Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems
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2005
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INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th
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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).
Como referenciar
MATTAR NETO, M.; CRUZ, J.R.B.; JONG, R.P. Influence of the materials mechanical properties on the structural integrity assessment of cracked piping of PWR nuclear reactors primary systems. In: INTERNATIONAL CONGRESS OF MECHANICAL ENGINEERING, 18th, November 6-11, 2005, Ouro Preto, MG. Proceedings... Disponível em: http://repositorio.ipen.br/handle/123456789/18335. Acesso em: 30 Dec 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.