bending-Test at 600 8C are presented.
Fil: Grosse, M.. Karlsruher Institut für Technology; Alemania
Fil: Santisteban, Javier Roberto. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; Argentina
Fil: Bertsch, J.. Paul Scherrer Institut; Suiza
Fil: Schillinger, B.. Universitat Technical Zu Munich; Alemania
Fil: Kaestner, A.. Paul Scherrer Institut; Suiza
Fil: Daymond, M. R.. Queens University; Canadá
Fil: Kardjilov, N.. Helmholtz Zentrum Berlin; Alemania
Materia
neutron imaging
hydrogen diffusion
in-situ imaging
zircnoim alloys
Nivel de accesibilidad
acceso abierto
Condiciones de uso
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
Repositorio
CONICET Digital (CONICET)
Institución
Consejo Nacional de Investigaciones Científicas y Técnicas
OAI Identificador
oai:ri.conicet.gov.ar:11336/125268
Acceder
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oai_identifier_str oai:ri.conicet.gov.ar:11336/125268
network_acronym_str CONICETDig
repository_id_str 3498
network_name_str CONICET Digital (CONICET)
spelling Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron ImagingGrosse, M.Santisteban, Javier RobertoBertsch, J.Schillinger, B.Kaestner, A.Daymond, M. R.Kardjilov, N.neutron imaginghydrogen diffusionin-situ imagingzircnoim alloyshttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Absorbed hydrogen degrades the mechanical properties of zirconium alloys used for nuclear fuel claddings. Not only the total amount of hydrogen absorbed in the cladding tube but also the zirconium hydride orientation and its distribution influence the toughness of the material. For instance, the so-called delayed hydride cracking is caused by the diffusive re-distribution of hydrogen into the dilative elastic strain field ahead of crack tips. The paper presents in-situ and ex-situ neutron imaging investigations of hydrogen uptake, diffusion and distribution in zirconium alloys used for claddings. An overview about results of in-situ experiments studying the hydrogen uptake in strained Zircaloy-4, as well as ex-situ investigations of the diffusion of hydrogen in cold rolled Zircaloy-2 and Zr-2.5 % Nb alloy depending on temperature, rolling direction and thermal treatment and of the hydrogen re-distribution in the b-phase of Zircaloy-4 during a Three-Point-Bending-Test at 600 8C are presented.Fil: Grosse, M.. Karlsruher Institut für Technology; AlemaniaFil: Santisteban, Javier Roberto. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; ArgentinaFil: Bertsch, J.. Paul Scherrer Institut; SuizaFil: Schillinger, B.. Universitat Technical Zu Munich; AlemaniaFil: Kaestner, A.. Paul Scherrer Institut; SuizaFil: Daymond, M. R.. Queens University; CanadáFil: Kardjilov, N.. Helmholtz Zentrum Berlin; AlemaniaCarl Hanser Verlag2018-12info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/125268Grosse, M.; Santisteban, Javier Roberto; Bertsch, J.; Schillinger, B.; Kaestner, A.; et al.; Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging; Carl Hanser Verlag; Kerntechnik; 83; 6; 12-2018; 495-5010932-3902CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://www.hanser-elibrary.com/doi/10.3139/124.110946info:eu-repo/semantics/altIdentifier/doi/10.3139/124.110946info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-09-29T09:46:41Zoai:ri.conicet.gov.ar:11336/125268instacron: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:34982025-09-29 09:46:42.14CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
title Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
spellingShingle Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
Grosse, M.
neutron imaging
hydrogen diffusion
in-situ imaging
zircnoim alloys
title_short Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
title_full Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
title_fullStr Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
title_full_unstemmed Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
title_sort Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
dc.creator.none.fl_str_mv Grosse, M.
Santisteban, Javier Roberto
Bertsch, J.
Schillinger, B.
Kaestner, A.
Daymond, M. R.
Kardjilov, N.
author Grosse, M.
author_facet Grosse, M.
Santisteban, Javier Roberto
Bertsch, J.
Schillinger, B.
Kaestner, A.
