Structural integrity assessments of steam generator tubes using the FAD methodology

Autores
Bergant, Marcos Antonio; Yawny, Alejandro Andres; Perez Ipiña, Juan Elias
Año de publicación
2015
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Steam generator tubes (SGTs) represents up to 60% of the total primary pressure retaining boundary area of a nuclear power plant. They have been found susceptible to diverse degradation mechanisms during service. Due to the significance of a SGT failure on the plant safe operation, nuclear regulatory authorities have established tube plugging or repairing criteria which are based on the defect depth. The widespreadly used "40% criterion" proposed in the 70s is an example whose use is still recommended in the last editions of the ASME Boiler and Pressure Vessel Code. In the present work, an alternative, more realistic and less conservative methodology for SGT integrity evaluation is proposed. It is based on the Failure Assessment Diagram (FAD) and takes advantage of the recent developments in non-destructive techniques which allow a more comprehensive characterization of tube defects, i.e., depth, length, orientation and type. The proposed approach has been applied to: the study of the influence of primary and secondary stresses on tube integrity; the prediction of failure mode (i.e., ductile fracture or plastic collapse) of defective SGTs for varied crack geometries and loading conditions; the analysis of the sensibility of tensile and fracture properties with temperature. The potentiality of the FAD as a comprehensive methodology for predicting the failure loads and failure modes of flawed SGTs is highlighted.
Fil: Bergant, Marcos Antonio. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
Fil: Yawny, Alejandro Andres. 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: Perez Ipiña, Juan Elias. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional del Comahue; Argentina
Materia
Structural Integrity
Steam Generator Tubes
Fad
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:11336/50246
Acceder
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network_name_str CONICET Digital (CONICET)
spelling Structural integrity assessments of steam generator tubes using the FAD methodologyBergant, Marcos AntonioYawny, Alejandro AndresPerez Ipiña, Juan EliasStructural IntegritySteam Generator TubesFadhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Steam generator tubes (SGTs) represents up to 60% of the total primary pressure retaining boundary area of a nuclear power plant. They have been found susceptible to diverse degradation mechanisms during service. Due to the significance of a SGT failure on the plant safe operation, nuclear regulatory authorities have established tube plugging or repairing criteria which are based on the defect depth. The widespreadly used "40% criterion" proposed in the 70s is an example whose use is still recommended in the last editions of the ASME Boiler and Pressure Vessel Code. In the present work, an alternative, more realistic and less conservative methodology for SGT integrity evaluation is proposed. It is based on the Failure Assessment Diagram (FAD) and takes advantage of the recent developments in non-destructive techniques which allow a more comprehensive characterization of tube defects, i.e., depth, length, orientation and type. The proposed approach has been applied to: the study of the influence of primary and secondary stresses on tube integrity; the prediction of failure mode (i.e., ductile fracture or plastic collapse) of defective SGTs for varied crack geometries and loading conditions; the analysis of the sensibility of tensile and fracture properties with temperature. The potentiality of the FAD as a comprehensive methodology for predicting the failure loads and failure modes of flawed SGTs is highlighted.Fil: Bergant, Marcos Antonio. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; ArgentinaFil: Yawny, Alejandro Andres. Comision Nacional de Energía Atómica. Gerencia de Área Investigaciones y Aplicaciones no Nucleares. Gerencia de Física (Centro Atómico Bariloche). División Física de Metales; ArgentinaFil: Perez Ipiña, Juan Elias. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional del Comahue; ArgentinaElsevier Science Sa2015-12info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/50246Bergant, Marcos Antonio; Yawny, Alejandro Andres; Perez Ipiña, Juan Elias; Structural integrity assessments of steam generator tubes using the FAD methodology; Elsevier Science Sa; Nuclear Engineering and Design; 295; 12-2015; 457-4670029-5493CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2015.09.022info:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549315004306info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-15T15:46:32Zoai:ri.conicet.gov.ar:11336/50246instacron: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:34982025-10-15 15:46:32.392CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Structural integrity assessments of steam generator tubes using the FAD methodology
title Structural integrity assessments of steam generator tubes using the FAD methodology
spellingShingle Structural integrity assessments of steam generator tubes using the FAD methodology
Bergant, Marcos Antonio
