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.
Original language | English |
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Title of host publication | Codes and Standards |
Publisher | American Society of Mechanical Engineers (ASME) |
ISBN (Electronic) | 9780791851593 |
DOIs | |
State | Published - 2018 |
Event | ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic Duration: Jul 15 2018 → Jul 20 2018 |
Publication series
Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
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Volume | 1B-2018 |
ISSN (Print) | 0277-027X |
Conference
Conference | ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 |
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Country/Territory | Czech Republic |
City | Prague |
Period | 07/15/18 → 07/20/18 |
Funding
This manuscript has been co-authored by UChicago Argonne LLC under Contract No. DE-AC02-06CH11357, and by UT-Battelle LLC, under Contract No. DE-AC05-00OR22725, with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan: (http://energy.gov/downloads/doe-public-access-plan). The research was sponsored by the U.S. Department of Energy, under Contract No. DE-AC02-06CH11357 with Argonne National Laboratory, managed and operated by UChicago Argonne LLC, and under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed and operated by UT-Battelle LLC. Programmatic direction was provided by the Office of Nuclear Energy.