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| Content Provider | The American Society of Mechanical Engineers (ASME) Digital Collection |
|---|---|
| Author | Messner, M. C. Wang, Yanli Jetter, R. I. Sham, T. -L |
| Copyright Year | 2018 |
| Abstract | Design approaches using elastic perfectly-plastic (EPP) analysis have recently been approved as Code Cases for the Section III, Division 5 design of high-temperature nuclear reactor components made from austenitic stainless steel. These methods bound the ratcheting strain and creep-fatigue damage accumulated over the life of a component with a simplified, elastic-perfectly plastic analysis using a special pseudo-yield stress — often not equal to the true material yield stress. The austenitic materials specified in the existing Code cases are cyclic-hardening for all allowable operating temperatures. However, other Section III, Division 5 materials, such as Grade 91 steel, are cyclic softening at expected advanced reactor operating temperatures. This work describes the extension of EPP methods to cyclic softening materials through the use of a postulated saturated material state and softening factors to be applied to the pseudo yield stress. We demonstrate the conservatism of the modified EPP method against a series of inelastic simulations of two bar tests, using a constitutive model that captures work and cyclic softening. |
| Sponsorship | Pressure Vessels and Piping Division |
| File Format | |
| ISBN | 9780791851593 |
| DOI | 10.1115/PVP2018-84103 |
| Volume Number | Volume 1B: Codes and Standards |
| Conference Proceedings | ASME 2018 Pressure Vessels and Piping Conference |
| Language | English |
| Publisher Date | 2018-07-15 |
| Publisher Place | Prague, Czech Republic |
| Access Restriction | Subscribed |
| Subject Keyword | Creep Design methodology Fatigue High temperature Steel Stress Design Hardening Simulation Stainless steel Engineering simulation Nuclear reactors Damage Yield stress Constitutive equations Operating temperature |
| Content Type | Text |
| Resource Type | Article |
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