The Proceedings of the Materials and Mechanics Conference
Online ISSN : 2424-2845
2023
Session ID : CL0711
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Development of true stress-true strain relation for various structural materials in light water reactor plants
*Yukio TAKAHASHIHaruhisa SHIGEYAMA
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Abstract

Inelastic analysis considering individual material behavior is expected to play a more and more important role in design and fitness-for-service assessment of various facilities including nuclear power plants. Constitutive model is a fundamental element of such an analysis and modeling of stress-strain relations under uniaxial loading constitutes its basis. Some formulae for describing stress-strain relations under monotonically increasing loading have been developed and incorporated in some codes to provide a guidance for elastic-plastic analysis. The authors have been trying to find alternative formulae to improve the accuracy and widen the applicability. A simple formula based on the Swift-type equation was derived as a result of systematic analysis of the test data on a number of materials used in nuclear power plants. A new equation for estimating uniform elongation as a function of rupture elongation and reduction of area was derived. An alternative expression was also developed in order to circumvent the deficiency observed in ferritic steels. Formulae were found to be applicable to various materials such as austenitic stainless steels, high- and medium-strength ferritic steels and some of Nicked based alloys.

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© 2023 The Japan Society of Mechanical Engineers
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