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Title: Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading

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. This uncertainty may be reduced by using a more mechanistic approach such as physics based three-dimensional (3D) finite element (FE) methods. In a recent paper (Barua et al., 2018, ASME J. Pressure Vessel Technol., 140(1), p. 011403), a fully mechanistic fatigue modeling approach which is based on time-dependent stress–strain evolution of material over the entire fatigue life was presented. Based on this approach, FE-based cyclic stress analysis was performed on 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. An elastic-plastic analysis of a pressurized water reactor (PWR) surge line (SL) pipe under idealistic fatigue loading condition was performed and compared with experimental results.

Authors:
 [1];  [1];  [1];  [1];  [1]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7)
OSTI Identifier:
1491264
Grant/Contract Number:  
AC02-06CH11357
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Pressure Vessel Technology
Additional Journal Information:
Journal Volume: 140; Journal Issue: 5; Journal ID: ISSN 0094-9930
Publisher:
ASME
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; fatigue; stress; hardening; finite element analysis; modeling; fatigue life; nuclear reactors; stainless steel; stress analysis; pressurized water reactors

Citation Formats

Barua, Bipul, Mohanty, Subhasish, Listwan, Joseph T., Majumdar, Saurindranath, and Natesan, Krishnamurti. Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading. United States: N. p., 2018. Web. doi:10.1115/1.4040790.
Barua, Bipul, Mohanty, Subhasish, Listwan, Joseph T., Majumdar, Saurindranath, & Natesan, Krishnamurti. Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading. United States. doi:10.1115/1.4040790.
Barua, Bipul, Mohanty, Subhasish, Listwan, Joseph T., Majumdar, Saurindranath, and Natesan, Krishnamurti. Thu . "Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading". United States. doi:10.1115/1.4040790. https://www.osti.gov/servlets/purl/1491264.
@article{osti_1491264,
title = {Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading},
author = {Barua, Bipul and Mohanty, Subhasish and Listwan, Joseph T. and Majumdar, Saurindranath and Natesan, Krishnamurti},
abstractNote = {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. This uncertainty may be reduced by using a more mechanistic approach such as physics based three-dimensional (3D) finite element (FE) methods. In a recent paper (Barua et al., 2018, ASME J. Pressure Vessel Technol., 140(1), p. 011403), a fully mechanistic fatigue modeling approach which is based on time-dependent stress–strain evolution of material over the entire fatigue life was presented. Based on this approach, FE-based cyclic stress analysis was performed on 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. An elastic-plastic analysis of a pressurized water reactor (PWR) surge line (SL) pipe under idealistic fatigue loading condition was performed and compared with experimental results.},
doi = {10.1115/1.4040790},
journal = {Journal of Pressure Vessel Technology},
number = 5,
volume = 140,
place = {United States},
year = {2018},
month = {8}
}

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Works referenced in this record:

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