Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review

Autores
Rodríguez, Martín Alejandro
Año de publicación
2020
Idioma
inglés
Tipo de recurso
artículo
Estado
versión publicada
Descripción
Nuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators and other components of the secondary cooling system from corrosion during plant outages.
Fil: Rodríguez, Martín Alejandro. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Unidad de Actividad de Materiales (CAC); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Materia
CORROSION
HEAT TRANSFER CREVICE
HYDRAZINE LAY-UP
PRESSURIZED WATER REACTOR
STEAM GENERATOR
STRESS CORROSION CRACKING
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:11336/168938

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spelling Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A reviewRodríguez, Martín AlejandroCORROSIONHEAT TRANSFER CREVICEHYDRAZINE LAY-UPPRESSURIZED WATER REACTORSTEAM GENERATORSTRESS CORROSION CRACKINGhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2Nuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators and other components of the secondary cooling system from corrosion during plant outages.Fil: Rodríguez, Martín Alejandro. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Unidad de Actividad de Materiales (CAC); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFreund Publishing House Ltd2020-06-04info: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/11336/168938Rodríguez, Martín Alejandro; Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review; Freund Publishing House Ltd; CORROSION REVIEWS - (Print); 38; 3; 4-6-2020; 1-360334-60052191-0316CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://www.degruyter.com/view/journals/corrrev/ahead-of-print/article-10.1515-corrrev-2020-0015/article-10.1515-corrrev-2020-0015.xmlinfo:eu-repo/semantics/altIdentifier/doi/10.1515/corrrev-2020-0015info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-15T14:47:08Zoai:ri.conicet.gov.ar:11336/168938instacron: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 14:47:09.274CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse
dc.title.none.fl_str_mv Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
title Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
spellingShingle Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
Rodríguez, Martín Alejandro
CORROSION
HEAT TRANSFER CREVICE
HYDRAZINE LAY-UP
PRESSURIZED WATER REACTOR
STEAM GENERATOR
STRESS CORROSION CRACKING
title_short Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
title_full Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
title_fullStr Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
title_full_unstemmed Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
title_sort Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review
dc.creator.none.fl_str_mv Rodríguez, Martín Alejandro
author Rodríguez, Martín Alejandro
author_facet Rodríguez, Martín Alejandro
author_role author
dc.subject.none.fl_str_mv CORROSION
HEAT TRANSFER CREVICE
HYDRAZINE LAY-UP
PRESSURIZED WATER REACTOR
STEAM GENERATOR
STRESS CORROSION CRACKING
topic CORROSION
HEAT TRANSFER CREVICE
HYDRAZINE LAY-UP
PRESSURIZED WATER REACTOR
STEAM GENERATOR
STRESS CORROSION CRACKING
purl_subject.fl_str_mv https://purl.org/becyt/ford/2.5
https://purl.org/becyt/ford/2
dc.description.none.fl_txt_mv Nuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators and other components of the secondary cooling system from corrosion during plant outages.
Fil: Rodríguez, Martín Alejandro. Comisión Nacional de Energía Atómica. Gerencia del Área de Energía Nuclear. Unidad de Actividad de Materiales (CAC); Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
description Nuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators and other components of the secondary cooling system from corrosion during plant outages.
publishDate 2020
dc.date.none.fl_str_mv 2020-06-04
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/11336/168938
Rodríguez, Martín Alejandro; Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review; Freund Publishing House Ltd; CORROSION REVIEWS - (Print); 38; 3; 4-6-2020; 1-36
0334-6005
2191-0316
CONICET Digital
CONICET
url http://hdl.handle.net/11336/168938
identifier_str_mv Rodríguez, Martín Alejandro; Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: A review; Freund Publishing House Ltd; CORROSION REVIEWS - (Print); 38; 3; 4-6-2020; 1-36
0334-6005
2191-0316
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.degruyter.com/view/journals/corrrev/ahead-of-print/article-10.1515-corrrev-2020-0015/article-10.1515-corrrev-2020-0015.xml
info:eu-repo/semantics/altIdentifier/doi/10.1515/corrrev-2020-0015
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
application/pdf
dc.publisher.none.fl_str_mv Freund Publishing House Ltd
publisher.none.fl_str_mv Freund Publishing House 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 13.22299