A discussion about simplified methodologies for failure assessment of nuclear reactor components

Detalhes bibliográficos
Autor(a) principal: CRUZ, J.R.B.
Data de Publicação: 2014
Outros Autores: LANDES, J.D., PAES de ANDRADE, A.H., ASME PRESSURE VESSEL AND PIPING CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/13595
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spelling 2014-11-17T17:23:50Z2014-11-18T17:21:54Z2015-04-01T23:58:14Z2014-11-17T17:23:50Z2014-11-18T17:21:54Z2015-04-01T23:58:14ZJuly 21-26, 1996http://repositorio.ipen.br/handle/123456789/13595Made available in DSpace on 2014-11-17T17:23:50Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T17:21:54Z (GMT). No. of bitstreams: 1 04878.pdf: 298077 bytes, checksum: a59d1b0fd64780f9029124210b9c29c9 (MD5)Made available in DSpace on 2015-04-01T23:58:14Z (GMT). No. of bitstreams: 1 04878.pdf: 298077 bytes, checksum: a59d1b0fd64780f9029124210b9c29c9 (MD5)reactor componentsfailurespressure vesselspipescracksductilityfracture propertiesA discussion about simplified methodologies for failure assessment of nuclear reactor componentsinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectIMontreal, CanadaCRUZ, J.R.B.LANDES, J.D.PAES de ANDRADE, A.H.ASME PRESSURE VESSEL AND PIPING CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN048781996PAES de ANDRADE, A.H.96-111729-11153CRUZ, J.R.B.:1729:-1:SLANDES, J.D.:-1:-1:NPAES de ANDRADE, A.H.:1153:-1:NORIGINAL04878.pdfapplication/pdf298077http://repositorio.ipen.br/bitstream/123456789/13595/1/04878.pdfa59d1b0fd64780f9029124210b9c29c9MD51123456789/135952015-04-01 23:58:14.217oai:repositorio.ipen.br:123456789/13595Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102015-04-01T23:58:14Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv A discussion about simplified methodologies for failure assessment of nuclear reactor components
title A discussion about simplified methodologies for failure assessment of nuclear reactor components
spellingShingle A discussion about simplified methodologies for failure assessment of nuclear reactor components
CRUZ, J.R.B.
reactor components
failures
pressure vessels
pipes
cracks
ductility
fracture properties
title_short A discussion about simplified methodologies for failure assessment of nuclear reactor components
title_full A discussion about simplified methodologies for failure assessment of nuclear reactor components
title_fullStr A discussion about simplified methodologies for failure assessment of nuclear reactor components
title_full_unstemmed A discussion about simplified methodologies for failure assessment of nuclear reactor components
title_sort A discussion about simplified methodologies for failure assessment of nuclear reactor components
author CRUZ, J.R.B.
author_facet CRUZ, J.R.B.
LANDES, J.D.
PAES de ANDRADE, A.H.
ASME PRESSURE VESSEL AND PIPING CONFERENCE
author_role author
author2 LANDES, J.D.
PAES de ANDRADE, A.H.
ASME PRESSURE VESSEL AND PIPING CONFERENCE
author2_role author
author
author
dc.contributor.author.fl_str_mv CRUZ, J.R.B.
LANDES, J.D.
PAES de ANDRADE, A.H.
ASME PRESSURE VESSEL AND PIPING CONFERENCE
dc.subject.por.fl_str_mv reactor components
failures
pressure vessels
pipes
cracks
ductility
fracture properties
topic reactor components
failures
pressure vessels
pipes
cracks
ductility
fracture properties
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv July 21-26, 1996
dc.date.accessioned.fl_str_mv 2014-11-17T17:23:50Z
2014-11-18T17:21:54Z
2015-04-01T23:58:14Z
dc.date.available.fl_str_mv 2014-11-17T17:23:50Z
2014-11-18T17:21:54Z
2015-04-01T23:58:14Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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