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:
-
- 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), Reactor Fleet and Advanced Reactor Development. Nuclear Reactor Technologies
- 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. https://doi.org/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. https://doi.org/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 = {Thu Aug 02 00:00:00 EDT 2018},
month = {Thu Aug 02 00:00:00 EDT 2018}
}
Web of Science
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