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RATCHET BOUNDARY EVALUATION AND COMPARISON WITH RATCHETING EXPERIMENTS INVOLVING STRAIN HARDENING MATERIAL MODELS

机译:涉及应变硬化材料模型的棘轮边界评估与棘轮实验的比较

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Pressure components in nuclear power plants are designed to prevent the failure mechanism of incremental deformation or "ratcheting" due to the simultaneous application of mechanical loads such as pressure and cyclic loads. Design criteria using elastic methods that are specified in NB-3200 of ASME Section III Code are derived from a perfectly-plastic material model. The Code allows the use of plastic methods to demonstrate an acceptable response to cyclic loading, but does not provide clear guidance on any specific plasticity model to use. It has been shown in previous studies that some strain hardening plasticity models are unsuitable for establishing the absence of ratcheting. In this paper, the ratchet boundary obtained from the perfectly plastic and the strain hardening Armstrong-Frederick material models are examined based on the published experimental investigations of the classical Bree problem, pipe bends under in-plane bending and tension-torsion tests. Suitable criteria for evaluating the cyclic analysis response are discussed.
机译:核电厂中的压力组件旨在防止由于同时施加机械负载(例如压力和循环负载)而导致增量变形或“棘轮”的失效机理。 ASME第III部分NB-3200中指定的使用弹性方法的设计标准是从完全塑性材料模型得出的。该规范允许使用塑性方法来证明对循环载荷的可接受的响应,但未提供有关使用任何特定塑性模型的明确指南。在先前的研究中已经表明,某些应变硬化可塑性模型不适用于确定没有棘齿。在本文中,基于已发布的经典Bree问题,面内弯曲下的管子弯曲和张力-扭转测试的实验研究,研究了从完全塑性和应变硬化Armstrong-Frederick材料模型获得的棘轮边界。讨论了评估循环分析响应的合适标准。

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