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Finite Element Based Full-life Cyclic Stress Analysis of 316 grade Nuclear Reactor Stainless Steel under Constant, Variable and Random Fatigue Loading

[+] Author and Article Information
Bipul Barua

Argonne National Laboratory, Lemont, IL, USA
barua@anl.gov

Subhasish Mohanty

Argonne National Laboratory, Lemont, IL, USA
smohanty@anl.gov

Joseph Listwan

Argonne National Laboratory, Lemont, IL, USA
jlistwan@anl.gov

Saurin Majumdar

Argonne National Laboratory, Lemont, IL, USA
majumdar@anl.gov

Krishnamurti Natesan

Argonne National Laboratory, Lemont, IL, USA
natesan@anl.gov

1Corresponding author.

ASME doi:10.1115/1.4040790 History: Received March 22, 2018; Revised June 23, 2018

Abstract

Although S~N curve based approaches are widely followed for fatigue evaluation of nuclear reactor components and other safety critical structural systems, there is a chance of large uncertainty in estimated fatigue lives. Probably this uncertainty can be reduced by using more mechanistic approach such as using physics based 3D finite element (FE) methods. In our recent paper (Barua et al., 2018, Journal of Pressure Vessel Technology 140(1), pp 011403), we presented a fully mechanistic fatigue modeling approach which is based on time-dependent stress-strain evolution of material over the entire fatigue life. Based on this approach, in this work, we perform FE based cyclic stress analysis of 316 nuclear grade reactor stainless steel (SS) fatigue specimens, subjected to constant, variable, and random amplitude loading, for their entire fatigue lives. The simulated results are found to be in good agreement with experimental observation. We also perform an elastic-plastic analysis of a Pressurized Water Reactor (PWR) surge line (SL) pipe under idealistic fatigue loading condition and compared with experimental results.

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