Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys
Autor(a) principal: | |
---|---|
Data de Publicação: | 2020 |
Outros Autores: | , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/30719 |
Resumo: | In pressurized water reactors (PWR) the fuel rod cladding is the first barrier against the spread of fission products. It is therefore essential to guarantee its use in the reactor. Sometimes the production of electricity requires that certain power plants operate in ???network monitoring???. The fuel introduced into nuclear power reactors can then undergo so metimes significant power variations. Following a severe reactor power transient, clad failure can occur through a stress corrosion phenomenon (SCC), under the combined action of mechanical stresses and gaseous fission products generated by the fuel pellets. Among those iodine plays a major role, for it may induce SCC in zircaloy. In the early ages of water cooled reactors (PWRs, BWRs or CANDU), series of similar failures took place following sharp startups. Today power increase rates as well as instantaneous local power levels are limited. Indeed, it is well know that cladding failure by iodine induced stress corrosion cracking (I SCC) may occur under pellet cladding interactions (PCI) conditions during power transients in PWRs. In this paper we review the advances in the understanding of these SCC cracking mechanisms of the fuel rod cladding that would then allow better control of the integrity of the clad during the more severe demands related to the operating conditions of th e PWRs. |
id |
IPEN_828b3170075a9df6ee7e23b28714310f |
---|---|
oai_identifier_str |
oai:repositorio.ipen.br:123456789/30719 |
network_acronym_str |
IPEN |
network_name_str |
Repositório Institucional do IPEN |
repository_id_str |
4510 |
spelling |
2020-01-15T17:56:01Z2020-01-15T17:56:01ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/30719In pressurized water reactors (PWR) the fuel rod cladding is the first barrier against the spread of fission products. It is therefore essential to guarantee its use in the reactor. Sometimes the production of electricity requires that certain power plants operate in ???network monitoring???. The fuel introduced into nuclear power reactors can then undergo so metimes significant power variations. Following a severe reactor power transient, clad failure can occur through a stress corrosion phenomenon (SCC), under the combined action of mechanical stresses and gaseous fission products generated by the fuel pellets. Among those iodine plays a major role, for it may induce SCC in zircaloy. In the early ages of water cooled reactors (PWRs, BWRs or CANDU), series of similar failures took place following sharp startups. Today power increase rates as well as instantaneous local power levels are limited. Indeed, it is well know that cladding failure by iodine induced stress corrosion cracking (I SCC) may occur under pellet cladding interactions (PCI) conditions during power transients in PWRs. In this paper we review the advances in the understanding of these SCC cracking mechanisms of the fuel rod cladding that would then allow better control of the integrity of the clad during the more severe demands related to the operating conditions of th e PWRs.