Daymond, M. R.
Kardjilov, N.
author_role author
author2 Santisteban, Javier Roberto
Bertsch, J.
Schillinger, B.
Kaestner, A.
Daymond, M. R.
Kardjilov, N.
author2_role author
author
author
author
author
author
dc.subject.none.fl_str_mv neutron imaging
hydrogen diffusion
in-situ imaging
zircnoim alloys
topic neutron imaging
hydrogen diffusion
in-situ imaging
zircnoim alloys
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv Absorbed hydrogen degrades the mechanical properties of zirconium alloys used for nuclear fuel claddings. Not only the total amount of hydrogen absorbed in the cladding tube but also the zirconium hydride orientation and its distribution influence the toughness of the material. For instance, the so-called delayed hydride cracking is caused by the diffusive re-distribution of hydrogen into the dilative elastic strain field ahead of crack tips. The paper presents in-situ and ex-situ neutron imaging investigations of hydrogen uptake, diffusion and distribution in zirconium alloys used for claddings. An overview about results of in-situ experiments studying the hydrogen uptake in strained Zircaloy-4, as well as ex-situ investigations of the diffusion of hydrogen in cold rolled Zircaloy-2 and Zr-2.5 % Nb alloy depending on temperature, rolling direction and thermal treatment and of the hydrogen re-distribution in the b-phase of Zircaloy-4 during a Three-Point-Bending-Test at 600 8C are presented.
Fil: Grosse, M.. Karlsruher Institut für Technology; Alemania
Fil: Santisteban, Javier Roberto. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas. Centro Científico Tecnológico Conicet - Patagonia Norte; Argentina
Fil: Bertsch, J.. Paul Scherrer Institut; Suiza
Fil: Schillinger, B.. Universitat Technical Zu Munich; Alemania
Fil: Kaestner, A.. Paul Scherrer Institut; Suiza
Fil: Daymond, M. R.. Queens University; Canadá
Fil: Kardjilov, N.. Helmholtz Zentrum Berlin; Alemania
description Absorbed hydrogen degrades the mechanical properties of zirconium alloys used for nuclear fuel claddings. Not only the total amount of hydrogen absorbed in the cladding tube but also the zirconium hydride orientation and its distribution influence the toughness of the material. For instance, the so-called delayed hydride cracking is caused by the diffusive re-distribution of hydrogen into the dilative elastic strain field ahead of crack tips. The paper presents in-situ and ex-situ neutron imaging investigations of hydrogen uptake, diffusion and distribution in zirconium alloys used for claddings. An overview about results of in-situ experiments studying the hydrogen uptake in strained Zircaloy-4, as well as ex-situ investigations of the diffusion of hydrogen in cold rolled Zircaloy-2 and Zr-2.5 % Nb alloy depending on temperature, rolling direction and thermal treatment and of the hydrogen re-distribution in the b-phase of Zircaloy-4 during a Three-Point-Bending-Test at 600 8C are presented.
publishDate 2018
dc.date.none.fl_str_mv 2018-12
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/11336/125268
Grosse, M.; Santisteban, Javier Roberto; Bertsch, J.; Schillinger, B.; Kaestner, A.; et al.; Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging; Carl Hanser Verlag; Kerntechnik; 83; 6; 12-2018; 495-501
0932-3902
CONICET Digital
CONICET
url http://hdl.handle.net/11336/125268
identifier_str_mv Grosse, M.; Santisteban, Javier Roberto; Bertsch, J.; Schillinger, B.; Kaestner, A.; et al.; Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging; Carl Hanser Verlag; Kerntechnik; 83; 6; 12-2018; 495-501
0932-3902
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.hanser-elibrary.com/doi/10.3139/124.110946
info:eu-repo/semantics/altIdentifier/doi/10.3139/124.110946
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
eu_rights_str_mv openAccess
rights_invalid_str_mv https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Carl Hanser Verlag
publisher.none.fl_str_mv Carl Hanser Verlag
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
_version_ 1844613458215043072
score 13.070432

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