Monitoring reinforcement corrosion of concretes designed for nuclear facilitie

Detalhes bibliográficos
Autor(a) principal: Vazquez,Damián
Data de Publicação: 2018
Outros Autores: Duffó,Gustavo
Tipo de documento: Artigo
Idioma: eng
Título da fonte: Matéria (Rio de Janeiro. Online)
Texto Completo: http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1517-70762018000200457
Resumo: ABSTRACT The facilities designed for the peaceful activities of nuclear energy are made with different materials, among them, reinforced concrete. This material, in addition to being structural, is a barrier for isolation and confinement from the environment of the radioactive materials. One of its degradation mechanisms is the corrosion of the reinforcement, a frequent cause of premature failure in service. Consequently, it is essential to study this degradation mechanism in formulations developed for this purpose, as well as the development and implementation of monitoring techniques. The objective of this work is to compare, from the corrosion of reinforcement point of view, two concrete formulations, one made with ordinary portland cement and the other with pozzolanic portland cement. Both formulations are candidate for some nuclear applications, such as the Low Radioactive Waste disposal facilities, whose durability requirement is higher than 300 years. The results of approximately four years of monitoring are presented. The parameters followed are: corrosion potential and corrosion rate of the reinforcements, electrical resistivity, oxygen flow, internal temperature and carbonation rate of concrete. These parameters were measured and monitored in reinforced concrete specimens by embedded sensors previously developed in our laboratory. Also, unreinforced specimens were prepared to measure the carbonation rate. The presence of reinforcements provides the possibility of monitoring directly on them the corrosion potential, the corrosion rate and electrical resistivity of concrete, using on-surface electrodes provided by a commercial instrument. This allows the comparison of the parameters monitored by embedded sensors and the on-surface electrodes.
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spelling Monitoring reinforcement corrosion of concretes designed for nuclear facilitieReinforced concrete corrosiondurability of reinforced concretenuclear materialsABSTRACT The facilities designed for the peaceful activities of nuclear energy are made with different materials, among them, reinforced concrete. This material, in addition to being structural, is a barrier for isolation and confinement from the environment of the radioactive materials. One of its degradation mechanisms is the corrosion of the reinforcement, a frequent cause of premature failure in service. Consequently, it is essential to study this degradation mechanism in formulations developed for this purpose, as well as the development and implementation of monitoring techniques. The objective of this work is to compare, from the corrosion of reinforcement point of view, two concrete formulations, one made with ordinary portland cement and the other with pozzolanic portland cement. Both formulations are candidate for some nuclear applications, such as the Low Radioactive Waste disposal facilities, whose durability requirement is higher than 300 years. The results of approximately four years of monitoring are presented. The parameters followed are: corrosion potential and corrosion rate of the reinforcements, electrical resistivity, oxygen flow, internal temperature and carbonation rate of concrete. These parameters were measured and monitored in reinforced concrete specimens by embedded sensors previously developed in our laboratory. Also, unreinforced specimens were prepared to measure the carbonation rate. The presence of reinforcements provides the possibility of monitoring directly on them the corrosion potential, the corrosion rate and electrical resistivity of concrete, using on-surface electrodes provided by a commercial instrument. This allows the comparison of the parameters monitored by embedded sensors and the on-surface electrodes.Laboratório de Hidrogênio, Coppe - Universidade Federal do Rio de Janeiroem cooperação com a Associação Brasileira do Hidrogênio, ABH22018-01-01info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersiontext/htmlhttp://old.scielo.br/scielo.php?script=sci_arttext&pid=S1517-70762018000200457Matéria (Rio de Janeiro) v.23 n.2 2018reponame:Matéria (Rio de Janeiro. Online)instname:Matéria (Rio de Janeiro. Online)instacron:RLAM10.1590/s1517-707620180002.0383info:eu-repo/semantics/openAccessVazquez,DamiánDuffó,Gustavoeng2018-07-16T00:00:00Zoai:scielo:S1517-70762018000200457Revistahttp://www.materia.coppe.ufrj.br/https://old.scielo.br/oai/scielo-oai.php||materia@labh2.coppe.ufrj.br1517-70761517-7076opendoar:2018-07-16T00:00Matéria (Rio de Janeiro. Online) - Matéria (Rio de Janeiro. Online)false
