Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems

Detalhes bibliográficos
Autor(a) principal: MATTAR NETO, M.
Data de Publicação: 2014
Outros Autores: CRUZ, J.R.B., JONG, R.P., INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/18335
Resumo: The structural integrity assessment methods of cracked components manufactured with ductile materials request the evaluation of parameters of the Elastic-Plastic Fracture Mechanics (EPFM) and of the Limit Load Analysis (LL). Since the use of numerical methods to apply the concepts of EPFM and LL may be costly and time demanding, the existence of the so-called simplified methods for cracked piping evaluation is still considered of great relevance. The following simplified methods for evaluation of the ductile behavior of piping systems are available in the literature and were considered in this work: J-T Method (J Integral versus the Tearing Modulus T), R6 Method and DPFAD Method (Deformation Plasticity Failure Assessment Diagram). The methods were applied for the computation of instability loads of some piping systems, with through-wall circumferential cracks, subjected to bending moments, made with high toughness steels. Changes in the values of the materials properties were considered. The estimated instability loads were compared with experimental results obtained in the literature. From those comparisons, some conclusions and comments could be made, being the main focus of the work the aspects related to the characterization of the materials properties to the appropriate application of the methods to cracked piping of pressurized water nuclear reactor (PWR) primary systems, in evaluations of the LBB (Leak-Before-Break) concept. As the methods are strongly dependent on the properties, some recommendations must be followed. These properties are basically expressed by means of the stressstrain curves and fracture resistance curves (JR curves).
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spelling 2014-11-17T18:45:53Z2014-11-18T18:52:16Z2015-04-02T02:32:05Z2014-11-17T18:45:53Z2014-11-18T18:52:16Z2015-04-02T02:32:05ZNovember 6-11, 2005http://repositorio.ipen.br/handle/123456789/18335The structural integrity assessment methods of cracked components manufactured with ductile materials request the evaluation of parameters of the Elastic-Plastic Fracture Mechanics (EPFM) and of the Limit Load Analysis (LL). Since the use of numerical methods to apply the concepts of EPFM and LL may be costly and time demanding, the existence of the so-called simplified methods for cracked piping evaluation is still considered of great relevance. The following simplified methods for evaluation of the ductile behavior of piping systems are available in the literature and were considered in this work: J-T Method (J Integral versus the Tearing Modulus T), R6 Method and DPFAD Method (Deformation Plasticity Failure Assessment Diagram). The methods were applied for the computation of instability loads of some piping systems, with through-wall circumferential cracks, subjected to bending moments, made with high toughness steels. Changes in the values of the materials properties were considered. The estimated instability loads were compared with experimental results obtained in the literature. From those comparisons, some conclusions and comments could be made, being the main focus of the work the aspects related to the characterization of the materials properties to the appropriate application of the methods to cracked piping of pressurized water nuclear reactor (PWR) primary systems, in evaluations of the LBB (Leak-Before-Break) concept. As the methods are strongly dependent on the properties, some recommendations must be followed. These properties are basically expressed by means of the stressstrain curves and fracture resistance curves (JR curves).Made available in DSpace on 2014-11-17T18:45:53Z (GMT). No. of bitstreams: 0Made available in DSpace on 2014-11-18T18:52:16Z (GMT). No. of bitstreams: 1 11046.pdf: 1315848 bytes, checksum: b54d334969b3eb214bdd0eaf46f1ac9e (MD5)Made available in DSpace on 2015-04-02T02:32:05Z (GMT). No. of bitstreams: 1 11046.pdf: 1315848 bytes, checksum: b54d334969b3eb214bdd0eaf46f1ac9e (MD5)materials testing reactorsmechanical propertiesmechanical structurescrackspipesfracture mechanicsleaksInfluence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systemsinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectCOBEMIOuro Preto, MGMATTAR NETO, M.CRUZ, J.R.B.JONG, R.P.INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18thinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN110462005MATTAR NETO, M.66-66Proceedings7017293102MATTAR NETO, M.:70:21:SCRUZ, J.R.B.:1729:-1:NJONG, R.P.:3102:-1:NORIGINAL11046.pdfapplication/pdf1315848http://repositorio.ipen.br/bitstream/123456789/18335/1/11046.pdfb54d334969b3eb214bdd0eaf46f1ac9eMD51123456789/183352022-04-29 12:36:16.479oai:repositorio.ipen.br:123456789/18335Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-04-29T12:36:16Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
title Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
spellingShingle Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
MATTAR NETO, M.
materials testing reactors
mechanical properties
mechanical structures
cracks
pipes
fracture mechanics
leaks
title_short Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
title_full Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
title_fullStr Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
title_full_unstemmed Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
title_sort Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
author MATTAR NETO, M.
author_facet MATTAR NETO, M.
CRUZ, J.R.B.
JONG, R.P.
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th
author_role author
author2 CRUZ, J.R.B.
JONG, R.P.
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th
author2_role author
author
author
dc.contributor.author.fl_str_mv MATTAR NETO, M.
CRUZ, J.R.B.
JONG, R.P.
INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th
dc.subject.por.fl_str_mv materials testing reactors
mechanical properties
mechanical structures
cracks
pipes
fracture mechanics
leaks
topic materials testing reactors
mechanical properties
mechanical structures
cracks
pipes
fracture mechanics
leaks
description The structural integrity assessment methods of cracked components manufactured with ductile materials request the evaluation of parameters of the Elastic-Plastic Fracture Mechanics (EPFM) and of the Limit Load Analysis (LL). Since the use of numerical methods to apply the concepts of EPFM and LL may be costly and time demanding, the existence of the so-called simplified methods for cracked piping evaluation is still considered of great relevance. The following simplified methods for evaluation of the ductile behavior of piping systems are available in the literature and were considered in this work: J-T Method (J Integral versus the Tearing Modulus T), R6 Method and DPFAD Method (Deformation Plasticity Failure Assessment Diagram). The methods were applied for the computation of instability loads of some piping systems, with through-wall circumferential cracks, subjected to bending moments, made with high toughness steels. Changes in the values of the materials properties were considered. The estimated instability loads were compared with experimental results obtained in the literature. From those comparisons, some conclusions and comments could be made, being the main focus of the work the aspects related to the characterization of the materials properties to the appropriate application of the methods to cracked piping of pressurized water nuclear reactor (PWR) primary systems, in evaluations of the LBB (Leak-Before-Break) concept. As the methods are strongly dependent on the properties, some recommendations must be followed. These properties are basically expressed by means of the stressstrain curves and fracture resistance curves (JR curves).
publishDate 2014
dc.date.evento.pt_BR.fl_str_mv November 6-11, 2005
dc.date.accessioned.fl_str_mv 2014-11-17T18:45:53Z
2014-11-18T18:52:16Z
2015-04-02T02:32:05Z
dc.date.available.fl_str_mv 2014-11-17T18:45:53Z
2014-11-18T18:52:16Z
2015-04-02T02:32:05Z
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