Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
Autor(a) principal: | |
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Data de Publicação: | 2014 |
Outros Autores: | , , |
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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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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info:eu-repo/semantics/publishedVersion |
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info:eu-repo/semantics/openAccess |
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openAccess |
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I |
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