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Research Papers: Materials and Fabrication

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

[+] Author and Article Information
Bipul Barua, Joseph T. Listwan, Saurindranath Majumdar, Krishnamurti Natesan

Argonne National Laboratory,
Lemont, IL 60440

Subhasish Mohanty

Argonne National Laboratory,
Lemont, IL 60440
e-mail: smohanty@anl.gov

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received March 22, 2018; final manuscript received June 23, 2018; published online August 2, 2018. Assoc. Editor: Steve J. Hensel.The United States Government retains, and by accepting the article for publication, the publisher acknowledges that the United States Government retains, a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this work, or allow others to do so, for United States government purposes.

J. Pressure Vessel Technol 140(5), 051403 (Aug 02, 2018) (8 pages) Paper No: PVT-18-1061; doi: 10.1115/1.4040790 History: Received March 22, 2018; Revised June 23, 2018

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, in this work, 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.

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References

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Figures

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Fig. 1

Block loading during (a) variable amplitude and (b) random amplitude fatigue tests

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Fig. 2

Geometry information of actual specimen and FE modeled equivalent specimen

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Fig. 3

(a) Three-dimensional-FE simulated versus experimental axial stress of constant-amplitude fatigue specimen for whole fatigue life. Magnified versions showing that the 3D-FE results can predict the material behavior during (b) initial stress hardening, softening, and stabilized cycles; and (c) rapid crack propagation and failure under constant amplitude loading. Predictions are from simulation using time-dependent parameters estimated from constant-amplitude fatigue test.

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Fig. 4

(a) Three-dimensional-FE simulated versus experimental axial stress of variable-amplitude fatigue specimen for whole fatigue life. Magnified versions showing that the 3D-FE results can predict the material behavior during (b) initial stress hardening, softening, and stabilized cycles; and (c) rapid crack propagation and failure under variable amplitude loading. Predictions are from simulation using time-dependent parameters estimated from variable-amplitude fatigue test.

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Fig. 5

Simulated versus experimental axial stress history of (a) constant- and (b) variable-amplitude test. Predictions are from simulation using APSE-dependent parameters estimated from variable-amplitude test.

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Fig. 6

(a) Three-dimensional-FE simulated versus experimental axial stress of random-amplitude test during. (b) Magnified version of a, and (c) corresponding hysteresis plot. Predictions are from simulation using APSE-dependent material parameters estimated from variable-amplitude test.

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Fig. 7

Flowchart showing the steps in mechanics-based fatigue-modeling framework

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Fig. 8

(a) FE mesh of the PWR surge line. Arrows indicate fixed displacement boundary conditions applied at both ends and the location and direction of cyclic displacement applied near one end. (c) Profile of the applied cyclic displacement.

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Fig. 9

Contour plot of the von Misses stress at an instant during the displacement control fatigue loading shown in Fig. 8. The highlighted element in the magnified inset is the element of interest for analyzing results from simulation.

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Fig. 10

(a) Simulated (elastic-plastic analysis) ɛz as function of fatigue cycles. Simulated (elastic-plastic analysis) versus experimental (b) maximum principal stress, (c) mid principal stress, and (d) minimum principal stress as function of fatigue cycles. Experimental results are shown for first 100 cycles. Simulation was performed for only 100 cycles.

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Fig. 11

Simulated (elastic-plastic analysis) versus experimental von Mises stress amplitudes as function of fatigue cycles. Simulation was performed for only 100 cycles.

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