dc.title.none.fl_str_mv Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
title Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
spellingShingle Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
Vazquez,Damián
Reinforced concrete corrosion
durability of reinforced concrete
nuclear materials
title_short Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
title_full Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
title_fullStr Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
title_full_unstemmed Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
title_sort Monitoring reinforcement corrosion of concretes designed for nuclear facilitie
author Vazquez,Damián
author_facet Vazquez,Damián
Duffó,Gustavo
author_role author
author2 Duffó,Gustavo
author2_role author
dc.contributor.author.fl_str_mv Vazquez,Damián
Duffó,Gustavo
dc.subject.por.fl_str_mv Reinforced concrete corrosion
durability of reinforced concrete
nuclear materials
topic Reinforced concrete corrosion
durability of reinforced concrete
nuclear materials
description ABSTRACT The facilities designed for the peaceful activities of nuclear energy are made with different materials, among them, reinforced concrete. This material, in addition to being structural, is a barrier for isolation and confinement from the environment of the radioactive materials. One of its degradation mechanisms is the corrosion of the reinforcement, a frequent cause of premature failure in service. Consequently, it is essential to study this degradation mechanism in formulations developed for this purpose, as well as the development and implementation of monitoring techniques. The objective of this work is to compare, from the corrosion of reinforcement point of view, two concrete formulations, one made with ordinary portland cement and the other with pozzolanic portland cement. Both formulations are candidate for some nuclear applications, such as the Low Radioactive Waste disposal facilities, whose durability requirement is higher than 300 years. The results of approximately four years of monitoring are presented. The parameters followed are: corrosion potential and corrosion rate of the reinforcements, electrical resistivity, oxygen flow, internal temperature and carbonation rate of concrete. These parameters were measured and monitored in reinforced concrete specimens by embedded sensors previously developed in our laboratory. Also, unreinforced specimens were prepared to measure the carbonation rate. The presence of reinforcements provides the possibility of monitoring directly on them the corrosion potential, the corrosion rate and electrical resistivity of concrete, using on-surface electrodes provided by a commercial instrument. This allows the comparison of the parameters monitored by embedded sensors and the on-surface electrodes.
publishDate 2018
dc.date.none.fl_str_mv 2018-01-01
dc.type.driver.fl_str_mv info:eu-repo/semantics/article
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
format article
status_str publishedVersion
dc.identifier.uri.fl_str_mv http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1517-70762018000200457
url http://old.scielo.br/scielo.php?script=sci_arttext&pid=S1517-70762018000200457
dc.language.iso.fl_str_mv eng
language eng
dc.relation.none.fl_str_mv 10.1590/s1517-707620180002.0383
dc.rights.driver.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv text/html
dc.publisher.none.fl_str_mv Laboratório de Hidrogênio, Coppe - Universidade Federal do Rio de Janeiro
em cooperação com a Associação Brasileira do Hidrogênio, ABH2
publisher.none.fl_str_mv Laboratório de Hidrogênio, Coppe - Universidade Federal do Rio de Janeiro
em cooperação com a Associação Brasileira do Hidrogênio, ABH2
dc.source.none.fl_str_mv Matéria (Rio de Janeiro) v.23 n.2 2018
reponame:Matéria (Rio de Janeiro. Online)
instname:Matéria (Rio de Janeiro. Online)
instacron:RLAM
instname_str Matéria (Rio de Janeiro. Online)
instacron_str RLAM
institution RLAM
reponame_str Matéria (Rio de Janeiro. Online)
collection Matéria (Rio de Janeiro. Online)
repository.name.fl_str_mv Matéria (Rio de Janeiro. Online) - Matéria (Rio de Janeiro. Online)
repository.mail.fl_str_mv ||materia@labh2.coppe.ufrj.br
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