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

Barua, Bipul; Mohanty, Subhasish; Listwan, Joseph T.; Majumdar, Saurindranath; Natesan, Krishnamurti

doi:10.1115/1.4040790

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:

Barua, Bipul ^[1]; Mohanty, Subhasish ^[1]; Listwan, Joseph T. ^[1]; Majumdar, Saurindranath ^[1]; Natesan, Krishnamurti ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)

Publication Date:: Thu Aug 02 00:00:00 EDT 2018

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.

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                    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

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                    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.

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@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}

}

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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

Chaboche, J. L.
International Journal of Plasticity, Vol. 7, Issue 7
DOI: 10.1016/0749-6419(91)90050-9

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

Shit, J.; Dhar, S.; Acharyya, S.
Procedia Engineering, Vol. 55
DOI: 10.1016/j.proeng.2013.03.330

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, J. L.
International Journal of Plasticity, Vol. 2, Issue 2
DOI: 10.1016/0749-6419(86)90010-0

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

Mohanty, Subhasish; Soppet, William K.; Majumdar, Saurindranath
Nuclear Engineering and Design, Vol. 305
DOI: 10.1016/j.nucengdes.2016.05.031

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

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Similar Records

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

Abstract

Citation Formats

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

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

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

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

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

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

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

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

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

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

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

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
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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

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

Numerical Evaluation of Environmentally Assisted Fatigue (EAF) in Consideration of Recent Updates of the Formulas and Hold Time Effects
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A Comparison of Different Design Codes on Fatigue Life Assessment Methods
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