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T17:56:01Z No. of bitstreams: 1 26372.pdf: 194698 bytes, checksum: ac5944fab601653baf46cebd017a888b (MD5)Made available in DSpace on 2020-01-15T17:56:01Z (GMT). No. of bitstreams: 1 26372.pdf: 194698 bytes, checksum: ac5944fab601653baf46cebd017a888b (MD5)5339-5345Associa????o Brasileira de Energia Nuclearcladdingcleavagecomputerized tomographycrackingfuel rodsiodinenucleationpitting corrosionpwr type reactorsslipstress corrosionzircaloy 4Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloysinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP4661153600600LOBO, RAQUEL de M.ANDRADE, ARNALDO H.P. deINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263722019ANDRADE, ARNALDO H.P. deLOBO, RAQUEL de M.20-01Proceedings1153466ANDRADE, ARNALDO H.P. de:1153:730:NLOBO, RAQUEL de M.:466:450:SORIGINAL26372.pdf26372.pdfapplication/pdf194698http://repositorio.ipen.br/bitstream/123456789/30719/1/26372.pdfac5944fab601653baf46cebd017a888bMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30719/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/307192020-04-12 22:00:21.923oai:repositorio.ipen.br:123456789/30719Tk9URTogUExBQ0UgWU9VUiBPV04gTElDRU5TRSBIRVJFClRoaXMgc2FtcGxlIGxpY2Vuc2UgaXMgcHJvdmlkZWQgZm9yIGluZm9ybWF0aW9uYWwgcHVycG9zZXMgb25seS4KCk5PTi1FWENMVVNJVkUgRElTVFJJQlVUSU9OIExJQ0VOU0UKCkJ5IHNpZ25pbmcgYW5kIHN1Ym1pdHRpbmcgdGhpcyBsaWNlbnNlLCB5b3UgKHRoZSBhdXRob3Iocykgb3IgY29weXJpZ2h0Cm93bmVyKSBncmFudHMgdG8gRFNwYWNlIFVuaXZlcnNpdHkgKERTVSkgdGhlIG5vbi1leGNsdXNpdmUgcmlnaHQgdG8gcmVwcm9kdWNlLAp0cmFuc2xhdGUgKGFzIGRlZmluZWQgYmVsb3cpLCBhbmQvb3IgZGlzdHJpYnV0ZSB5b3VyIHN1Ym1pc3Npb24gKGluY2x1ZGluZwp0aGUgYWJzdHJhY3QpIHdvcmxkd2lkZSBpbiBwcmludCBhbmQgZWxlY3Ryb25pYyBmb3JtYXQgYW5kIGluIGFueSBtZWRpdW0sCmluY2x1ZGluZyBidXQgbm90IGxpbWl0ZWQgdG8gYXVkaW8gb3IgdmlkZW8uCgpZb3UgYWdyZWUgdGhhdCBEU1UgbWF5LCB3aXRob3V0IGNoYW5naW5nIHRoZSBjb250ZW50LCB0cmFuc2xhdGUgdGhlCnN1Ym1pc3Npb24gdG8gYW55IG1lZGl1bSBvciBmb3JtYXQgZm9yIHRoZSBwdXJwb3NlIG9mIHByZXNlcnZhdGlvbi4KCllvdSBhbHNvIGFncmVlIHRoYXQgRFNVIG1heSBrZWVwIG1vcmUgdGhhbiBvbmUgY29weSBvZiB0aGlzIHN1Ym1pc3Npb24gZm9yCnB1cnBvc2VzIG9mIHNlY3VyaXR5LCBiYWNrLXVwIGFuZCBwcmVzZXJ2YXRpb24uCgpZb3UgcmVwcmVzZW50IHRoYXQgdGhlIHN1Ym1pc3Npb24gaXMgeW91ciBvcmlnaW5hbCB3b3JrLCBhbmQgdGhhdCB5b3UgaGF2ZQp0aGUgcmlnaHQgdG8gZ3JhbnQgdGhlIHJpZ2h0cyBjb250YWluZWQgaW4gdGhpcyBsaWNlbnNlLiBZb3UgYWxzbyByZXByZXNlbnQKdGhhdCB5b3VyIHN1Ym1pc3Npb24gZG9lcyBub3QsIHRvIHRoZSBiZXN0IG9mIHlvdXIga25vd2xlZGdlLCBpbmZyaW5nZSB1cG9uCmFueW9uZSdzIGNvcHlyaWdodC4KCklmIHRoZSBzdWJtaXNzaW9uIGNvbnRhaW5zIG1hdGVyaWFsIGZvciB3aGljaCB5b3UgZG8gbm90IGhvbGQgY29weXJpZ2h0LAp5b3UgcmVwcmVzZW50IHRoYXQgeW91IGhhdmUgb2J0YWluZWQgdGhlIHVucmVzdHJpY3RlZCBwZXJtaXNzaW9uIG9mIHRoZQpjb3B5cmlnaHQgb3duZXIgdG8gZ3JhbnQgRFNVIHRoZSByaWdodHMgcmVxdWlyZWQgYnkgdGhpcyBsaWNlbnNlLCBhbmQgdGhhdApzdWNoIHRoaXJkLXBhcnR5IG93bmVkIG1hdGVyaWFsIGlzIGNsZWFybHkgaWRlbnRpZmllZCBhbmQgYWNrbm93bGVkZ2VkCndpdGhpbiB0aGUgdGV4dCBvciBjb250ZW50IG9mIHRoZSBzdWJtaXNzaW9uLgoKSUYgVEhFIFNVQk1JU1NJT04gSVMgQkFTRUQgVVBPTiBXT1JLIFRIQVQgSEFTIEJFRU4gU1BPTlNPUkVEIE9SIFNVUFBPUlRFRApCWSBBTiBBR0VOQ1kgT1IgT1JHQU5JWkFUSU9OIE9USEVSIFRIQU4gRFNVLCBZT1UgUkVQUkVTRU5UIFRIQVQgWU9VIEhBVkUKRlVMRklMTEVEIEFOWSBSSUdIVCBPRiBSRVZJRVcgT1IgT1RIRVIgT0JMSUdBVElPTlMgUkVRVUlSRUQgQlkgU1VDSApDT05UUkFDVCBPUiBBR1JFRU1FTlQuCgpEU1Ugd2lsbCBjbGVhcmx5IGlkZW50aWZ5IHlvdXIgbmFtZShzKSBhcyB0aGUgYXV0aG9yKHMpIG9yIG93bmVyKHMpIG9mIHRoZQpzdWJtaXNzaW9uLCBhbmQgd2lsbCBub3QgbWFrZSBhbnkgYWx0ZXJhdGlvbiwgb3RoZXIgdGhhbiBhcyBhbGxvd2VkIGJ5IHRoaXMKbGljZW5zZSwgdG8geW91ciBzdWJtaXNzaW9uLgo=Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-04-12T22:00:21Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
title |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
spellingShingle |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys LOBO, RAQUEL de M. cladding cleavage computerized tomography cracking fuel rods iodine nucleation pitting corrosion pwr type reactors slip stress corrosion zircaloy 4 |
title_short |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
title_full |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
title_fullStr |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
