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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: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. doi: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 = {2018},
month = {8}
}

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Works referenced in this record:

On some modifications of kinematic hardening to improve the description of ratchetting effects
journal, January 1991


Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
journal, December 2015

  • Wilhelm, Paul; Rudolph, Jürgen; Steinmann, Paul
  • Journal of Pressure Vessel Technology, Vol. 137, Issue 6
  • DOI: 10.1115/1.4029832

Modeling and Finite Element Simulation of Low Cycle Fatigue Behaviour of 316 SS
journal, January 2013


On the Plastic and Viscoplastic Constitutive Equations—Part II: Application of Internal Variable Concepts to the 316 Stainless Steel
journal, May 1983

  • Chaboche, J. L.; Rousselier, G.
  • Journal of Pressure Vessel Technology, Vol. 105, Issue 2
  • DOI: 10.1115/1.3264258

Time-independent constitutive theories for cyclic plasticity
journal, January 1986


Chaboche-based cyclic material hardening models for 316 SS–316 SS weld under in-air and pressurized water reactor water conditions
journal, August 2016


A Cyclic-Plasticity-Based Mechanistic Approach for Fatigue Evaluation of 316 Stainless Steel Under Arbitrary Loading
journal, December 2017

  • Barua, Bipul; Mohanty, Subhasish; Listwan, Joseph T.
  • Journal of Pressure Vessel Technology, Vol. 140, Issue 1
  • DOI: 10.1115/1.4038525

Study of Fatigue Initiation of Austenitic Stainless Steel in a High Temperature Water Environment and in Air Using Blunt Notch Compact Tension Specimens
conference, November 2015

  • Platts, Norman; Tice, David R.; Nicholls, Jennifer
  • ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards
  • DOI: 10.1115/PVP2015-45844

Proposal of Surface Finish Factor on Fatigue Strength in Design Fatigue Curve
conference, November 2014

  • Fukuta, Yuichi; Kanasaki, Hiroshi; Asada, Seiji
  • ASME 2014 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards
  • DOI: 10.1115/PVP2014-28601

Numerical Evaluation of Environmentally Assisted Fatigue (EAF) in Consideration of Recent Updates of the Formulas and Hold Time Effects
conference, November 2015

  • Reese, Sven H.; Seichter, Johannes; Klucke, Dietmar
  • ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards
  • DOI: 10.1115/PVP2015-45020

A Comparison of Different Design Codes on Fatigue Life Assessment Methods
conference, December 2016

  • Shi, Jinhua; Wei, Liwu; Faidy, Claude
  • ASME 2016 Pressure Vessels and Piping Conference, Volume 1B: Codes and Standards
  • DOI: 10.1115/PVP2016-63040

Effect of Pressurized Water Reactor Environment on Material Parameters of 316 Stainless Steel: A Cyclic Plasticity Based Evolutionary Material Modeling Approach
conference, November 2015

  • Mohanty, Subhasish; Soppet, William K.; Majumdar, Saurindranath
  • ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards
  • DOI: 10.1115/PVP2015-45701

Fatigue Modeling of 508 LAS Under Variable Amplitude Loading: A Mechanistic Based Analytical Approach
conference, October 2017

  • Barua, Bipul; Mohanty, Subhasish; Soppet, William K.
  • ASME 2017 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards
  • DOI: 10.1115/PVP2017-65876