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

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

Journal Article · Thu Aug 02 00:00:00 EDT 2018 · Journal of Pressure Vessel Technology

DOI:https://doi.org/10.1115/1.4040790· OSTI ID:1491264

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

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

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.

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1491264

Journal Information:: Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 5 Vol. 140; ISSN 0094-9930

Publisher:: ASMECopyright Statement

Country of Publication:: United States

Language:: English

References (13)

Time-independent constitutive theories for cyclic plasticity Chaboche, J. L. International Journal of Plasticity, Vol. 2, Issue 2 https://doi.org/10.1016/0749-6419(86)90010-0	journal	January 1986
On some modifications of kinematic hardening to improve the description of ratchetting effects Chaboche, J. L. International Journal of Plasticity, Vol. 7, Issue 7 https://doi.org/10.1016/0749-6419(91)90050-9	journal	January 1991
Chaboche-based cyclic material hardening models for 316 SS–316 SS weld under in-air and pressurized water reactor water conditions Mohanty, Subhasish; Soppet, William K.; Majumdar, Saurindranath Nuclear Engineering and Design, Vol. 305 https://doi.org/10.1016/j.nucengdes.2016.05.031	journal	August 2016
Modeling and Finite Element Simulation of Low Cycle Fatigue Behaviour of 316 SS Shit, J.; Dhar, S.; Acharyya, S. Procedia Engineering, Vol. 55 https://doi.org/10.1016/j.proeng.2013.03.330	journal	January 2013
On the Plastic and Viscoplastic Constitutive Equations—Part II: Application of Internal Variable Concepts to the 316 Stainless Steel Chaboche, J. L.; Rousselier, G. Journal of Pressure Vessel Technology, Vol. 105, Issue 2 https://doi.org/10.1115/1.3264258	journal	May 1983
Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels Wilhelm, Paul; Rudolph, Jürgen; Steinmann, Paul Journal of Pressure Vessel Technology, Vol. 137, Issue 6 https://doi.org/10.1115/1.4029832	journal	December 2015
A Cyclic-Plasticity-Based Mechanistic Approach for Fatigue Evaluation of 316 Stainless Steel Under Arbitrary Loading Barua, Bipul; Mohanty, Subhasish; Listwan, Joseph T. Journal of Pressure Vessel Technology, Vol. 140, Issue 1 https://doi.org/10.1115/1.4038525	journal	December 2017
Proposal of Surface Finish Factor on Fatigue Strength in Design Fatigue Curve Fukuta, Yuichi; Kanasaki, Hiroshi; Asada, Seiji ASME 2014 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards https://doi.org/10.1115/PVP2014-28601	conference	November 2014
Numerical Evaluation of Environmentally Assisted Fatigue (EAF) in Consideration of Recent Updates of the Formulas and Hold Time Effects Reese, Sven H.; Seichter, Johannes; Klucke, Dietmar ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards https://doi.org/10.1115/PVP2015-45020	conference	November 2015
Effect of Pressurized Water Reactor Environment on Material Parameters of 316 Stainless Steel: A Cyclic Plasticity Based Evolutionary Material Modeling Approach Mohanty, Subhasish; Soppet, William K.; Majumdar, Saurindranath ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards https://doi.org/10.1115/PVP2015-45701	conference	November 2015
Study of Fatigue Initiation of Austenitic Stainless Steel in a High Temperature Water Environment and in Air Using Blunt Notch Compact Tension Specimens Platts, Norman; Tice, David R.; Nicholls, Jennifer ASME 2015 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards https://doi.org/10.1115/PVP2015-45844	conference	November 2015
A Comparison of Different Design Codes on Fatigue Life Assessment Methods Shi, Jinhua; Wei, Liwu; Faidy, Claude ASME 2016 Pressure Vessels and Piping Conference, Volume 1B: Codes and Standards https://doi.org/10.1115/PVP2016-63040	conference	December 2016
Fatigue Modeling of 508 LAS Under Variable Amplitude Loading: A Mechanistic Based Analytical Approach Barua, Bipul; Mohanty, Subhasish; Soppet, William K. ASME 2017 Pressure Vessels and Piping Conference, Volume 1A: Codes and Standards https://doi.org/10.1115/PVP2017-65876	conference	October 2017

Similar Records

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

Journal Article · Mon Dec 04 19:00:00 EST 2017 · Journal of Pressure Vessel Technology · OSTI ID:1426765

3D-FE Modeling of 316 SS under Strain-Controlled Fatigue Loading and CFD Simulation of PWR Surge Line

Technical Report · Tue Feb 28 23:00:00 EST 2017 · OSTI ID:1375458

Implementation of ANL’s Mechanics Based Evolutionary Fatigue Modeling Through ABAQUS-WARP3D Based High-Performance Computing Framework

Technical Report · Fri Apr 27 00:00:00 EDT 2018 · OSTI ID:1480516

Related Subjects

36 MATERIALS SCIENCE
fatigue
fatigue life
finite element analysis
hardening
modeling
nuclear reactors
pressurized water reactors
stainless steel
stress
stress analysis

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

Citation Formats

References (13)

Similar Records

Related Subjects