title_full_unstemmed |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
title_sort |
Advances in the understanding of the mechanisms of iodine-induced SCC cracking in zirconium alloys |
author |
LOBO, RAQUEL de M. |
author_facet |
LOBO, RAQUEL de M. ANDRADE, ARNALDO H.P. de INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
ANDRADE, ARNALDO H.P. de INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author |
dc.contributor.author.fl_str_mv |
LOBO, RAQUEL de M. ANDRADE, ARNALDO H.P. de INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
cladding cleavage computerized tomography cracking fuel rods iodine nucleation pitting corrosion pwr type reactors slip stress corrosion zircaloy 4 |
topic |
cladding cleavage computerized tomography cracking fuel rods iodine nucleation pitting corrosion pwr type reactors slip stress corrosion zircaloy 4 |
description |
In pressurized water reactors (PWR) the fuel rod cladding is the first barrier against the spread of fission products. It is therefore essential to guarantee its use in the reactor. Sometimes the production of electricity requires that certain power plants operate in ???network monitoring???. The fuel introduced into nuclear power reactors can then undergo so metimes significant power variations. Following a severe reactor power transient, clad failure can occur through a stress corrosion phenomenon (SCC), under the combined action of mechanical stresses and gaseous fission products generated by the fuel pellets. Among those iodine plays a major role, for it may induce SCC in zircaloy. In the early ages of water cooled reactors (PWRs, BWRs or CANDU), series of similar failures took place following sharp startups. Today power increase rates as well as instantaneous local power levels are limited. Indeed, it is well know that cladding failure by iodine induced stress corrosion cracking (I SCC) may occur under pellet cladding interactions (PCI) conditions during power transients in PWRs. In this paper we review the advances in the understanding of these SCC cracking mechanisms of the fuel rod cladding that would then allow better control of the integrity of the clad during the more severe demands related to the operating conditions of th e PWRs. |
publishDate |
2020 |
dc.date.evento.pt_BR.fl_str_mv |
October 21-25, 2019 |
dc.date.accessioned.fl_str_mv |
2020-01-15T17:56:01Z |
dc.date.available.fl_str_mv |
2020-01-15T17:56:01Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/conferenceObject |
format |
conferenceObject |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/30719 |
url |
http://repositorio.ipen.br/handle/123456789/30719 |
dc.relation.authority.fl_str_mv |
466 1153 |
dc.relation.confidence.fl_str_mv |
600 600 |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.format.none.fl_str_mv |
5339-5345 |
dc.coverage.pt_BR.fl_str_mv |
I |
dc.publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
dc.source.none.fl_str_mv |
reponame:Repositório Institucional do IPEN instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN) instacron:IPEN |
instname_str |
Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
instacron_str |
IPEN |
institution |
IPEN |
reponame_str |
Repositório Institucional do IPEN |
collection |
Repositório Institucional do IPEN |
bitstream.url.fl_str_mv |
http://repositorio.ipen.br/bitstream/123456789/30719/1/26372.pdf http://repositorio.ipen.br/bitstream/123456789/30719/2/license.txt |
bitstream.checksum.fl_str_mv |
ac5944fab601653baf46cebd017a888b 8a4605be74aa9ea9d79846c1fba20a33 |
bitstream.checksumAlgorithm.fl_str_mv |
MD5 MD5 |
repository.name.fl_str_mv |
Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
repository.mail.fl_str_mv |
bibl@ipen.br |
_version_ |
1767254250635657216 |