Structural Integrity
Steam Generator Tubes
Fad
title_short Structural integrity assessments of steam generator tubes using the FAD methodology
title_full Structural integrity assessments of steam generator tubes using the FAD methodology
title_fullStr Structural integrity assessments of steam generator tubes using the FAD methodology
title_full_unstemmed Structural integrity assessments of steam generator tubes using the FAD methodology
title_sort Structural integrity assessments of steam generator tubes using the FAD methodology
dc.creator.none.fl_str_mv Bergant, Marcos Antonio
Yawny, Alejandro Andres
Perez Ipiña, Juan Elias
author Bergant, Marcos Antonio
author_facet Bergant, Marcos Antonio
Yawny, Alejandro Andres
Perez Ipiña, Juan Elias
author_role author
author2 Yawny, Alejandro Andres
Perez Ipiña, Juan Elias
author2_role author
author
dc.subject.none.fl_str_mv Structural Integrity
Steam Generator Tubes
Fad
topic Structural Integrity
Steam Generator Tubes
Fad
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv Steam generator tubes (SGTs) represents up to 60% of the total primary pressure retaining boundary area of a nuclear power plant. They have been found susceptible to diverse degradation mechanisms during service. Due to the significance of a SGT failure on the plant safe operation, nuclear regulatory authorities have established tube plugging or repairing criteria which are based on the defect depth. The widespreadly used "40% criterion" proposed in the 70s is an example whose use is still recommended in the last editions of the ASME Boiler and Pressure Vessel Code. In the present work, an alternative, more realistic and less conservative methodology for SGT integrity evaluation is proposed. It is based on the Failure Assessment Diagram (FAD) and takes advantage of the recent developments in non-destructive techniques which allow a more comprehensive characterization of tube defects, i.e., depth, length, orientation and type. The proposed approach has been applied to: the study of the influence of primary and secondary stresses on tube integrity; the prediction of failure mode (i.e., ductile fracture or plastic collapse) of defective SGTs for varied crack geometries and loading conditions; the analysis of the sensibility of tensile and fracture properties with temperature. The potentiality of the FAD as a comprehensive methodology for predicting the failure loads and failure modes of flawed SGTs is highlighted.
Fil: Bergant, Marcos Antonio. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
Fil: Yawny, Alejandro Andres. 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: Perez Ipiña, Juan Elias. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Universidad Nacional del Comahue; Argentina
description Steam generator tubes (SGTs) represents up to 60% of the total primary pressure retaining boundary area of a nuclear power plant. They have been found susceptible to diverse degradation mechanisms during service. Due to the significance of a SGT failure on the plant safe operation, nuclear regulatory authorities have established tube plugging or repairing criteria which are based on the defect depth. The widespreadly used "40% criterion" proposed in the 70s is an example whose use is still recommended in the last editions of the ASME Boiler and Pressure Vessel Code. In the present work, an alternative, more realistic and less conservative methodology for SGT integrity evaluation is proposed. It is based on the Failure Assessment Diagram (FAD) and takes advantage of the recent developments in non-destructive techniques which allow a more comprehensive characterization of tube defects, i.e., depth, length, orientation and type. The proposed approach has been applied to: the study of the influence of primary and secondary stresses on tube integrity; the prediction of failure mode (i.e., ductile fracture or plastic collapse) of defective SGTs for varied crack geometries and loading conditions; the analysis of the sensibility of tensile and fracture properties with temperature. The potentiality of the FAD as a comprehensive methodology for predicting the failure loads and failure modes of flawed SGTs is highlighted.
publishDate 2015
dc.date.none.fl_str_mv 2015-12
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/11336/50246
Bergant, Marcos Antonio; Yawny, Alejandro Andres; Perez Ipiña, Juan Elias; Structural integrity assessments of steam generator tubes using the FAD methodology; Elsevier Science Sa; Nuclear Engineering and Design; 295; 12-2015; 457-467
0029-5493
CONICET Digital
CONICET
url http://hdl.handle.net/11336/50246
identifier_str_mv Bergant, Marcos Antonio; Yawny, Alejandro Andres; Perez Ipiña, Juan Elias; Structural integrity assessments of steam generator tubes using the FAD methodology; Elsevier Science Sa; Nuclear Engineering and Design; 295; 12-2015; 457-467
0029-5493
CONICET Digital
CONICET
dc.language.none.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2015.09.022
info:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549315004306
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 Elsevier Science Sa
publisher.none.fl_str_mv Elsevier Science Sa
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 13.22299

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