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
- Institución
- Consejo Nacional de Investigaciones Científicas y Técnicas
- OAI Identificador
- oai:ri.conicet.gov.ar:11336/168938
Ver los metadatos del registro completo
id |
CONICETDig_8fb34492907ea1396f8cde5c3087f183 |
---|---|
oai_identifier_str |
oai:ri.conicet.gov.ar:11336/168938 |
network_acronym_str |
CONICETDig |
repository_id_str |
3498 |
network_name_str |
CONICET Digital (CONICET) |
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 |
_version_ |
1846082986808705024 |
score |
13.22299 |